ML20032B841
| ML20032B841 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/01/1981 |
| From: | BECHTEL GROUP, INC. |
| To: | |
| Shared Package | |
| ML20032B836 | List: |
| References | |
| 13587-2-G01-101, 13587-2-G1-101, NUDOCS 8111060431 | |
| Download: ML20032B841 (24) | |
Text
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13587-2-G01-101
~g (Tf DESIGN CRITERIA DOCUMENTS COVER SHEET CONTAINMENT RECOVERY SERVICE BUILDING FOR GPUSERVICE[ CORPORATION THREE MILE IS, LAND--bl:IT 2 13587 General JO B N a:
. DISCIPLINE.
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JOB NO. 13587 REV.
DISCIPLINE l
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DESIGN CRITERI A DOCUMENTS 2
REVISION STATUS SHEET PAGE i
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O 13SS7-2-G01-101 CONTAINMENT RECOVERY SERVICE BUILDING DESIGN CRITERIA TABLE OF CONTENTS SECTION' PAGE 1.0~
FUNCTION 1
1 2.0 SCOPE 2
^
i 3.0 INTERFACES 3
4.0 FUNCTIONAL REQUIREMENTS 5
4.1 Functions 5
4.2 Accessibility 5
4.3 Maintainability 6
4.4 Personnel 6
4.5 Safety 6
4.6 Contamination Control 7
5.0 DESIGN REQUIREMENTS 7
5.1 Safety Design Bases
'7 5.2 General Design Bases 7
5.3 Codes, Standards, and Regulatory Rewquirements 8
5.4 Civil / Structural / Architectural Requirements 10 5.5 Layout Requirements 13 5.6 Systems Design 15 5.7 Control Systets Requirements 18 5.8 Electrical Requirements 18
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6.0 REFERENCES
20 7.0 GENERAL DESIGN CRITERIA EXCEPTIONS 20 7.1 General Section 20 7.2 Architectural Section 20 7.3 Civil / Structural Section 20 2
7.4 Control Systems Section 20 7.5 Electrical Section 21 7.6 Plant Design / Mechanical Section 21 7.7 Nuclear Section 21 l
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k ii Rev. 2
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13587-2-G01-101 DESIGN CRITERIA FOR CONTAINMENT RECOVERY SERVICE BUILDING t
FOR GPU SERVICE CORPORATION s
THREE MILE ISLAND--UNIT 2 1.0 FUNCTQN The Containment Recovery Service Building (CRSB) will provide space to l1 mobilize equipment'and materials needed to support the in-containment decontamination efforts.
Close proximity to the equipment hatch maximizes productivity of personnel who are working in radiation areas.
Since work inside the reactor building will. require a large quantity of materials to be brought into and taken out of the reactor building, contamination control and minimizing worker radiation exposures are important consid-erations.
The containment recovery serv b. building will be constructed to serve the following functions:
1.1 Maintain contamination control during reactor building cleanup lal all phases of the containment recovery l1 1.2 Provide efficient personnel access to the reactor building during
- 1. 3 Allow passage of large pieces of equipment and the removal of bulk
[1 radwaste without opening the reactor building directly to the atmosphere 1.4 Serve as a staging area to decontaminate and/or package contam-l1 inated equipment removed frc.: Qe reactor building 1.5 Provide for a hot tool crib (during early stages of recovery only) l1 in the vicinity of the reactor building to irrprove work efficiency
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- 1. 6 Provide space for various reactor building service systems l1 i
1.7 Provide a facility to serve as the primary reactor building air l1 boundary when the equipment hatch is open
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- 1. 8 Provide access areas for on-and off.aading of trucks l1 l3
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- 1. 9 Provide an area to accomplish tasks away from the reactor building thereby minimizing personnel doses and easing congestian in the reactor
. building
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Page 1 l
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13587-2-G01-101 1.10 Provide space for decontiminating equipment l1 2.0 SCOPE 2.1 The CRSB will be comprised of the following areas:
2.1 1 Interim staging area ('for radioactive materials) l 2.1.2 Decontamination area 2.1.3 Containment air control envelope (CACE) 2.1.4 Truck bay 2.1.5 General Work - This area may be used for a variety of activities including clean storage, packaging, heavy equipment access, shipment staging, waste compacting, containment staging, and mockups.
2.2 These design criteria delineate the requirements for the following:
2.2.1 Civil / Structural / Architectural 2.2.1.1 Design Bases 2.2.1.2 Design Loads 2.2.1.3 Painting and Coating 2.2.2 Mechanical and Plant Design J
k 2.2.2.1 Layout 2.2.2.2 Material Handling 2.2.2.3 Contamination Control 1
2.2.2.4 Demineralized Water 2.2.2.5 Fire Detection and Extinguishing 2.2.2.6 Floor Drains 2.2.2.7 Service Air j
2.2.2.6 HVAC 2.2.2.9 Roof Drainage 2.2.3 Control Systems 1
1 2.2.3.1 Radiation Monitoring 2.2.3.2 Communications Page 2 Rev. 1
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13587-2-G01-101 I1 2.2.4 Electrical 2.2.4.1 Power Systems 2.2.4.2 Normal Lighting 2.2 A.3 EmergenchLighting 2.2.4.4 Exterie Jghting q
2.2.4.5 Raceway 2.2.4.6 Cable 2.2.4.7 Grounding This criteria document addresses essential design requirements.
Addi-tional criteria are delineated in the General Project Design Criteria 13587-2-G01-100.
