ML20057B378
| ML20057B378 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 09/02/1993 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20057B377 | List: |
| References | |
| 3184-007, 3184-7, NUDOCS 9309210276 | |
| Download: ML20057B378 (20) | |
Text
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SD 3184-007 REV 6 ISSUE DATE August 1993 U ITS C NITS DIVISION SYSTEM DESCRIPTION FOR Solid Haste Staging Facility COG ENG M
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MNuclear 3184-007 Page 2 Of 20 Solid Waste Staging Facility System Description Rev.
SUMMARY
OF CHANGE Approval Da te 0
Initial issue per GPU Nuclear letter 4400-82-L-0059.
4/82 1
Reissued per GPU Nuclear letter 4410-83-L- 0078.
3/83 2
Annual Update.
7/85 3
Annual Update.
7/87 4
Annual Update.
Revised Section 2.1.2, 2.1.3.2, 2.4.9, 8/89 and 2.4. 3.1.
5 Annual Update. fiinor changes to Sections 2.4.1, 2.4.7, 8/90 2.4.8, and Table 3.
6 Annual Update. Revised following Sections to clarify 8/93 information or modify to improve flexibility for anticipated interim storage period:
2.1.1, 2.1.3, 2.1. 3. 2, 2.1. 3. 3, 2. 2. 4, 2. 3. 2, 2. 4. 7, 2. 4. 8, Ta bl e 3, and Attachment 1.
R 3
e 4
.a e
i 3184-007 TABLE OF CONTENTS SECTION PAGE
1.0 INTRODUCTION
4 2.0 DESIGN DESCRIPTION 4
2.1 Facility Function 4
2.2 References 6
2.3 Design Basis 7
2.4 Summary System Description 8
Table 1 Solid Waste Staging Facility Instrumentation 14 Table 2 Instrument Setpoint Index 15 Table 3 Operating Procedures 16
- Shielding Analysis - Types of Wastes 17 Figure 1 TMI Unit 2 Plot Plan 19 Figure 2 Sump Module A & B Flow Diagram 20 Revision 6
3184-007
1.0 INTRODUCTION
The Solid Waste Staging Facility (SWSF) performs no active function. The facility is a passive system for temporary staging of nuclear radioactive waste prior to preparation for shipment and disposal to approved off-site burial gmunds. The SWSF has teen designed and is operated in such a manner as to provide assurance that:
A.
The health and safety of the public will be protected, l
B.
Occupational exposures will be as low as reasonably achievable (ALARA); and C.
There will be no significant adverse impact on the environment.
2.0 DESIGN DESCRIIYlION
-I 2.1 Facility Function 2.1.1 The SWSF is designed ar5d used for the collection and tempomry staging of the radioactive waste (e.g., solidified /dewatered msins, filters, sludges) generated during the cleanup operations at TMI-2, and operations at TMI-1.
2.1.2 The SWSF is located as shown on Figure 1, south and east of Unit 2 Natural Draft Cooling Towers within the area protected by the Flood Contml Dikes.
Space was allocated to accommodate six (6) modular stmetures. Two modules ("A" and "B") are completed and space is available for three (3) of the four (4) additional modules. At this dc:% there is no intention to construct any of the additional modules.
2.1.3 Reference 2.2.3.2 shows the typical layout of the SWSF.
2.1.3.1 Each module is designed with 60 cells forming the compartments for storing the radioactive waste generated.
2.1.3.2 Each cell is designed to stage the mdioactive waste contained in either one (1) 6 ft diameter by 6 ft. high Revision 6
3184-007 liner, or two (2) 4 ft. diameter by 4 ft. high liners, or 18 55-gallon DOT specification drums.
It is anticipated that offsite radioactive waste disposal will not be available after June 1994. After that date, waste will have to be stored at the generator's site (i.e., TMI) until offsite disposal becomes available. This interim storage period will require that all onsite radioactive waste facilities be flexible in their capability for use in storing waste. Actual waste streams and stomge containers may then vary from those specified in the facility design.
However, design dose rates and total activity levels must not be exceeded.
