ML20137F268
| ML20137F268 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/31/1985 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20137F256 | List: |
| References | |
| PROC-850731, NUDOCS 8508260182 | |
| Download: ML20137F268 (38) | |
Text
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PROCESS CONTROL PROGRAM HOPE C' REEK GENERATING STATION Revision 0
-July 1985 8508260182 850821
~
{DR ADOCK 05000354-PDR 1
. ~.-,,,_....
o TABLE OF CONTENTS SECTION TITLE PAGE(S) 1.0 Purpose......................................
1 2.0 System Description..........................
2 3.0 Waste Sources...............................
4 4.0 Process Contro1.............................
8 5.0 Sampling....................................
12 6.0 Waste Classification........................
12 7.0 Temporary Radwaste Processing (Contracted Ve n d o r ).....................................
13 8.0 Administrative Controls.....................
14 8.1 Quality Assurance......................
15 8.2 Training...............................
16 8.3 Do c ume n t a t io n Co n t ro l..................
18 9.0 Re v i s i o n s To Th e PC P........................
19 ATTACHMENTS i
1.
APPENDICES Appendix A
- System Operating Procedure
- Alarm Response Procedures
- Station Administrative Procedures
- Chemistry Procedures
- Radiation - Protection Procedures Appendix B
- Process Control Nomographs Appendix C
- Attachments 19, 20, and 21 from RP-RW.ZZ-004(Q) i Rev. O
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+
TABLE OF CONTENTS (cont.)
2.
FIGURES Figure 1, Solid Ra,dwaste System Block Diagram Figure 2, ~Radwaste Supply and Exhaust Ventilation Block Diagram Figure.3, Waste Processing, Sequence of Events Figure 4, -Operational Responsibility Chart Figure 5, VRS Process Data Sheet 11 Re v.
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1.0 PURPOSE The' purpose of the Hope Creek Generating Station (HCGS)
Process Control Program (PCP) is to describe the envelope within which processing and packaging of Low-Level radioactive waste is accomplished and as such provide assurance of complete solidification of various radioactive "we t wa s t'e s " in accordance with the applicable portions of NRC regulations and guidance which includes the following documents:
10CFR61 " Licensing Requirements for Land Disposal of
-Radioactive Waste" 10CFR20 " Standards for Protection Against Radiation" 10CFR71 " Packaging of Radioactive Material f or Transport and Transportation of Radioactive Material under Certain Conditions" 49CFR, " Transportation" NUREG-0800; Standard Review Plan Section 11.2 Liquid Waste Management System NUREG-0800; Standard Review Plan Section 11.4 Solid Waste Management System Branch Technical Position ( ETSB) 11-3 " Design Guidance for Solid Radioactive Waste Management SystemsInstalled in Light Water Cooled Nuclear Power Reactor Plants" Branch Technical Position. Papers pertaining to Waste Classification and Waste Form as transmitted to Commission Licensees in letter from Leo B.
Higgonbotham, Chief Low-Level Waste Licensing Branch dated May 11, 1983.
.Werner & Pfleiderer Volume Reduction System Technical Manual; 10855-M137A-463.
Werner & Pfleiderer Volume Reduction System Topical Report WPC-VRS-001 Revision 1, dated May 1978 (p roprietary).
O, Design Guidance for Radioactive Waste Management System, Structure, and
. Components Installed in Light-Water-Cocled Nuclear Power Plants.
Page 1 of 19 Rev. 0
" Standard Radiological Effluent Technical Specifications for Boiling Water Reactors.
South Carolina Department of Health and Environmental Control, Radioactive Material License No. 097, as amended.
NRC Special Nuclear Material License No. 12-13536-02, as amended, for Barnwell, SC.
State of_ Washington Radioactive Materials License
- WN-IOl9-2, as amended, for Richland, Washington.
NRC Special Nuclear Material License No. 16-19204-01, as amended, for Richland, Washington.
ANSI /ANS-55.1/1979, American National Standard for Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants.
State of New Jersey Regulations Applicable to Hope Creek Generating Station.
Toward this purpose, the Hope Creek PCP ensures that the solidified waste form maintains structural integrity in the form of a free standing monolith and has no more than 0.5% of the waste volume as f ree liquid.
This criteria shall be met for all Class A waste as defined in the BTP on Waste Classification and Waste Form.
This PCP will also ensure that solidification will be performed to maintain any potential radiation exposure to plant personnel "as low as reasonably achievable" (ALARA) in accordance with Hope Creek ALARA program procedures.
2.0 SYSTEM DESCRIPTION The Solid Waste Management System (SWMS) collects, reduces the volume of, solidifies, and packages wet and dry types of radioactive waste in preparation for shipment offsite to a licensed burial site.