It is recog.tized that specific design features and equipment may be required in addition to those features explicitly described, to implement the overall criteria.
3.0 INTERFACES 3.1 The CRSB interfaces the following structures and systems:
3.1.1 Reactor Building The CRSB is not a seismic Category I building.
It will be adjacent to the reactor building; thus it will be checked to assure that, during a safe shutdown earthquake (SSE), it will not fail and damage the struc-tural integrity of the reactor building.
The CRSB is the primary point j
of entry and exit of personnel to and from the reactor building.
3.1.2 Personnel Access Facility (PAF)
The PAF is the point of entry and exit of personnel to and from the CRSB.
3.2 The design of the containment recovery service building will con-sider the interface with the following process / utility systems, and incorporate the required interface provisions.
i 3.2.1 Demineralized Water System i
A supply header will tii into an existing header, to provide service to l
the CRSB.
3.2.2 Fire Protection System 3.2.2.1 A supply header will tie into existing 12-inch NPS fire protec-tion system yard loop piping to provide service to the CRSB.
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j 13587-2-G01-101 W
l 3.2.2.2 The CRSB fire protection system alarms will tie into the existing fire protection alarm system in the main control room.
l 3.2.3 Floor Drain System The floor drainage system sump pump discharge piping will be rcuted to the. Unit 2 auxiliary building sump.
The truck bay surnp pump discharges
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g will be conveyed to the Unit 2 auxiliary building sump or the storm drain system.
3.2.4 Service Air System' I
A supply header will tie into an existing service air header to provide service to the CRSB for service an and breathing air.
3.2.5 HVAC System The CRSB HVAC system will provide supply and exhaust for the PAF disrobe area. This will provide separation of the clean and contaminated areas within tne PAF.
The CRSB ventilation system will interface with the reactor building as an operational requirement for controlling airflow between these buildings.
The CRSB ventilation system will interface with the smoke detection / fire alarm system as required by NFPA 90A.
3.2.6 Electrical Service The CRSB will interface with the plant electrical system to receive 4160 volt, 3 phase, 60 Hertz power and 125 volt DC' power for unit sub-i station breaker control.
3.2.7 Communications System The CRSB will require an interface with the plant communications system to permit coordinated activity between the facility and ',he rest of the plant.
The CACE will interface with a radio communication system c(nnecting the command center, the CACE and the reactor building for the purpose of serving the decontamination effort.
3.2.8 Roof Drain System The CRSB roof drains will tie into existing yard storm drain system.
3.3 BURIED SAFETY-RELATED PIPING AND CABLE The design of the CRSB will consider underground piping and cable in its vicinity.
The CRSB shall not adversely affect buried safety-related piping and cable.
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i 13587-2-G01-101 i
4.0 FUNCTIONAL REQUIREMENTS k
1 d.1 FUNCTIONS t
4.1.1 The CRSB will allow the equipment hatch to be removed during the i
reactor building cleanup.
The equipment hatch and the No. I personne;-
airlock can be decontaminated 'and moved to a storage area outside of the building.
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t 4.1.2 When the equipment. hatch.is removed, the CACE will provide the -
required reactor. building air boundary.
During the decontamination and i
defueling phases, the CACE will, limit the uncontrolled release of air- -
a 4,r borne particles and radioactive gases to the outside environment, and
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will contain the contamint.nts from inside the reactor building.
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4.1.3 The reactor but cing cleanup and decontamination will result !n a large quantity of contaminated materials being brought out of the reactor building for shipment as radwaste.
Some of the packaging can be done
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inside the reacte. building, however, the CRSB service areas will allow j
the decontamination and packaging to be done in low rodiation fields and free valuable containment space for other construction efforts.
l The layout of the CRSB will provide an area for a hot tool c' rib
.r 4.1.4 near the equipment batch, until radiation levels permit moving the tool crib inside the reactor building.
4.1.5 The CRSB will contain areas providing for interim staging of material removed from the reactor building.
4.2 ACCESSIBILITY 4.2.1 Access to the CRSB will be controlled and restricted.
Personnel ingress and egress of the CRSB will be through the PAF; emergency exits will be provided.
4.2.2 Equipment and material movement to and from the CRSB will be through the truck bay and heavy equipment access doors.
Vehicle doors to the truck bay and the heavy equipment access area will be locked.
Trucks will enter and exit only under Health Physics (HP) control.
II 4.2.3 Personnel entry to the interim staging area and the decor,tami-nation area will be under direct HP control.
l 4.2.4 The CACE will be the primary control point for personnel and material movement into the reactor building.
The CACE will provide the control barrier for sirborne contamination from the containment.