2.1.3.3 Each module is designed to accommodate any combination of the radioactive waste containers as follows:
Wt. of One Total Filled Container Ouantity Container (lb).
6'x6' Liners 60 (1 per cell) 7,000 - 22,000 max.
or 55 gallon dmms 1080 (18 per cell) 840 or 4'x4' Liners 120 (2 per cell) 4,500 - 5,000 max.
Due to the likely mmoval of the disposal option (discussed above), additional storage flexibility is desired. For this reason, other waste containers may be stored in the facility if they can be safely handled radiologically and industrially and are within the facility design dose rate. Examples of what may be stored in the modules are provided below: Revision 6
3184-007 Wt. of One Total Filled Container Ouantity Container Ob).
4'x4'x6' Box 60 (1 per cell) 4,500 or Steel D m m 1260 (21 per cell) 840 or Poly or Metal HIC 60 (1 per cell) 22,000 or Liner > 4'x4' or Poly or Metal HIC 120 (2 per cell) 10,000 or Liner s 4'x4' I
2.1.3.4 A floor drainage system is incorporated into the module design which discharges into a common sump located I
between Modules "A" and "B". The total capacity of the l
sump is approximately 2750 gallons.
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2.2 References 2.2.1 U.S. Nuclear Regulatory Guide 1.143, July 1978, Design Guidance for Radioactive Management Systems, Structums, and Components Installed in Light-Water-Cooled Nuclear Power Plants.
I 2.2.2 Design Criteria / Input Record. GAI W.O. #04-4283-070.
2.2.3 Gilbert Associates, Inc. (GAI) Drawings:
1 2.2.3.1 Excavation and Grading Plan.
E-774-151 2.2.3.2 Plant Layout.
E-012-006 E-014-004
! Revision 6
3184-007 2.2.3.3 Stmetural.
E-430-006 E-430-007 E-430-008 E-430-011 E-430-012 E-430-013 E-430-014 E-430-015 2.2.3.4 Building Services-Piping.
E-311-873 E-311-874 2.2.3.5 Electrical.
SS-308-417 B-256-031 E-266-011 2.2.4 GPU Nuclear memo 6615-92-0117, "Fenceline Dose Rate Limit,"
dated August 5,1992.
2.3 Design Basis 2.3.1 The SWSF is designed to comply with the requirements of Regulatory Guide 1.143, July 1978.
The facility is designed to provide a controlled but ready access for material handling operations and to ensure that the operator exposures are as low as reasonably achievable (ALARA).
2.3.2 The facility is designed to maintain the dose rates in accordance with 10 CFR Part 20 and to meet the requirements of 40 CFR Part 190 at the site boundary and beyond. Site Boundary dose rate is required to be 0.2 mrem /hr or less.
2.3.3 The shielding thickness was calculated to limit the contact dose rates at the outer surfaces of the module walls and the top of the cell covers to within 0.5 mr/hr and 2.5 mr/hr, respectively. The analysis was based on the types of waste defm' ed in Attachment 1. No credit was taken for the structure being partially underground. Revision 6
3184-007 2.3.4 Quality Assurance requirements for the design, construction, and operation of the SWSF am consistent with those specified in Regulatory Guide 1.143.
2.4 Summary System Description 2.4.1 The concrete stmeture and individual cell covers provide the necessary shielding from the radioactive waste housed in the SWSF
{
Module Storage Cells.
j The cell covers with gaskets protect the waste containers fmm the elements and the ingress of precipitation. Slots and weep holes in the upper module stmeture are provided to direct rainwater to the module sides. A drainage piping system prevents any spillage / leakage of fluids from accumulating in the cells (i.e., floor drain hub in each cell); the system manifold discharges into a common sump.
2.4.2 The sump compartment, a radwaste seismic concrete stmeture, houses the pump, valves, piping, instmmentation, etc., necessary to perform the intended functions and control the disposal of any effluent which may collect in the sump. The companment is divided into two (2) levels, with the upper operator level shielded by a thick concrete floor fmm the sump. Access to the upper companment is via a manhole in the concmte slab roof. Access to the sump is via a removable ladder at the sump plug opening and a pennanently installed ladder into the sump.