The SWMS is designed to operate on a batch process basis.
A block diagram of the Hope Creek SWMS is presented as Figure 1.
The SWMS accepts dry solid trash, evaporator bottoms from the concentrated waste tanks, and powdered and bead resin and filter media slurries from the waste sludge phase separator, cleanup phase separator, and the spent resin tank.
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The resin and filter media slurries and concentrates are processed for preliminary volume reduction by removing the free water.
Final volume reduction is accomplished in each of two (2) extruder-evaporators.
The initial volume reduction process varies for each waste type, e.g., a centrifuge for resin slurries, and a crystallizer for evaporator concentrates.
These radioactive waste. products are further reduced in volume and mixed with asphalt in the extruder-evaporators.
Extruder-evaporator "A"
receives dry cake discharge f rom the centrifuge or slurry feed from the centrifuge feed tank or concentrates from the crystallizer bottoms l
tank.
Extruder-evaporator "B" receives slurry feed from the centrifuge feed tank, and concentrates from the crystallizer bottoms tank.
The extruder-evaporators mix the waste streams with asphalt ~ at approximately 1 gpm at 325*F (supply temperature).
At this temperature, all remaining water is evaporated.
The extruder-evaporators through their kneeding and mixing action also compact the waste and asphalt, producing a denser product.
The waste and asphalt mixture ~ is deposited into a 55 gallon drum.
The solid radwaste monorail hoist places empty drums on the turntables, which position the drums for filling under the extruder-evaporator discharge ports.
The same monorail hoist removes filled drums from the turntables.
The filled drums are placed on a-conveyor and guided to a capping-swipe station.
At this location, the drums are capped, swiped, and labeled.
Radiation readings are also taken.
The drums are then conveyed to the truck bay where they are placed in the temporary storage area located in the north part of the auxiliary building by the storage area bridge crane.
This facility provides for over 30 days of storage space, prior to shipment offsite.
The radwaste area (Auxiliary Building) ventilation systems (Figure 2) are arranged as follows:
Outside air supply to the areas designated as solid radwaste consisting of two one-half capacity trains with low efficiency and high efficiency filters.
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outside air supply to the balance of the radwaste areas in the Auxiliary Building, consisting of two one-half capacity trains with low ef ficiency and high efficiency filters.
ventilation of all tanks in the radwaste system.
This consists of two trains of low efficiency prefilters, HEPA filters, charcoal absorbers, fire protection nozzles, and high ef ficiency af ter-filters.
ventilation of the extruder-evaporator rooms consisting of one train of pre-filter, charcoal and HEPA filters for each.
ventilation of the radwaste trash compactor through a HEPA filter.
The solid radwaste area exhaust, compactor exhaust and exhaust from the extruder-evaporators are directed to the filter trains dedicated to this area.
This train consists of two one-half capacity low ef ficiency and HEPA filters af ter which is the north plant vent.
The tank exhaust is directed to the exhaust filter trains for the balance of radwaste.
These consist of three one-third capacity units with low efficiency and HEPA-filters.
This flow is directed to the south plant vent.
3.0 WASTES SOURCES 3.1 Equipment Drains Filter and Demineralizer This subsystem processes high purity waste from piping and equipment containing high quality water in the Reactor Recirculation System, Condensate System, Feedwater System, low conductivity rinse water from regenerations, etc.
The waste is processed through a filter, coated with a powdered resin product and a deep-bed demineralizer.
After a batch of processed water is collected in a sample tank, a sample is taken and analyzed.
If it meets water quality requirements, the water is transferred to the condensate storage tank.
If the batch does not~ meet water quality or radiological concentration specifications, it is reprocessed.
j Page 4 of 19 Rev. O l
3.2 Floor Drains Filter and Demineralizer This subsystem processes waste the same.as the m
equipment drain subsystem, except that the waste to be processed is of lower purity.
This waste is from floor drains, drains from the fuel pool cooling system and the RHR system. flush.
After a batch of processed water is collected in a sample tank, a sample is taken and analyzed.
If it meets water quality requirements,.the water is.
transferred.to the condensate storage tank.
If the batch does not meet water quality or radiological concentration specifications, it is reprocessed.
3.3 Decontamination Solution Evaporator The Decontamination Solution Evaporator receives laboratory waste, decontamination solutions and sample drain waste which is collected in the chemical waste tank.
These wastes are neutralized and if required, buffered with sodium phosphate,.
then processed by the Decontamination Solution Evaporator.
The Decontamination Solution Evaporator is designed to concentrate to a 10% by weight solid concentration.
The bottoms are then discharged to the decontamination solution concentrates waste tank.
The bottoms are later discharged to the regenerative waste concentrates tanks for processing thru a crystallizer evaporator.