4.2.5 Contaminated laundry and respirators / air masks from the PAF will be loaded on trucks in the heavy equipment access area.
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13587-2-G01-101 s
2 MAINTAINABILITY
,.3.1 The CRSB floor and interior wall surface (to an elevation 10 feet above the floor) shall be coated to facilitate decontamination.
The g
amount of contamination :f surfaces above 10 feet should be minimal.
Cranes, monorail equipment, and when practical, piping will be located mora.than 10 feet above the floor.
f 4.3.2 Permanent and temporary (movable) shielding will be provided for use in the CRSB as required to ensure that personnel exposure is as low as reasonably achievable.
4.3.3 A transfer cart, underhung monorail, underhung bridge crane, and forklifts will be provided for the movement of large items within the CRSB.
4.3.4 Provision will be made for the removal of the equipment hatch.
4.3.5 Provision will be made for movement of the shield door.
4.4 PERSONNEL ThenumberandcraftofrecoveryandmaintenancepersonnelcalledIpon will depend upon what tasks are expected to be performed.
However, for facility sizing, 150 personnel are assumed to be present at one time.
Of the 150 personnel,100 will be in transit to the reactor building and 50 will be employed,. full time, in the CRSB.
It is estimated that six health physics technicians will be needed in the CRSB during normal recovery operatians.
4.5 SAFETY 4.5.1 The CRSB will be designed as a radiation area and provision shall be made to shield recovery and maintenance personnel from direct radia-tion as much as practicable.
However. radiation levels will vary within the CRSB due to n.0vement of material through tne staging, storage, and decon areas.
4.5.2 The concentration of airborne contamination will be maintained during normal facility operations below maximam permissible concentra-tions (MPC) per 10 CFR 20, Appendix B, Table I, Column I.
4.5.3 The facility shall have at least two emergency exits.
4.5.4 Portable or local safety eq"ipment shall be locatec in the 'acility.
These shall include:
a.
Fire extinguishers and hose cc:ripets b.
Emergency ~ shower and eyewash fountains c.
nadiation monitoring equipment d.
Emergency lighting Page 6 Rev. 1
13387-2-G01-101 4.5.5 Appropriate signs shall be used for exits, fire equipment, and safety equipment.
4.5.6 All electrical equipment shall be grounded in accordance with it applicable codes and regulations.
4.6, CONTAMINATION CONTROL 4.6.1 Control of. potential. radioactive contamination in the CRSB struc-f ture and the equipment contained therein will be established primarily' by preventive measures.
Material will be decontaminated (if required),
sorted, and packaged in the reactor building prior to its movement into the CACE and CRSB.
4.6.2 Further decontamination, as required, of material in the CRSB and subsequent radioactive waste management activities will take place in the decontamination area of the CRSB.
4.6.3 Movement of material in the CRSB will primarily be by monorail or bridge crane.
Such transport in suspension is designed to minimize the spread of contamination through " tracking."
4.6.4 The CRSB ventilation system provides for movement of potential airborne contamination from clean to higher contamination areas.
3.0 DESIGN REQUIREMENTS 5.1 SAFETY DESIGN BASES The CRSB serves no nuclear safety related functions.
Nuclear safety-related function is defined in Reference 6.5.
The-CRSB will not hinder i
3 the safety-related function of any existing system or structure.
5.2 GENERAL DESIGN BASES 5.2.1 Since the equipment hatch may be removed anytime during the recovery operation, the design of the CRSB will permit transporting the 1
equipment hatch from the CRSB.
5.2.2 The CRSB will be designed with the following general bases:
l1 5.2.2.1 Seismic separation from the reactor building to assure that the l1 seismic responses of the reactor building are not altered l
- 5. 2. 2. 2 Sloped floor with drains to sumps to collect liquids for rad-y j
waste processing l
5.2.2.3 A dedicated truck bay area l 1 5.2.2.4 Designed for ease of decontamination
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l 5.2.2.5 Designed for design basis winds as defined in the TMI-2 Final l 1 Safety Analysis Report (Section 3.3.1.)
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13587-2-G01-101 5.2.2.6 Designed as a low air leakage, negative pressure building with outside air leakage into the building 5.2.2.7 Filter and monitor exhaust air for control of releases 5.2.2.8 Hose stations, fire extinguishers, and/or sprinklers for f, ire prot,ection; fire detection and alarm systems.
j 5.2.2.9 Area and process radiation monitors and alarms 5.2.2.10 The facility shall be designed in accordance with the follow-ing indoor conditions:
2 Summer Temperature (maximum) 104 F Winter Temperature (minimum) 50 F
- 5. 2. 3 The containment air control envelope will be designed to serve as an air control boundary for the containment atmosphere when the equip-ment hatch is removed, as well as a control barrier to minimize the spread of contamination.
Spread of contamination will also be minimized by a temporary equipment hatch cover.
5.2.4 The radiation dose rate at the outside surface of the CRSB Ualls will be less than or equal to 0.5 mr/hr.
Temporary shielding will be 2
used as necessary to provide supplemental shielding in order to freet this design basis.