2.4.3 The flow diagram (Figure 2) shows the pumping system for the sump effluent. All operations are local / manual. The local alarms and sump level indication are housed in a weatherpmof instmmentation panel mounted outside the Module "A" stmeture adjacent to the sump companment.
The sump pump, Solenoid Valve #WS-5 and three-way valve #WS-1 (extension spindle) are located in the lower sump while the electrical distribution and control panels, valves, etc. are mounted in the operators compartment.
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3184-007 I
Sump level is measumd by a variable capacitance sensor (SWS-LE-
- 01) which transmits the signal to local and remote (Unit 2 Control Room) alarms. Sump influent flow alarms are pmvided. The sensing elements (conductivity) Nos. SWS-CE-07 and SWS-CE-08 am mounted in the Module "A" and "B" drain system manifold.
2.4.3.1 Sump Pumping Operations (See Figure 2)
The SWSF sump is controlled and disposal of the effluent is in accordance with the Unit 2 Procedures 4210-OPS-3011.01 and 4215-OPS-3232.14. The sump compartment is posted as a radiological controlled area and surveillance is requimd prior to entry to ensum operator exposure will be as low as reasonably achievable (ALARA).
On receipt of the alarm signal (approximately 50% sump level) in Unit 2 Control Room, the above procedures are put into effect and the sequence of operations is as follows:
2.4.3.1.1 Recirculation Mode (sump effluent mixing to obtain representative sample for analysis)
A.
All valves to be checked closed; B.
Operate three-way valves WS-1 to route pump discharge returned to sump; and
)
C.
Start pump.
{
l 2.4.3.1.2 Sampling Mode (during Recirculation Mode)
NOTE: Radiologically monitor the collection of the sample with the appropriate instrument.
A.
Solenoid valve WS-5 open; B.
Valve WS-7 open; C.
Collect sample; D.
WS-5 and WS-7 closed; and E.
Stop pump.
- Revision 6
3184-007 2.4.3.1.3 Discharge Mode (Only after sample analysis is completed)
A.
All valves to be checked closed; B.
Connect hose to the tank tmck (or portable vehicle) connection for effluent disposal; C.
Operate three-way valve WS-1 to route pump discharge to tmck discharge manifold; D.
Valve WS-4 (WS-3) open; E.
Start pump; F.
Stop pump, disconnect tank tmck (orportable vehicle);
l G.
Valve WS-4 (or WS-3) closed; and H.
Operate three-way valve WS-1 for recimulation mode and secun:.
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2.4.4 Major Equipment A.
Sump Pump (1): Gould Model 3171 1 x 1-1/2-6 Capacity:
50 gpm TDH:
100 ft Fluid:
Radioactive waste water / resin slurry 1
Ph approx. 7 Materials:
Cast iron / bronze fittings Impeller:
Open type Discharge Conn.:
Flanged above mig. plate Service:
Intermittent 5 year life B.
Solenoid Valve (1):
Instrumentation: See Table 1.
2.4.5 Facility General Arrangement: The general arrangement, layout, and details of the SWSF systems are shown in the drawings in Section 2.2.3. Revision 6
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i 3184-007 2.4.6 Instrumentation and Controls 2.4.6.1 The SWSF has three (3) instmment loops as follows:
A.
A level instmment string provides the alarm and level indication both local and remote. In addition, this loop provides a sump pump permissive at greater j
l than 10% level.
B.
The other two (2) instmment strings are conductivity flow loops providing local alarms. One (1) loop senses input from the drain discharge manifold from Module "A" and the other from Module "B".
2.4.6.2 Instmment Setpoint Index (See Table 2).
l 2.4.7 System Interfaces There are five (5) interfaces associated with this facility:
1.
Processing Systems: Access mad to and fmm waste and fluid processing facilities for transportation of materials and equipment.
2.
Material Handling System: Facility will accept radioactive waste containers from the processing systems or packaging that are compatible with transportation and lifting equipment (i.e.,
transfer shield, site cranage and appropriate crane).
3.