3.4 Regenerant Waste Evaporator The regenerant waste evaporator receives regeneration solutions from the condensate demineralizer and radwaste deminralizer resin regenerations as well as inputs from the high conductivity sumps in the Turbine and Auxiliary Buildings.
These wastes are neutralized and then processed by the regenerant waste evaporator.
The regenerative waste evaporator is designed to concentrate wastes to a 25% by weight solid concentration of sodium sulfate.
The bottoms are then discharged to the regenerative waste concentrates tank, where it is processed thru a crystallizer evaporator.
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3.5 De tergent Waste The. Detergent Waste System receives-waste from laundry drains, personnel decontamination and the chemistry laboratory.
These' wastes which are normally low in r'adioactivity, are processed by
'filtrstion and then discharged to the circulating water blowdown line for dilution.
If unsuitable for discharge (10CFR2 0 limits), the waste is processed through the decontamination solution evaporator.
3.6 Crystallizer Evaporator
.The crystallizer evaporator processes the' sodium sulfate waste in the waste evaporator concentrates tank.
This waste is concentrated to a 50% by weight concentration and is discharged to the crystallizer bottoms tank.
This tank is one of two of the final waste streams-that are isolated, sampled and finally introduced for solidification into the asphalt extruder-evaporator.
3.7 Spent Resin Storage Tank Exhausted resin from the twelve condensate deep-bed demineralizers and the two radwaste demineralizers are stored in this tank.
Once suf ficient resin is in the tank it will be transferred to the centrifuge feed tank.
This is the second of the two final waste streams that is isolated, sampled, and finally introduced for solidification into asphalt extruder-evaporator "A".
3.8 Waste Sludge Phase Separator This separator receives exhausted powdered filter coating from the fuel pool and radwaste filters, along with crud discharged from the ultrasonic resin cleaner.
The sludge, separated from the water, is transferred to the centrifuge feed tank.
3.9 Cleanup Phase Separators These separators receive exhausted and fouled powdered resin from the Reactor Water Cleanup System.
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.a The sludge separated from the water is transferred to the centrifuge feed tank.
3.10 Centrifuge Feed Tank and Centrifuge Spent resin, fouled and exhausted powdered resin and crud from the spent resin storage tank and -
sludge separators are fed to this tank to be processed through the-centrifuge.
The feed tank recirculates the slurry to produce a homogeneous mixture.
Once in a homogeneous form a sample.is taken to determine the pH and the solids concentration of the slurry.
The concentration measurement is used to set the metering pump flow rate for feeding to the centrifuge and on to the extruder-evaporator.
The centrifuge separates the carrier water from the resin / sludge phase separator.
The remaining waste solids are discharged as a moist, solid to extruder-evaporator "A" via a vertical chute.
The centrifuge can be bypassed, if inoperable, to feed the extruder-evaporators directly.
3.11 Extruder Evaporators Extruder Evaporator A and B receive concentrates from the crystallizer bottoms tank and slurries
'from the centrifuge feed tank.
Extruder t
Evaporator A is the only one to receive resin from the centrifuge.
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The extruder-evaporators encapsulate a waste stream with asphalt at a temperature of
~
approximately 325*F (supply).
At this temperature the remaining water is evaporated resulting in a-reduction in volume.
The end product drips in a 55-gallon drum, where cooling and solidification occurs.. The drums are then capped, swiped, labeled, and stored for shipment of fsite.
3.12 Contaminated Oils Oils will be collected and stored in 55 gallon drums.
With a large enough volume on hand to economically justify, a contracted vendor will be brought in, with an approved topical report to solidify same.
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3.13 Filter Cartridges and Miscellaneous Items Filters and miscellaneous items, will be handled l
on a case by case basis, being disposed of by l
methods acceptable to the burial site.
3.14 Trash Compactor l
Compactable low level trash will be processed and compacted in a hydraulic-operated box compactor.
A 100 ft3 container made of plywood and lined with galvanized steel is used for storing and shipping.
The box compactor is equipped with an external HEPA filtration system.
4.0 PROCESS CONTROL The process variables having a direct bearing on the properties of the final product which relate only to the ability to form a free standing monolith with no free water are described.
Additional process variables such as phi.must be contro11ed to minimize corrosion within the system; however, s'.nce these variables do not affect the ability of the waste product to form a monolithic solid upon cooling, they will.not be discussed herein.
In accordance with the foregoing limitations, the following variables influence the properties and consistency of the final solid product:
- Asphalt type;
- Waste chemical species being incorporated into the asphalt matrix;
,g j
- Ratio of waste-to-asphalt; and
- Process temperature.
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4.1 Asphalt Type Hope-Creek will use an oxidized petroleum-based asphalt, conforming to ASTM-D-312-71, Type III requirements.