- 5. 3 CODES, STANDARDS, AND REGULATORY REQUIREMENTS The following establish the basic criteria for the CRSB.
The design of the CRSB shall conform to all applicable portions of the latest issue (unless otherwise indicated) of the applicable specifications, codes, and standards, including case rulings, interpretations, and addenda where applicable..
5.3.1 Federal Regulations 5.3.1.1 The CRS8 will be designed to assure that the requirements of 10 CFR Part 20 and 10 CFR Part 50 are met for all activities.
5.3.2 United States Nuclear Regulatory Commission (USNRC) 5.3.2.1 Regulatory Guide 1.69, Concrete Radiation Shields for Nuclear Power Flants, Rev. O, Dec. 1973 5.3.2.2 Regulatory Guide 1.140, Design, Testing, and Maintenance Criteria for Noreal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants, Rev. 1, Oct. 1979 i
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13587-2-G01-101 4
5.J.2.3 Regulatory Guide 8.8, Information Relevant to Ensuring the Occupation Radiation Exposures at Nuclear Power Stations will be as low as is reasonably achievable,.Rev. 3 June 1978 5.3 2.4 Branch Technical Position APCSB 9.5-1.; " Guidelines for Fire.
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Protection for Nuclear Power Plants," Rev. 1 5.3.3 Air Movement and Control Association, AMCA I
5.3.4 American National Standards Institute, ANSI
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i 5.3.5 Air Conditioning and Refrigeration Institute, ARI 5.3.6 American Society of Heating, Refrigeration, and Air-Conditioning i
Engineers, ASHRAE 5.3.7 American Society of Mechanical Engineers, ASME 5.3.8 American Society for Testing and Materials, ASTM 5.3.9 American Water Works Association, AWA 5.3.10 American Welding Society, AWS 5.3.11 Department of Energy, DOE (formerly ERDA) i
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5.3.12 Hydraulic Institute Standards, HI l
5.3.13 Illuminating Engineering Society, IES
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5.3.14 Institute of Electrical and Electronics Engineers, IEEE 5.3.15 Insulated Cable Engineers Association, ICEA 5.3.16 Man'ufacturer's Standardization Society of the Valves and 'ittings Industry, MSS 5.3.17 National Electrical Manufacturers Association, HEMA 5.3.18 National Fire Protection Association, Fire Codes, NFPA 5.3.19 Occupational Safety and Health Act, OSHA 5.3.20 Steel Structure's Painting Council, SSPC 5.3.21 Underwriters' Laboratories, UL 5.3.22 Sheet Metal and Air Conditioning Contractors' National Associa-y tion, SMACNA Y
Page 9 Rev. 1
13587-2-G01-101 5.3.23 TMI Unit 2 Interim Recovery Technical Specifications 1
5.3.24 State and Local Building Codes
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]1 5.3.24.1. Pennsylvanial State Building Code for Fire and Panic Regula-:
tiorjs by Department of Labor and Industry-l
..l.1 5.3:24.2 The Building Officials and Code Administrators (B0CA) Basic Codes 5.3.25 The latest issue of such specifications codes, standards, in-
.l 1 ciuding case rulings, interpretations, is defined as the issue (in-ciuding latest published addenda) in force at the date the purchase order is placed or design drawings are issued for construction.
5.4 CIVIL / STRUCTURAL / ARCHITECTURAL REQUIREMENTS 5.4.1 Structure Descrbtion The containment recovery service building ( 258) will be a single-story structure arranged to fit the contours of the existing buildings.
The CRSB will consist of the following specific structural systems:
5 4.1.1 The superstructure will consist of structural steel framing sipported by steel columns.
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5.4.1.2 The roof structure will be metal decking.
The insulated steel deck assembly will have a FM Class 1 fire classification and Class 1-60 1
or above wind uplift classification.
- 5. 4.1. 3 The lower portion of the exterior walls will be concrete.
The upper portion of the wall will be covered with metal siding supported by steel girts.
The insulation on the metal siding shall be glass fiber 1
batts or blankets with a flame spread of 25 or less.
5.4.1.4 Structural steel bracing will be provided.
5.4.1.5 The foundation structure will consist of reinforced concrete caissons with caps.
The caissons will be drilled to bedrock.
The ground floor will be reinforced concrete slab supported by caissons so as not to load underground piping.
i 5.4.1.6 Structural steel framing will be provided to support an over-head crane and monorail systems.
5.4.1.7 The following additional structural provisions will be required for the CACE:
a.
Perimeter walls will consist of reinforced concrete for the full height,of the CACE.
b.
The roof structure will be reinforced concrete slab with metal decking.
i Page 10 Rev. 1
13587-2-G01-101 5.4.2 Design Basis The design of the CRSB will be based on the following:
5.4.2.1.The CRSB is not a seismic Category I structure.-
It will be -
.s located adjacent to safety-related systems, structures, and equipme.nt; and,shall be designed for sei'smic loads determined in accordance with the BOCA Basic Building Code.
In addition, the structure shall be checked to assure that it will not collapse or. experience excessive deformation when subjected to the safe shutdown earthquake (SSE) so that it will not affect other seismic Category I structures or systems.
