ML20054C123
| ML20054C123 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/14/1982 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20054C120 | List: |
| References | |
| PROC-820414, NUDOCS 8204200075 | |
| Download: ML20054C123 (20) | |
Text
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i THREE MILE ISLAND NUCLEAR STATION UNIT 2 RECOVERY FROGRAM I
SOLID WASTE STAGING FACILITY l
SYSTEM DESCRIPTION l
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TABLE OF CONTENTS FOR SOLID WASTE STAGING FACILITY Article Page 1.0 Introduction 1
2.0 Design Description 1
2.1 Facility Function 1
2.2 References 2
2.3 Design Bases 3
2.4 Summary System Description 4
Table 1 SWSF Instrumentation 11 Table 2 Instrument Setpoint Index 12 Table 3 Operating Procedures 13 Figure 1 Plot Plan - Location of SWSF Figure 2 Typical Layout - SWSF Figure 3 SWSF Sump Flow Diagram Shielding Analysis - Types of Waste i
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SYSTEM DESCRIPTION 0f, SOLIO WASTE STAGING FACILITY (SWSF)
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 offsite burial grounds. The SWSF has been designed and will be operated in such a manner as to provide assurance that:
A.
The health and safety of the public will be protected.
Occupational exposures will be as low as reasonably achievable B.
(ALARA)
C.
There will be no significant adverse impact on the environment.
2.0 DESIGN DESCRIPTION 2.1 Facility Function The SWS' is used for the collection and temporary staging of the 2.1.1 nuclear waste (solidified and/or Dewatered Resins) generated in processing the fluids during the Recovery cleanup operations at TMI Unit 2.
The SWSF is located as shown on Figure 1, South and East of Unit 2 2.1.2 Natural Draft Cooling Towers within the area protected by the Flood Control Dikes.
Space was allocated to accomodate six (6) modular structures; two (2) modules "A" and "B" are completed, the remaining space is available for additional modules as, or if, required.
2.1.3 Figure 2 shows the typical layout of the SWSF system.
2.1.3.1 Each Module is designed with Sixty (60) Cells forming the com-partments for storing the radioactive waste generated during processing.
2.1.3.2 Each Cell is designed to stage the radioactive waste contained in either One (1) 6 ft, diameter by 6 ft. high liner, or Two (2) 4 ft.
diameter by 4 ft. high liners, or Eighteen (18) 55 gallon, type DOT.17H Drums.
2.1.3.3 Each Hodule is designed to accomodate any comoination of the radio-active waste containers as follows:
Total Wt of One Filled Container Quantity Container 1b.
6 ft, dia. x 6 ft. H Liners 60 (1 per cell) 14,000 or 55 gallon drums 1080 (18 per cell) 800 or 4 f t. dia. x 4 ft. H Liners 120 (2 per cell) 4,500 2.1.3.4 A floor drainage system is incorporated into the module design which discharges into a common sump located between Modules "A" and "B".
The total capacity of the sump is approximately 2750 gallons.
2.2 References 2.2.1 U.S. NRC Regulatory Guide 1.143, July 1978, Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants.
2.2.2 Design Criteria / Input Record. GAI W.O. #04-4283-070 2.2.3 Gilbert Associates, Inc. (GAI) Drawings:
2.2.3.1 Excavation and Grading Plan. E-774-151.
2.2.3.2 Plant Layout E-012-006 E-014-004.
2.2.3.3 St ructural.
E-430-006 E-430-007 E-430-008 E-430-Oll 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-Oll 2.3 Design Basis 2.3.1 The SWSF is designed to comply with the requirements of RG.l.143, July, 1978.
The facility is designed to provide a controlled, but reacy 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 n2gJirements of 40 CFR Part 190 at the site boundary and beyond.
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 wittdn 0.5 mr/hr and 2.5 mr/hr, respectively.
The analysis was based on the types of waste defined in Attachment 1.