This grade of asphalt has a low residual volatile content, and a high molecular weight.
At room temperature, and at all normal ambient conditions, this material is a free standing monolith.
Specification of Witco Pioneer 221, or an equivalent, is the means by which process control for asphalt quality is achieved.
At Hope Creek, delivery of this asphalt will be sampled for product conformance.
Page 8 of 19 Rev. 0
4.2 Waste Chemical Species The type and relative quantity (waste-to-asphalt ratio) of waste chemicals being incorporated in the asphalt matrix has a direct influence on the properties of the final product.
Encapsula tion of inorganic salts and solids typically " stiffen" and harden the waste product; whereas organic liquids have the opposite effect.
When the
. proper ratio of waste-to-asphalt is maintained, final product properties relative to solidification, are independent of the waste type.
A limit of 1 percent oil and organic contaminants in the waste feed stream is imposed for process control.
Most oils found in a power plant waste stream are low viscosity fluids, which are liquid at room temperature.
Based on calculations for a typical waste stream with 20 percent solids by weight and 1 percent oil, the total concentration of oil in the end product would be approximately 2.5 percent.
This would lower the end product softening point by approximately 5' F; a negligible change.
4.3 Waste-to-Asphalt Ratio in the Product The ratio of waste-to-asphalt contained in the end product has the most bearing on the viscosity and physical consistency of that product during processing.
The recommended ratios of waste-to-asphalt for each waste feed is as follows:
Ratio of Waste-to-Asphalt in Feed the End Product 1.
Evaporator Concentrates 4 5/55 to 5 0/50 2.
Spent Rosins (Bead or 30/7 0 to 50/5 0 Powered)
Page 9 of 19 Re v.
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Optimum value depends on type and quantity of
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contaminants present.
For resins, the presence of fibrous additives may also influence product i
flow characteristics, and, therefore, waste loadings.
Should the ratio of waste-to-asphalt l
be increased above the range specified in the l
foregoing table,the end product viscosity will increase and may exhibit a grainy texture.
This could lead to " pyramiding" of the product in the container, thereby decreasing the container filling efficiency.
In all cases, the product will cool to form a freestanding monolith.
If l.
lower than specified waste loadings are realized, l
the end product properties will approach that of
. pure asphalt.
Proper waste-to-asphalt ratios in the product are i
automatically maintained by a coordinated proportioning feed system to the extruder-evaporator.
Operator involvement is limited to
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setting the extruder-evaporator and the initial proportion of waste-to-asphalt flow.
To do this, he must determine, by sampling, the solids contents of the waste feed.
With the sample analysis, he need only consult the nomographs shown in Appendix B for proper feed control settings.
4.4 Process Temperature A proper temperature profile along the length of the extruder-evaporator is required to provide adequate evaporative (process) capacity, and to assure that f ree water is not discharged from the machine.
Typical process temperature profiles for all llope Creek waste types are as follows:
WASTE TYPE PROCESS TEMPERATURE (F)
BARREL:
1 2
3 4
5 6/7 8
EVAPORATOR 85 190 250 250 250 320 280 CONCENTRATES l
SPENT RESINS 85 190 230 230 230 240 240 (Centrifuge)
SPENT RESINS 85 190 240 240 240 270 270 l
(Slurry) i f
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Low temperature alarms are provided to alert the operator to a low temperature of f-spec. condition which could potentially lead to the discharge of f ree water.
These alarms are based on a percent ( 5 ) deviation from set point, typically 1/2-l% or 1-4* F.
The percent deviation permitted can be adjusted in the field up to 10% (16-35 'F) of set point.
While deviations of 10% will not result in free water in the product, this condition is the maximum deviation that should be tolerated since failure to hold this range indicates a problem with the equipment.
If an off-spec. condition persists for two (2) minutes, the extruder-evaporator and feed pumps are automatically tripped to prevent free water f rom being discharged into the container.
Free water cannot be discharged in the interim, since the residual heat of the extruder-evaporator itself is suf ficient to ef fect evaporation.
The foregoing controls / interlocks are provided to prevent the discharge of free water to the container.
The temperature profiles specified above have been proven by experiment to yield residual total moisture content in the product of 1% by weight for bead resins.
This margin provides assurance that f ree water cannot be discharge under normal circumstances.
Under upset or off-spec. conditions, discharge of f ree water is prevented by the low temperatures process interlocks.
4.5 Minimum Functional Components In support of maintaining the four major process parametors; Process Temperature Asphalt Type Mixture Ratio Oil Content and to assure a stable waste form consistent with the guidance of the PCP, operators will insure the following list of equipment is available, as a minimum, prior to beginning processing.
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Closed circuit television system at the asphalt loading stations.
All temperature profile monitoring instrumentation.