5.4.2.2 The exterior walls shall be of sufficient thickness and height to ensure compliance with the requirements of Section 5.2.4 of this 2
criteria.
5.4.3 Design Loads The following loads will be used in the design of the CRSB:
5.4.3.1 The ground floor shall be designed for 500 psf uniform live load, which is sufficient for heavy warehouse / machine shop use.
5.4.3.2 The ground floor slab directly outside the equipment hatch and CACE shall be designed for the following equipment removal loads in addition to the normal ground floor live load.
A twenty-five percent increase as an cilowance for impact has been included in the loads listed below.
To pr ovide for steam generator removal the slab shall be a.
designed for a uniform load of 2400 psf distributed on an area 25'-0" by 25'-0".
b.
To provide for other miscellaneous equipment removal, such as the reactor core support assembly, the slab shall be designed for a load of 150 tons distributed according to both of the following:
1)
A uniform floor load of 3000 psf on an area 8'-0" by l
12'-6".
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21 Four 75 Kip concentrated loads, each acting on 1-foot-square areas with center-to-center spacings of 7'-0" in the lateral direction and 11'-6" in the longitudinal direction.
A one-third incriate in allowable stresses shall be permitted for steam generator removal loads.
5.4.3.3 The roof shall be designed for a ground snow load of 30 psf using appropriate distribution coefficients to account for roof geometry and drifting.
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13587-2-G01-101 5.4.3.4 The largest possible material handling system compatible with the structural design shall be as follows:
overhead bridge crane 10 tons monorail trolley (each) 7.5 tons 5.4.3.5 The CACE shall be designed for an internal vacuum cressuri of j
0.5'psig.
I 5.4.4 Additional Requirements Structural provisions shall be made for the following items:
5.4.4.1 The requirements for the removal of the existing equipment hatch and airlock including its movement and ease of replacement shall be satisfied.
L.4.4.2 The ground floor slab shall be sloped to drains connected to the radwaste drainage system.
The slab shall be designed to accommodate embedded drains.
5.4.4.3 The truck bay located in the northwest corner of the CRSB.shall be depressed 4 feet below the ground floor elevation to accommodate the loading and unloading of trucks.
5.4.4.4 All personnel doors will be hollow metal and steel frame and special doors will be provided as required.
5.4.4.5 A portion of the CRSB, including the CACE, will be supported by existing Unit 2 structures.
The structural adequacy of the existing structures shall be evaluated for the new loads imposed by the CRSB and f
CACE to assure conformance with the Unit 2 FSAR.
5.4.5 Painting and Coating 5.4.5.1 Concrete walls, floors, ceilings (if used), and masonry walls exposed to radioactive and chemical contaminants will receive decon-taminable surfacer and finish coatings.
f 5.4.5.2 All doors and frames in the CRSB will receive manufacturer's 2
standard primer and field applied epoxy topcoat.
5.4.5.3 All structural and miscellaneous steel up to 10 feet above floor level will receive shop-applied inorganic zinc primer and field-2 applied epoxy finish coating except where fireproofing material is to i
be applied.
The coatings will have a Class I surface burning characteris-l tic (0 to 25 when tested to ASTM E 84).
5.4.5.4 All ferritic steel, uninsulated piping, hangers, and supports in the CRSB up to 10 feet above floor level will receive shop-applied epoxy primer and field-applied epoxy finish coating.
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Page 12 Rev. 2
13587-2-G01-101 5.4.5.5 All ferritic steel valves and valve operators to be installed in the CRSB up to 10 feet above floor level will receive a shop-applied, two coat, epoxy coating.
Field touchup as required.
5.4.5.6.All major mechanical equipment and supports to be insta11ad in,
the.CRSB up to 10 feet above floor 1cvel will receive shop-applie' two coat epoxy coating.. Manufacturer's standard finish for small items shall be coated with water base epoxy in the field.
- 5. 4. 5. 7 The overhead crane in the CRSB and miscellaneous equipment associated with the crane will receive the manufacturer's standard finish.
5.4.5.8 Exterior surface of insulated metal siding in the CRSB shall be finished on exposed faces with PVF2 "KYNAR 500" or an approved equal shop-applied, baked-on finish.
Interface surface of insulated metal siding will be finished with manufacturer's standard shop-applied baked-on finish.
5.4.6 Temporary Equipment Hatch Cover The temporary equipment hatch cover will be designed as follows:
5.4.6.1 The cover will be provided with swinging doors as large as possible to facilitate movement of personnel and equipment.
- 5. 4. 6. 2 The cover will withstand a 1 psi pressure differential in either direction, with the doors closed.
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- 5. 4. 6. 3 Weather seals will be provided on the door edges to minimize the chance of contamination spreading from the Reactor Building when the 1
doors are closed.
5.5 LAYOUT REQUIREMENTS -
5.5.1 Containment Air Control Envelope 5.5.1.1 In order to maintain a contamination control barrier after the equipment hatch is remosed, it will be necessary to provide an air control envelope.