Cooling Water Pump (CHP) House: 480 V,3 4> 200 A feeder cable from Bus 2-61 shall provide power for the following:
A.
460 volts to the sump pump; B.
480 volt welding receptacle; and C.
25 KVA, 240-120V power center to energize lighting, i
convenience receptacles, instrumentation, and control devices. Revision 6 6
i
i 3184-007 NOTE:
No permanent heat tracing required for sump -
compartments.
l 4.
Control Room: Sump level alarm.
I 5.
Chemistry Laboratories: Sump effluent samples for chemistry and radiological analysis prior to distribution.
NOTE:
The sump pump discharge is not directly connected to any plant systems; a local hose station is provided.
2.4.8 Opentions-Radwaste Handling i
i The major operation performed at the SWSF is handling the f
radioactive waste containers while loading / unloading the individual cells in accordance witl) the types of containers specified in Section
+
2.1.3. Handling of these containers is performed in accordance with Unit 2 procedures. The appropriate crane (r) is utilized for handling activities along with appmpriately shielded equipment.
Each cell has an individual concrete cover 8'3" square x 3'0" deep (Dwg. #B-430-015) weighing approximately 14 tons. Normally only one (1) cell containing radioactive waste containers within a module j
system will be uncovered at any given time. If more than one (1) i cover is to be removed at any one time, additional safety procedures will be exercised.
2.4.9 Maintenance Most operations including maintenance requires a RWP.
Inner surfaces of the sump are epoxy coated to ease decontamination of the facility.
2.4.10 Acceptance Testing 2.4.10.1 Mechanical Drawings #E-311-873 and E-311-874
]
I A.
Module "A" and "A" Drain Piping Systems.
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3184-007
- i. Leak Test in accordance with ANSI B31.1,1977.
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Criteria: Static Head. (Fill system, water leve1 J
top of drain hubs) l Holding Period: No minutes minimum Acceptance: No visual leakage l
ii. Flow verification, allow leak test water to drain to sump.
Criteria: No visible fluid in system.
B.
Sump Pump "A" and associated piping Initial Service Leak Test in accordance with ANSI B31.1,1977.
Criteria: Pump discharge pressure Acceptance: No visual leakage, all welded joints leaktight 2.4.10.2 Electrical / Instrumentation: Drawings #B-356-031, B-248-011, and SS-261-011 A.
Continuity and megger tests were performed for all circuits.
B.
Instmment and control were tested and calibrated in accordance with MTX 507.
C.
Sump Pump "A" tested in accordance with Electrical Preopemtional Test Procedum WG-E01.
D.
Solenoid Valve #WS-V05, tested in accordance with Electrical Preoperational Test Procedure WG-E02. Revision 6 l
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3184-007 1
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TABLE 1
)
SOLID WASTE STAGING FACILITY INSTRUMENTATION Instmment Designator Model or Tvoe Locations Functions SWS-LE-01 Drexelbrook 700-2-57 Mod A Sump Sump Level Sensor SWS-LT-11 Drexelbrook 408-6230 Mod A Opr. Floor Sumpleve1 Transmitter SWS-LI-01 370-1104-401 Mode A Opr. Floor Sump IxvelIndication SWS-LI-01 A Intern'l Instr.1151 Mod A Top Panel Sump Level Indication SWS-LSL-01 SETCON 401-100x Mod A Top Panel SumpIzvel SwitchIew (Pump Permissive)
SWS-LSH-01 SETCON 401-100x Mode A Top Panel SumpIrvelSwitchHigh SWS-LAH-01 PANALARM Mode A Top Panel Sumplevel Alarm High SWS-LAH-01A PANALARM CR Panel 17E-24 Sumplevel AlannHigh SWS-CE-07 Level Lance 14-115V Sump Influent Flow Conductivity Element SWS-CAH-07 PANALARM Mod A Top Panel Influent Flow Alarm SWS-CE-08 Level lance 14-115V Sump Influent Flow Conductivity Element SWS-CAH-08 PANALARM Mod A Top Panel Influent Flow Alarm Revision 6
_=
3184-007 TABLE 2 INSTRUMENT SETPOINT INDEX Instrument Component Tac. No.