The' asphalt and slurry metering equipment (pumps, valves, etc.).
Crystallizer bottoms and centrifuge feed tank recirculation and agitation equipment.
All sampling capabilities.
Batches will not be processed through the af fected extruder-evaporator, when any of the above equipment is tagged out of service.
5.0 SAMPLING i
From all the various sources of wastes, two final isolable tanks receive input.
The crystallizer bottoms l
tank and the centrifuge feed tank are then recirculated and agitated to insure a homogeneous mixture.
Once isolated nothing further is'added.
A sample of each batch is obtained in accordance with operating procedures OP-SO-HC-004 and OP-SO-HC-005.
The samples are analyzed and the sample data form (Figure
- 5) is completed.
Chemistry personnel will determine the chemical and radionuclide content of each sample in accordance with the procedures as listed in Appendix A.
The system operators, utilizing the data form (Figure 5) and the nomograph (Appendix B) select appropriate feed rates for introduction into the extruder-evaporators.
The system will be operated until the entire batch is processed.
Should circumstances result in interruption of a batch, the source tank w 61 be isolated and remain so until processing can re3ume.
6.0 WASTE CLASSIFICATION The eight minimum waste characteristic requirements identified in 10CPR61.56(a) shall be satisfied.
The Page 12 of 19 Rev. 0
i Hope Creek PCP assures that wastes determined acceptable l
for near surface disposal are properly classified for the purpose of segregation at the disp'osal site.
Waste classification is performed consistent with the guidance provided in the Branch Technical position pertaining to Waste Classification and is based upon the concentration of. certain radionuclides in the waste form as given in 10CFR. parts 61.55 and 61.56.
The methods utilized by Hope Creek, and the frequency for determining the radionuclide concentration of the final waste form is conducted in accordance with Hope Creek Procedure RP-RW-ZZ-004 " Shipment of Radioactive Materials".
Classification will be performed in accordance with this procedure.
7.0 TEMPORARY RADWASTE PROCESSING (CONTRACTED VENDOR)
In the event Hope Creek requires the services of a contracted vendor to temporarily process and package radwaste on site, PSE&G will obtain the services of a
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vendor with an NRC approved topical report.
An engineering review of the subject topical report will be performed to assure vendor operational requirements are compatible with Hope Creek system operations responsibility.
In all cases, safety will not be compromised and assurance that ALARA concerns'are addressed will be the primary goal for any temporary radwaste system interface.
The services and plant interfaces available may consist of, but are not be limited to the following:
1.
Water flushing f acilities 2.
Drain-return " clean" liquids 3.
Supply of spent resin 4.
Concentrates; supply of sludge 5.
Vent-of f-gas thru HEPA filters 6.
Air 90-115 psi 7.
Electric - 120 amps /460 VAC 3 phase 8.
Shielding (as required) 9.
Health Physics support 10.
Fire protection coverage 11.
Communications All vendor procedures will be reviewed by engineering and approved by SORC in accordance with SA-AP. ZZ-001(0).
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Technical Specification 3.11.1.4 limits will be
. observed.
8.0 ADMINISTRATIVE CONTROLS This section of the ' Hope Creek PCP describes administrative controls as they relate to quality assurance, training, documentation, and record keeping programs implemented by the PCP.
Administrative controls are utilized to ensure that all e
processing is performed in accordance with the guidelines set forth in the Hope Creek.PCP.
Public i
Service Electric and Gas is ulimately responsible for performing this function through the Hope Creek
. operational Quality Assurance program.
The
. responsibility of the Operational Quality Assurance program include the following:
measures to, assure control of activities affecting the function of structures, systems and components planned monitoring and audit program assure that specified requirements of the operational OA program-are met coordinated and centralized quality assurance, direction, control' and. documentation as required by the applicable portions of 10CFR50 Appendix B are complied with management controls are established for the safe operation of Hope Creek 8.1 Ouality Assurance The administrative controls designed to prevent solidified waste forms from being released for shipment prior to test sample verification of acceptability require OA to verify that a sample l
record sheet has been properly executed for each waste batch prior to processing.
Figure 3 illustrates the sequence of. events in flow chart form, for the Hope Creek solidification t
process.
In addition, this figure presents the applicable Hope Creek procedures employed for each l
step of the solidification process.
5 Page 14 of 19 Rev. O u
-Figure 4~is the Operational Responsibility Chart for all radwastes systems.
Implementation of the operational QA program is assured by ongoing review, monitoring and audit functions which fall under the direction of the General. Manager - Nuclear Quality Assurance, who reports to.the Vice President - Nuclear.
- The authority vested in the General Manager -
Nuclear QA is as follows:
independence to interpret quality requirements identify quality problems and trends provide recommendation or solutions to Quality problems The General manager - Nuclear QA has the authority to stop work when significant conditions adverse to quality require action.