This feature will allow personnel and equipment to enter and exit from the containment while maintaining a barrier between the containment and outside environment.
The containment air control envelope may be used prior to completing construction of the remainder of the CRSB.
- 5. 5.1. 2 This feature will be a barrier consist'ng of concrete walls, the temporary equipment hatch and separate CACE doors.
The area will be I
large enough to allow for equipment maneuvering /laydown.
- 5. 5.1. 3 The design of the air control envelope will include provisions for the equipment hatch to be rensoved and replaced without interrupting the control functions of the envelope.
Provision shall also be made to move the mistile shield and reestablish the CACE boundary.
Page 13 i
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13587-2-G01-101 5.5.1.4 The layout of the air control envelope orca and its door will permit movement of large pieces of equipment from the reactor building, through the envelope area, and into the south end of the service area.
The outer door on the west side of the envelope will provide access _ for heavy equipment and is sized to permit passage of the equipment hatch.
5.5.1.5 A portion of the env' elope area may be used as a. hot tool crib j
until radiation levels are low enough to put the crib inside the reactor' building.
5 5.5.2 Containment Service Area 5.5.2.1 The containment service area will provide access'directly from ^
the air control envelope.
It will also provide for personnel and equip -
ment traffic to other facilities, such as the personnel access facility.
Provisions will be incorporated in the design to minimize the spread of contamination and to control the air flow.
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5.5.2.2 The south portion of the ceatainment service area will be used as a staging area for work planning and mobilization of equipment and materials for containment entry.
Personnel will enter this area frota either the personnel access facility or th? containment air control envelope.
The south portion will also be used as a truck access for laundry pickup and delivery service for the PAF.
5.5.2.3 The central and northern portions of the containment service aret will be used for decontamination of equipment and temporary' staging of contaminated materials while they are being packaged and prepared for transfer to the onsite radwaste facilities or for shipment.
Partitions or splash curtains for sprays or showers employed during decontamination of equipment will be provided in the decontamination ares.
5.5.2.4 The northwest corner of the containment service area will provide truck access to the building.
The truck bay will be located along the west wall of the building.
The truck bay will be recessed 4 feet to permit loading trailers by forklif t truck.
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5.5.2.5 Materials handling in the containment service area will be accomplished using a bridge crane, monorails, and forklifts.
Suitable aisle space and ramps will be provided to allow equipment to be moved through the equipment hatch and control envelope to the truck bay or to the north end of the service building.
Some means (e.g., rail system or crawler) will be provided to carry heavy equipment to a point beneath a roof hatch near the outside door.
Here a truck-mounted boom crane me.j be used to place heavy equipment on a lowboy trailer.
5.5.2.6 A large portion of the service area will be used for decon-
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tamination and packaging of equipment which is removed from the reactor building.
Additional design features may be reouired to support the decontamination operations.
These features will be incorporated into the design of the service building as their needs are identified.
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13587-2-G01-101 0
5.6 SYSTEMS DESIGN 5 5'.1 Several systems will be provided in the CRSB.
These systems will provide the additional services needed for the building to serve its intended functions.
The general purp3se and philosophy for al' the-building service systems is a,s follows:
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- 5. 6.1.1 Provide services required to support proposed decontamination operations 5.6.1.2 Adapt existing plant systems, equipment, and facilities for decontamination and service use when this action would present an obvious economic and schedule advantage 5.6.1.3 Design systems to be compatible with acek in a radioactive environment and mini.1.;ze the spread of airborne radioactivity 5.6.1.4 Incorporate provisions, as required, in the new piping systems to protect against freezing.
5.6.2 Material Handling. System 5.6.2.1 The system shall provide for the movement of material which has had preliminary decontamination, sorting, and packaging inside the reactor building.
5.6.2.2 Steel or plywood boxes, approximately 4' x 7'x 4' high, will be used for the removal of material, by a track-mounted transfer cart, from the reactor building into the CACE.
Material too large for the boxes will be handled as individual pieces.
5.6.2.3 A monorail / bridge crane system will provide for off-the-floor nnveient of material.
Suspended hoists are used to minimize the potential for spread of contamination.
5.6.2.4 The monorail / bridge crane system will have provision for transfer lof a loaded hoist from the bridge girder to a monorail and vice t.rsa.
- 5. 6. 2. 5 Two 20-ton-monorail hoists in the CACE will be used for equipment hatch removal.
- 5. 6. 3 Denineralized Water _ System l
5.6.3.1 The system shall provide demineralized water to the decontamina-tion area as ' makeup water source for decontamination equipment and to the CACE and decontanination area for use in " hands-on" decontamination procedures.
5.6.3.2 The system shall pros'de demineralized water outlets in the
' interim storage area, containtnent staging area, and adjacent to the truck bay for floor cTeenup and flushing, and flushing of decontamina-tior, equipment.
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13587-2-G01-101 s
5.6.3.3 "There a.e no safety design bases.
,5.6.4 Fire Protection System _
5.6.4.1 Primary fire prctection will be provided by automatic wet pipe cprinklers, and the backup fire protection will be provided by hose stations and portable fira extinguishe w.