No credit was taken for the structure being partially underground.
-. -. 2.3.4 Quality Assurance regJirements for the design, operation and construction of the SWSF are consistent with those specified in Regulatory Guide 1.143.
2.4 Summary System Description 2.4.1 The concrete structure and individual cell covers provide the necessary shielding from the radioactive waste housed in the SWSF Module Storage Cells.
The cell covers with gaskets protect the waste containers from the I
elements and the ingress of precipitation. Slots and weep holes in the upper module structure are provided to direct rainwater to l
external drainage ditetes.
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 discFarges into a common sump.
2.4.2 The sump compartment, a radwaste seismic concrete structure houses the pump, valves, piping, instrumentation, etc., necessary to perform the functions and control the disposal of any effluent which may collect in the sump.
The compartment is divided into two levels, the upper operator level is shielded by a thick concrete floor from the sump. Operator access is a manhole in the concrete slab roof.
2.4.3 The flow diagram Figure 3 shows the pumping system for the sump ef fluent. All operations are local / manual.
The local alarms and sump level indication are housed in a weatherproof instrumentation panel mounted outside adjacent to the sump compartment on Module "A" st ructure.
. The sump pump, Solenoid Valve #WS-5 and three-way valve #WS-1 (extension spindle) are located in the lower sump while the elec-trical distribution and control panels, valves, etc. are mounted in the operators compartment.
Sump level is measured by a variable capacitance sensor (SWS-LE-01) which transmits the signal to local and remote (Unit-2 Control Room) alams.
Sump influent flow alarms are provided.
The sensing elements (conductivity) f40s. SWS-CE-07 and SWS-CE-08 are mounted in the Module "A" and "B" drain system manifolds.
2.4.3.1 Sump Pumping Operations (See Figure 3)
The SWSF sump is controlled and disposal of the effluent will be in accordance with Unit-2 Chemistry Procedure #1899 and Operating Procedure #2104.4.100.
The sump compartment is posted as a radiological controlled area and surveillance is required prior to entry, to ensure 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 are 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 Valve WS-1 to route pump discharge returned to sump.
C.
Start pump.
2.4.3.1.2 Sampling Mode (during Recirculation tbde)
NOTE: Radiologically monitor the collection of the sample with the appropriate instrument.
A.
Solenoid Valve WS-5 open.
l B.
Valve WS-7 open.
C.
Collect sample.
D.
WS-5 and WS-7 closed.
E.
Stop pump.
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 truck (or portable vehicle) con-nection for effluent disposal.
C.
Operate three-way Valve WS-1 to route pump discharge to truck discharge manifold.
D.
Valve WS-4 (WS-3) open.
E.
Start pump.
F.
Stop pump, disconnect tank truck (or portable vehicle) connection, and allow contents of tuse to drain back into sump.
G.
Valve WS-4 (or WS-3) closed.
H.
Operate three-way Valve WS-1 for recirculation mode and secure.
2.4.4 Major Ecpipment 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 pH approx. 7.
Materials Cast iron / bronze fittings Impeller Open type Discharge Conn.
Flanged above mtg. plate l
Service Intermittent 5 yr. life l
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Solenoid Valve (1):
Instrumentation: See Table 1.
2.4.5 Facility General Arrangement: See typical layout Figure 2.
The general arrangement, laycut and details of the SWSF systems are stown in the drawings referenced in Section 2.2.3.
2.4.6 Instrumentation and Controls 2.4.6.1 The SWSF has three (3) instrument loops as follows:
A.
A level instrument string provides the alarm and level in-dication both local and remote.
In addition, this loop provides a sump pump permissive at greater than 10 percent le vel.
B.
The other two (2) instrument strings are conductivity flow loops providing local alarms.
One loop senses input from the drain discharge manifolds from Module "A" and the other from Module "B".
I 2.4.6.2 Instrument Setpoint Index.
See Table 2.