The Nuclear QA program assures compliance with the waste classification and characterization requirements of 10CFR61.55 and 10CFR 61.56.
With respect to waste classification, this is achieved by Nuclear - QA verifying proper adherence.to waste classification procedures and review and verification of waste classification data sheets.
A Nuclear - QA representative shall observe waste classification procedure adherence for a minimum single batch waste processing operation.
With respect to waste characterization, the requirements of 10CFR 61.56.are intended to provide stability of the waste.
Stability is intended'to ensure that waste does not structurally degrade and affect overall stability of the waste disposal site.
The auditing function of the Nuclear - QA program assures stability requirements are achieved in accordance with 10C FR.
In the event a vendor is' contracted to perform temporary radwaste services, the Nuclear - QA program requires management review of the vendor topical report.
The purpose of this review is to Page 15 of 19 Rev. 0
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assure that vendor operation and requirements are compatible with responsibilities and operation of Hope Creek.
The contracted vendor shall comply with all OA described in this document.
8.2 Training A training program is being implemented for personnel having responsibilities related to waste processing operations.
The results of this training program shall ensure that waste processing is performed within the specific requirements of the PCP.
To accomplish this objective and to provide the necessary control of the SWMS, the following general training programs will be implemented.
8.2.1 Initial Plant Staff Training Program -
These programs are designed to provide competent, trained personnel in all disciplines and at all levels of plant organization.
The programs are designed to allow personnel to be placed at various points, according to their training, experience and intended position.
- Subsequent to class room instruction, each operator must qualify on each piece of Radwaste Equipment to obtain a Qualification Card.
- On-the-job training will ensure that each SWMS operator maintains an acceptable level of skill and familiarity associated with SWMS, controls and operational procedures.
- The training procedures are detailed in the Nuclear Department Training Manual.
This training includes familiarity with the following SWMS components:
Liquid - Drains, Filters, Collection Tanks and Sub-Systems Solid - Extruder-Evaporators, Crystallizer and Sub-Systems i
Page 16 of 19 Rev. 0 l
8.2.2 Continuing Training Program - A continuing training program for SWMS personnel, is developed and provides continuous training and upgrading of plant personnel.
Continuing training in specific areas is provided to the extent necessary for personnel to safely and efficiently carry out their assigned responsibilities in accordance with established policies and 1
procedures.
The continuing training i
program shall run on an annual basis with all program requirements completed during the two year training cycle.
The continuing training program will consist of two areas; lectures, which may consist of vendor presentations, technical training sessions, on-the-job work experience or
. programmed instruction, and continuing training examinations.
(1) The continuing training program will cover fundamental review and operational proficiency.
Fundamental review training will be in system modifications, revision to procedures and incidents encountered during operations.
Operational proficiency training will involve lectures that will focus on essential plant pperational guidelines and changes or experiences in the nuclear industry.
(2) Continuing training examinations will be given to determine the SWMS operator's knowledge of the material covered, areas where additional training may be required and operational proficiency.
These examinations should consist of written examination and/or oral examination.
Personnel are evaluated on an annual basis where individual needs for retraining will be identified.
Personnel demonstrating a significant deficiency in a given area of knowledge and proficiency may be placed into a remedial training program.
This Page 17 of 19 Rev. 0 1
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program is specifically structured to upgrade knowledge and skills identified as deficiencies.
Successful completion of the accelerated training program is evaluated by a written and/or oral examination.
The combination of formal training, on-the-job experience, and SORC approved procedures which include cautions and corrective actions should a malfunction or an out of boundary condition occur,will give assurance that control parameters within this PCP are maintained.
8.2.3 Replacement trainina - These programs are designed to provide qualified personnel for i
the station organization.
The General i
Manager - Hope Creek operations, or the designated representative, may waive portions of the training program for I
individuals based on their previous i
experience and/or qualifications.
l l
The SWMS training records shall be maintained for audit and inspection purposes.
These records are considered nonpermanent records and shall meet the applicable requirements of ANSI /ASME l
N45.2.9-1979 " Requirements for Collection Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants".
8.3 Documentation Control and Record Retention Nuclear - OA program audits of waste classifi-cation records are performed on a periodic basis.
Management evaluation of such audits shall be performed and as such satisfy the requirements of 10CPR2 0.311(d ) ( 3 ).
Audits of the SWMS operating procedures shall be performed by the Nuclear - OA organization at a minimum of once per 24 months.
Changes to operating procedures shall be reviewed on an as required basis by Nuclear - OA in parallel with l
the Hope Creek Station Operation Review Committee Page 18 of 19 Rev. O
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(SORC) in order to ensure continued compliance
(
with the requirements and established process
[
-parameters of the PCP.