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5.6.4.2 Thefirewallintegrityofthe~reactorbuildingshallbesafe-...'_._h
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' guarded.when there.is fuel in the reactor building.
5.6.4.3 'The impact of fire protection systems on liquid radwaste collec-L tion systems shall be minimized.
5.6.4.4 Thnre are no safety design bases.
5.6.5 Floor Drains and Miscellaneous Liquids Radwaste Disposal System Connections 5.6.5.1 A system of embedded stainless steel floor drains will be s
provided..The floor areas in the CRSB will be sloped to the floor drains.
5.6.5.2 The drainage system will be sized so that standing water will
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not accumulate on the floor due to decontamination operations.
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' ~ 5.6.5.3 The embedded drains will be routed to four sumps equipped with duplex sump pumps.
In order to minimize airborne radioactive contamina-tion from-sumps, these four sumps will be vented to the building ventila-tion system. A fifth sump in the truck bay will contain a simplex sump pump, and since.It will not normally become cpntaminated, needs no P
special verifying provisions.
5.6.5.4 Drains from equipment in the decontamination area will be routsd to the drainage sump in the decontamination area.
5.6.5.5 Contaminated or potentially contaminated sump pump discharges will be routed to the UniL 2 auxiliary building sumo for liquid radwaste proce? sing and disposal.
Contaminated liquids not compatible with the radwaste disposal systems will not be allowed to reach the floor drain l2
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system:
Incompatible wastes will be locally collected.
l 5.6.5,C Uncontaminiteditruck bay sump pump discharges will be routed to
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'tN-5 term drain ~ system.
5.6.'5,'7lTherearenosafetydesignbases.
t 5 6.6 Service Air Sv,$ tem 5.6.6.1 The system shal.1 provide service air to the CACE, decontamina-J
~ tion areas, a'nd the containment staging area.
The service air system will-be used to provide breathing air in the CACE.
The air supply will termir, ate at hose connectfons, and may be used for air-operated devices which are used in the d,econtamination operations.
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13587-2-G01-101 5.6.6.2 The system shall provide service air at a pressure and flow rate which is adequate for the intended service.
t 5.6.6.3 There are no safety design bases.
5.6.7 HVAC System 5.6.7.1 The system shall maintain a negative atmospheric pressure inside the building and control free airflow between functional areas of F
the building from clean to higher ccotamination areas.
Supplemental filters will be used, also. -=
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5.6.7.2 The system shall supply fi?tered fresh air ventilation, at the rate of 5 air cbs.1ges per hour minimum at the operating floor. level, to maintain the required ambient conditions for personnel and equipment.
5.6.7.3 The system sha limit by filtration environmental releases of airborne radioactive particulates in the building exhaust below release limits established by 10 CFR 20 and Appendix I of 10 CFR 50, 5.6.7.4 The system shall provide emergency capabilities for smoke control in case of fire to support fire brigado operations.
5.6.7.5 The system shall maintain the concentration of airborne contamina-tion in the building below maximum permissible concentration (MPC) per 10 CFR 20, Appendix B, Table I, Column I.
- 5. 6. /. 6 The supply air shall be filtered by prefilters and medium efficiency filters.
The building exhaust shall be filtered by high efficiency particulate air (HE/A) filters to limit the release of con-taminated particulates to the anvironment.
5.6.7.7 The CRSB ventilation system will interface with the containment building ventilation system on an operational basis.
The containment building will be placed under a higher negative pressure than the CACE
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so that free air flow will be directed from the CACE toward the contain-ment building.
There is no physical connection between the two ventila-tion systems.
5.6.7.8 There are no safety design bases.
5.6.8 Roof Drains 5.6.8.1 Roof drains will be provided around portions of the roof of the 2
CRSB.
The roof will be slogtd to allow liquids to collect and drain from the roof into the storm drainage system.
5.6.8.2 The roof drains will be sized in accordance with the applicable codes and standards.
5.6.8.3 There are no safety design bases.
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13587-2-G01-101 5.7 CONTROL SYSTEMS REQUIREMENTS 5.7.1 Radiation Monitoring 5.7.1.1 Area radiatinn monitors shall be provided for the protection of personnel.
5.7.1.2 Process radiation monitors shall be provided to monitor the CRSB H and V exhaust.
5.7.1.3 There are no safety design bases.
5.7.2 Communications-5.7.2.1 Public address system components shall be provided in the CRSB service area and CACE.
5.7.2.2 Provisions shall be provided in the CACE to enable radio communi-cations with the command center and personnel inside containment involved in the decontamination effort.
5.8 ELECTRICAL REQUIREMENTS 5.8.1 Power Systems 5.8.1.1 The CRSB will be a permanent structure and, therefore, normal building service loads will be added to the electrical distribution system for the life of the plant.
5.8.1.2 Due to the magnitude of the permanent CRSB loads, 4160 volt service from the turbine building switchgear'will be used to energize new 4160-480/277 volt, 3 0 unit substations located in the personnel access facility mechanical equipment room.