Instmment Descrintion Tvoe Setooint Description Action SWS-LSIr01 Solid Waste Staging Facility Sump level Current 10% level (5.6 ma)
Contact Closure (GAI: LB-S-4)
Switch Low (Sump Pump Pemiissive)
Switch Increasing SWS-LSH-01 Solid Waste Staging Facility Sump Ixvel Current 42% level (11.2 ma)
Contact Closure (GAI: LB-S-3)
Switch High Switch Increasing SWS-CE-07 Solid Waste Staging Facility Sump Influent Conductivity Maximum Contact Closure (GAI: CE-S-7)
Flow Module "A" Conductivity Element Element Sensitivity SWS-CE4)8 Solid Waste Staging Facility Sump Influent Conductivity Maximum Contact Closure (GAI: CE-S-8)
Flow Module "B & C" Conductivity Element Element Sensitivity
, Revision 6
3184-007 TABLE 3 OPERATING PROCEDURES Procedure Number Description 4215-OPS-3232.14 SWSF Sump Pump Operation 4231-OPS-4440.01 Transfer of EPICOR 4'x4' Liners 4231-OPS-4450.08 On-site Transfer of Radioactive Liners te SWSF/ Shipping Cask /
Staging Area 4231-OPS-4450.09 On-site Transfer of Radioactive Liner from SWSF 4231-OPS-4450.20 Movements of 4'x4' Liner / HIC from SWSF 4231-OPS-4450.22 Transfer of TMI-1 HIC to Solid Waste Staging Facility / Shipping Cask Revision 6
-. =,
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3184-007 j
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ATTACHMENT 1 i
l SHIELDING ANALYSIS - TYPES OF WASTES l
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Types of wastes considemd are given below. A 3-month decay period was used in the analysis.
1.
Natural Circulation Evaporator with Solidification l
Waste Form: 55 gallon drums (solidified)
Design Basis for Cell: C-D waste at VR* = 4.5, n** =.6 18 drums per storage cell C-D waste analysis is given below j
i or t
2.
Forced Circulation Evaporator / Crystallizer with Solidification I
Waste Form: 55 gallon dmm (solidified)
Design Basis for Cell: C-D waste at VR = 22, n =.6 18 dmm per storage cell l
or l
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3.
EPICOR II Charcoal Filter Waste Form: Activated Charcoal in 4 ft. diameter x 4 ft. high liner Design Basis for Cell: 2500 R/hr on contact l
Two liners per cell j
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I 4.
EPICOR II Demineralizer Resins Waste Form: Dewatered Resins in 4 ft. diameter x 4 ft. high liner Design Basis for Cell: B-C waste at VR = 543 B-C waste analysis is given below VR = volume reduction
- VR = Packaging efficiency: ratio of volume of waste to total container volume Revision 6
3184-007 A.
Quantities: C-D Waste 83,000 Gallons - Reactor Coolant Bleed Tank - A l
83,000 Gallons - Reactor Coolant Bleed Tank - B 250,000 Gallons - Reactor Building Sump l
B.
Isotopic Analysis (uCi/ml)- Design Basis: C-D Waste Isotope pCi/ml l
Mo 180 Cs-138 -
120 Ce-144 - 100 I
l I-131
- 8200 Ba-140 -
290 H-3 1.2 l
I-132 20 La-140 -
160 l
Cs-134 --
82 Sr-89
- 1400 Cs-137 -
330 Sr-90 120 C.
Isotopic Analysis (uCi/mi)- Design Basis: B-C Waste l
B-C Wasig Isotope pCi/ml Isotope pCi/mi Ba-133 2 E-1 Ba-140 7.5 E-1 l
Co-60 1.4 E-4 La-140 2.4 E+0 Cs-134 1.6 E-1 Mo-99 2.7 E-1 I-131 2.3 E+1 l
Bi-207 2.2 E-2 Co-58 1.2 E-3 l
Cs-137 7 E-1 Revision 6
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3184-007 FIGURE 1
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3184-007 1
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