2.4.7 System Interfaces There are six interfaces associated with this facility:
1.
Processing Systems:
Access road to and from waste and fluid processing facilities for transportation of materials and ecpipment.
2.
Material Handling System: Facility will accept radioactive waste containers from the processing systems and are compatible with the transportation and lifting ecpipment, i.e., transfer shield and site cranage (Manitowoc 4000 W mobile crane or equivalent).
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Cooling Water Pump (CWP) House: 480 V, 3 f 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.
1 C.
25 KVA, 240-120V power center to energize lighting,
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l convenience receptacles, instrumentation, and control
- devices, f
NOTE:
No permanent heat tracing required for sump com-i j
partments.
4.
Control Room: Sump level alann.
q 5.
Chemistry Laboratories: Sump effluent samples for chemistry and radiological analysis prior to disposition.
NOTE: The sump pump discharge is not directly connected to i
any plant systems, a local hose station is provided, j
2.4.8 Operations-Radwaste Handling The major operations performed at the SWSF is handling the radio-l active waste containers while loading / unloading the individual cells in accordance with the types of containers specified in Section 2.1.3. Unit 2 Procedures (See Table 3), specifically written for l
j these operations are strictly adhered to, using the Manitowoc Mobile i
Crane or equivalent and the transfer shield (Bell).
Each cell has an individual concrete cover 8'3" square x 3'0" deep.
l (Dwg. #B-430-015) weighing approximately Fourteen (14) tons, this is the maximum load handled by the lifting system.
Only One (1) cover l
may be removed at any time from the cells containing radioactive waste containers within a module system.
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1 2.4.9 Maintenance All operations including Maintenance recpires a RWP.
Inner surfaces of the cells and the sump are epoxy coated to ease decontamination of the facility.
2.4.10 Acceptance Testing.
2.4.10.1 Mechanical. Dwgs. #E-311-873 and E-311-874 A.
Module "A" and "B" Drain Piping Systems.
(1) Leak Test in accordance with ANSI B31.1.1977.
Criteria: Static Head.
(Fill System, water level top of drain tubs)
Holding Period.
10 minutes minimum.
1 Acceptance.
No visual leakage.
i (ii) Flow wrification, allow Icak test water to drain to sump.
Criteria:
No visible fluid in system.
O.
Sump Pump "A" and associated piping.
Initial Service Leak Test in accordance with ANSI B31.1, 1977.
Criteria: Pump disciurge pressure Acceptance.
No visual leakage, all welded joints leaktight.
2.4.10.2 Electrical / Instrumentation: Dwgs. #8-256-031, B-248-011 and SS-261-011 A.
Continuity and Megger tests were performed for all circuits.
_._ B.
Instrument and Control were tested and calibrated in ac-cordance with MTX 507.
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C.
Sump Pump "A", tested in accordance with Electrical Preoperational Test Procedure WG-E01.
D.
Solenoid Valve #WS-VOS, tested in accordance with Electrical Preoperational Test Procedure WG-E02.
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Table 1 Solid Waste Stagino Facility Instrumentation Instrument Designator Model or Type Locations Functions SWS-LE-01 Orexelbrook 700-2-57 Mod A Sump Sump Level Sensor SWS-LT-11 Drexelbrook 408-6230 Mod A Opr. Floor Sump Level Transmitter SWS-LI-01 370-1104-401 Mod A Opr. Floor Sump Level Indication SWS-LI-OlA International Instr.1151 Mod A Top Panel Sump Level Indication SWS-LSL-01 SETCON 401-100x Mod A Top Panel Sump Level Switch Low (Pump Permissive)
SWS-LSH-01 SETCON 401-100x Mod A Top Panel Sump Level Switch High SWS-LAH-01 PANALARM Mod A Top Panel Sump Level Alarm High SWS-LAH-01A PANALARM CR Panel 17E-24 Sump Level Alarm High SWS-CE-07 Level Lance 14-ll5V Sump Influent Flow Conductivity Element SWS-CAH-07 PANALARM Mod A Top Panel Influent Flow Alarm SWS-CE-08 Level Lance 14-ll5V Sump Influent Flow Conductivity Element SWS-CAH-08 PANALARM Mod A Top Panel Influent Flow Alarm l
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Table 2 Instrument Setpoint Index Instrument Component Tag No.