5.8.1.3 Unit substations will energize large electrical loads and motor control centers directly.
The 480/277 volt lighting and distribution panels will be energized via 480 to 480/277 volt transformers fed from either unit substations or motor c3ntrol centers.
The 120/208 volt lighting and distribution panels will be fed from motor control centers or distribution panelboards via stepdown transformers.
Branch circuits will be supplied through individual circuit breakers within the panels.
5.8.1.4 One motor control center will be provided to energize those CRSB loads which will exist only for the recovery period but not after plant restart.
This motor control center will be temporarily energized by an existing unit substation located in the service building which will not be supplying its normal plant loads during the recovery period.
5.8.1.5 The 125 volt DC. power will be taken from existing plant DC panelboards to provide power for the unit substation control circuits.
1 5.8.1.6 Voltage scnsitive loads within the CRSB which require a regulated power source will be supplied from line voltage regulators.
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13507-2-G01-101 5.8.2 Normal Lighting System 5.8.2.1 This system shall provide adequate illumination levels and convenience power for operating and service conditions.
In addition, it serves as a distribution system of 120/208 Vac power to serve miscel-laneous small load requirements.
This system consists of a complete distribution network' of cable?, raceways, transformers, lighting panels, lighting fixtures, receptacles, and switches.
5.8.2.2 Lighting levels shall be 30fc general and if required supplemen-tary lighting will be pc.ided for more difficult visual tasks in selected areas.
5.8.3 Emergency Lighting System This system shall provide emergency lighting for egress routes in all areas and shall consist of individual, self-contained, sealed-beam, 5-hour rated battery units connected to the normal lighting AC source to maintain battery charge and which automatically transfer to their internal batteries upon loss of AC.
Illuroination levels shall be as required by the Pennsylvania Department of Labor and Industry Fire and Panic Regulations.
5.8.4 Exterior Lighting System Exterior lighting shall be limited to fixtures mounted on the perimeter building structure for entrance areas and where required for security illumination of areas adjacent to the structure.
Exterior lighting levels shall be in accordance with existing site surveillance require-ments.
- 5. 8. 5 Raceway A complete system of raceways shall be provided to furnish protection and support for all wire and cable systems.
5.8.6 Cable Power, control and instrumentation cable shall meet IEEE 383 flame resistance tests.
Ampacity rating and gr oup derating factors of cables
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shal! be in accordance with ICEA P-46-426 for cables in conduit, ducts, and trays with maintained spacing.
ICEA P-54-440 shall be used for cables in random filled trays.
Single phase branch circuit wiring for receptacle and lighting runs shall be copper with insulation rated for 90 C, 12 AWG minimum gauge.
Insulation shall be 600 volt, type THW moisture and heat resistant thermoplastic.
Lighting fixture wire shall be Class B stranded, tinned copper with insulation rated for 200 C, 14 AWG minimum gauge.
Insulation shall be 600 volt, type SF-2 silicone rubbcr.
Polyvinylchlori h (PVC) insulation shall not be used in any cable construc-1 tion.
All wiring shall carry Underwriters' Laboratories approval.
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5.8.7 Grounding All new structures, electrical equipment, and metal components likely to become energized under abnormal conditions shall be grounded by direct or indirect connection to the existing site grounding system.
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6.0 REFERENCES
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The fcilowing were used in the preparation of these design criteria.
Other references may be added as the criteria evolve.
6.1 Planning Study for Containment Entry and Decontamination, July 2, 1979.
(Phase I Study).~.
6.2. Phase I Supplement, Planning Study for Containment Entry and Decontami-nation (September 20, 1979 Draft).
6.3 CRSB Materials Handling Description (Transmittal GPU/TMI-0216, dated February 15, 1980).
6.4 CRSB Personnel Access Description (Transmittal GPU/THI-0216, dated February 15, 1980).
6.5 General Project Design Criteria 13587-2-G01-100 (Transmittal GPU/TMI-0407, dated May 16, 1980).
7.0 GENERAL DESIGN CRITERIA EXCEPTIONS This facility design criteria is to be used in conjunction with the General Design Criteria (GDC) 13587-2-G01-100.
Any exceptions between this facility criteria and the GDC are noted below for each section of the GDC.
7.1 GENERAL SECTION There are no exceptions between this facility criteria and the General section of the GDC.
7.2 ARCHITECTURAL SECTION 2
There are no exceptions between this facility criteria and the Architectural section of the GDC.
7.3 CIVIL / STRUCTURAL SECTION There are no exceptions between this facility criteria and the Civil /
i Structural section of the GDC.
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7.4 CONTROL SYSTEMS SECTION I
There are no exceptions between this facility criteria and the Control Systems section of the GDC.
Page 20 Rev. 2
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13587-2-G01-101 i
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7.5 ELECTRICAL SECTION There are no exceptions between this facility criteria and the Electrical section of the GDC.
7.6 PLAOTDESIGN/MECHANICALS.ECTION There are no exceptions between this facility criteria and the Plant Design / Mechanical section of the GDC.
7.7 NUCLEAR SECTION., _
There are no exceptions between this facility criteria and the Nuclear i
section of the GDC.
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