These changes may be promulgated as a result of proposed plant operations and betterment initiatives,' system design changes, maintenance requirements, ALARA concerns or temporary vendor interface.
Hope Creek shall utilize the PSE&G Radioactive y
Shipment Record Form as presented in Attachment 19 l
and 20 to Procedure RP-RW.ZZ-004 for manifest I
preparation (Appendix C).
The information l
contained in the form includes the required information of 10CFR 20.311.
The tracking System for manifest preparation I
shall be in accordance with Procedures I.
RP-RW.ZZ-004 " Shipment of Radioactive Materials" and RP-AP. ZZ-Oll " Records Management and Retention Program".
The retention period for these records is the life of the company.
l 9.0 REVISIONS TO THE PCP Public Service Electric & Gas Company proposed revisions l
to the Hope Creek PCP will receive SORC approval.
l These revisions may be initiated as a result of proposed plant operations and betterment initiatives, system design changes, maintenance reg'uirements, ALARA concerns or temporary vendor interface.
The PCP, if revised, shall be submitted to the NRC with the semi annual Radioactive Effluent Release Repor t.
t Page 19 of 19 Rev. O
a Figure 1 HOPE CREEK SOLID RANASTE BIOCK DIAGRAM Spent Resin k
To Vendor A
frm: CPS Rosin Radweste Resin il s
'/ 1/ 'l m ete Sludge Phase Separator v
1/
Centrifuge Extruder - Evaporator Sarpling A
fres Various high Centrifuge
^ ^
solido drains Feed Tank waste precosts Clean-up Asphalt Cooling Backwash Tank Storage Tank hter MCU Weste Proccat Electric Boiler (Steam)
Decontamination Vendor Solution Evaporator f
from Detergent Este M Wmate
'/ 'l Decon Weste Regenerate k 'I 'I Weste v
Evaporators.
>Sarpling Extruder 4 vaporator g
frm: CPS and Radweste B
Domineralizer Regenerations l
Cgstallizer Bottoms Tank
'/
Capper / Seamer Swipe Station Conveyor PC's Trash Onsite Offsite Corpactor Storage Shipment /
Radwaste Burial Trash (DAW)
FIGURE 2 I
RADWASTE SUPPLY AND EXHAUST VENTILATION Outside Radwaste Building Distribution Header South Air for Ventilation
' Plant Radwaste Supply Vent Filter Train Radwaste Building Exhaust Header Radwaste Exhaust Filter Train Radwaste Tank t
Vents l
Radwaste Tank l
Vents - Filter Train 1
Extruder-Evap.
l Vent Hoods Extruder-Evaporators North
^
Ventilation Filters Plant Vent v
Solid Radwa'ste Outside Solid Radwaste t
Area l
l Air
-Air Solid Radwaste
^
Solid Radwaste Exhaust Filter Supply Filter Train Train l
Trash Compactor i
Filter l
l
FIGURE 3 SEQUENCE OF EVENTS FOR SOLID RADWASTE PROCESSING 1
Start l
OP-S O. HC- 0 01( R)
O P-SO. H C-00 4 ( R)
C H-RC. Z Z- 007 ( 0 )
OP-S O. HC- 004 ( R)
C H-CA. Z Z- 021( 0 )
Isolate and Mix, OP-S O. HC- 005 ( R)
CH-CA. Z Z- 02 0( 0)
Sample Waste Form, Methods for determining CH-CA.22-018(O)
Chemical Addition feed sys. flow rates C H-CA. Z Z- 002 ( O )
(WPC-VRS)
OP-SO. HC- 002( R)
O P-S O. HC- 003 ( R )
Process OP-S O. HC- 004 ( R )
Waste Form O P-S O. HC- 00 5 ( R )
O P-S O. HC- 0 06 ( R )
OP-S O. HC- 0 07 ( R)
Classify, Label and OP-SO. HC- 006 ( R)
Store Waste Form RP-R W. Z Z- 0 04 ( 0 )
S A-A P. 2 2- 02 9 ( O )
Prepare RP-RW.ZZ-004(O)
Manifest R P-ST. Z Z- 0 01( 0 )
Notifications RP-RW. 2 2- 004 ( O )
for Shipping Ship RP-RW.22-004(O)
Waste Form RP-ST. 2 2- 001( O )
RP-RW.22-004(O) aste RP-AP.ZZ-lll(O) no Fo rms yes Close S A-AP.22-006( 0)
Investigate Received at File on -
RP-RW. 22- 004 ( O )
S A-AP. 2 2-03 5 ( 0)
Disposal Waste RP-AP. Z Z- 011( Q )
t ite Form RP-RW.22-004(0)
Close RP-RW. 2-004(0)
RP-AP.ZZ-Oll(0) f File on Waste i
Form
FIGURE 4 l
OPERATIONS RESPONSIBILITY CHART Operations Manager V
V V
Responsible for:
Senior Shif t Senior Overall implementation of Supervisor Operating liquid and solid radwaste Support management program Supervisor Co-ordinate efforts betwwen supporting departments (back shifts)
Supervises Shif t Supp. Supv.