Instrument Description Type Setpoint Descrip.
Action
};
SWS-LSL-01 Solid Waste Staging Facility Sump Level Current 10% level (5.6 ma)
Contact Closure (GAI: LB-S-4) Switch Low (Sump Pump Permissive)
Switch Increasing SWS-LSH-01 Solid Waste Staging Facility Sump Level 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-CE-08 Solid Waste Staging Facility Sump Influent Conductivity Maximum Contact Closure (GAI: CE-S-8) Flow Module 'B&C' Conductivity Element Element Sensitivity l
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Table 3 OPERATING PROCEDURES Proc. No.
Description 2104.4.53 Transfer Spent Filters 4' x 4' liner from FHS to SWSF.
2104.4.68 Stacking 4' x 4' liners at SWSF.
2104.4.73 Removal of 6' x 6' liners from Interim Staging Facility and tra.'sfer to SWSF.
2104.4.100 SWSF sump pumping operation.
2104.4.103 EPICOR II 4' x 4' liner transfer and shipping cask loading 2104.4.107 On-site transfer of Radioactive 6' x 6' resin liners from EPICOR II to SWSF/ Ship.
2104.4.108 On-site transfer of Radioactive 6' x 6' resin liners from SWSF to Transporter / Ship.
2104.4.118 On-site transfer of Radioactive 4' x 4' resin liners from EPICOR II to SWSF/ Ship.
2104.4.119 On-site transfer of Radioactive 4' x 4' resin liners from SWSF to Transporter / Ship.
2104.4.120 Transfer of Solidified Resin Liners from Unit II to SWSF.
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i Shielding Analysis - Types of Waste Types of waste considered are given below. A 3 month decay period was used in the analysis.
- 1) Natural Circulation Evaporator with Solidification Waste Form: 55 gallon drums (solidified)
Design Basis for Cell: C-D waste CVR* = 4.5, n** =.6 18 drums per storage cell C-D waste analysis is given below or 2) Forced Circulation Evaporator / Crystallizer with Solidification Waste Form: 55 gallon drum (solidified)
Design Basis for Cell: C-D waste G VR = 22, n =.6 18 drums per storage cell or 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 Two liners per cell or 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 O VR = 543 B-C waste analysis is given below
- VR -
volume reduction
- n Packaging efficiency:
ratio of volume of waste to total container volume.
A)
Quantities; C-D Waste i
83,000 gallon - Reactor Coolant Bleed Tank - A 1
83,000 gallon - Reactor Coolant Bleed Tank - B 250,000 gallon - Reactor Building Sump B)
Isotopic Analysis (1 Ci/ml) - Design Basis; C-D Waste IsotopepCi/ml Mo 99 - 180 Cs 136 - 120 Ce 144 - 100 I 131 - 8200 Ba 140 - 290 H 3-1.2 I 132 - 20 La 140 - 160 Cs 134 - 82 Sr 89 - 1400 Cs 137 - 330 Sr 90 - 120 i
C)
Isotopic Analysis (u Ci/ml) - Design Basis; B-C Waste B-C Waste i
Isotope u_Ci/ml Isotope u_Ci/ml Ba 133 2E-1 Ba 140 7.5 E - 1 Co 60 1.4 E - 4 La 140 2.4 E + 0 Cs 134 1.6 E - 1 4
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Cs 137 7E-1 I
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TMI UNIT 2 SWSF SUMP FLOW DIAGRAM Figure 3.
- - -