2 (Radwaste Supv.)
V l
Responsible fort Shift Assuring compliance of daily Support operations to the overall Supervisor liquid and solid radwaste management program Supervising Equipment operators radwaste Co-ordinating day to day efforts between departments V
Responsible fort Equipment all duties described in Job Operator Spec including Hadwaste operation of the liquid radwaste system operation of the solid radwaste system drum handling anphalt system operation aux. bollor operation
FIGURE 5
.1 FORM VRS. PROCESSING SHEET DATE pH DRUM NO.
TANK TANK
% OIL TANK STOP BATCH NR.
% SOLIDS START LEVEL MIN. ASPHALT FEED gpm SP GRAVITY LEVEL STOP MAX. WASTE FEED gpm TEMP.
START TIME /
' TIME /DATE DATE INIT.
INIT.
NOTE:
Take readings once per hour, when necessary.
WASTE TEMPERATURE PROFILE FLOW RATE ASPH FLOW _
DRUM TIME (GPM)
(GPM)
LEVEL 1
2 3
4 5
6 7
l APPENDIX A I
SYSTEM OPERATING PROCEDURES I
(
OP-SO.HA-001 Gaseous Radwaste Operation OP-SO.HA-002 Gaseous Radwaste Ambient Charcoal OP-SO.HB-001 Equipment Drain collection and Processing OP-SO.HB-002 Floor Drain Collection and Processing OP-SO.HB-003 Chemical Waste Collection and Processing OP-SO.HB-004 Regenerate Waste Collection and Processing OP-SO.HB-005. Liquid Radioactive Waste Release and Recycle OP-SO.HB-006 Liquid Radwaste Filter Precoat Operation OP-SO.HC-001 Solid Radwaste Collection OP-SO.HC-002 Asphalt Storage and Transfer OP-SO.HC-003 Solid Radwaste Auxiliary Boiler OP-SO.HC-004 Solid Radwaste Crystallizer l
l OP-SO.HC-005 Solid Radwaste Extruder-Evaporator OP-SO.HC-006 Solid Radwaste Drumming and Capping OP-SO.HC-007 Compactible Trash l
ALARM RESPONSE PROCEDURES I
OP-AR.HC-001 Slurry - Solid Radwaste Annunciator Panel OP-AR.HC-002 Concentrates - Solid ~Radwaste Annunciator Panel OP-AR.HC-003 Asphatl - Solid Radwaste Annunciator Panel
STATION ADMINISTRATIVE PROCEDURES IC-AP. Z Z- 010( 0 ) Preventive Maint. - Calibration Frequency Determination S A-AP. Z Z-02 4 ( O) Radiation Protection Program - Training S A-AP. Z Z-02 9 ( Q ) Administrative Control-Radiation Materials S A-A P. Z Z- 00 6 ( O ) Incident Report and Reportable Occurrences S A-AP. Z Z-03 5 ( 0) Reporting Requirements R P-AP. Z Z-l l l ( O ) Abnormal Radiation Occurrence S A-A P. Z Z- 001 ( 0 ) Preparation and Approval of Station Procedures RP-AP.ZZ-Oll(0) Records Management and Retention Program CHEMISTRY PROCEDURES C H-RC. Z Z- 021( O ) Total Dissolved Solids By Gravimetric Analysis C H-CA. Z Z- 02 0( Q ) Oil and Grease By Gravimetric Analysis CH-CA.ZZ-018(O) Suspended Solids By Gravimetric Analysis C H-CA. Z Z- 002 ( Q ) PH Analysis C H-RC. Z Z- 002( 0 ) Gross Beta By Liquid Scintillation C H-RC. Z Z- 0 01( Q ) Gross Beta By Proportional Count Rate C H-RC. Z Z- 006 ( Q ) Gross Beta By Proportional Count Rate C H-RC. Z Z- 007 ( Q ) Gamma Spectroscopy RADIATION PROTECTION PROCEDURES RP-ST. Z Z- 001( O ) Shipment Surveillance R P-RW. Z Z- 004 ( 0 ) Radwaste Shipment
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r APPENDIX C RP-RW.ZZ-004(Q)
ATTACHMENT 19 BARNWELL SHIPMENT RECORD (TYPICAL) 1 i
BARNWELL WASTE MANAGEMENT FACILITY f.e Operated by: CHEM NUCLEAR SYSTEMS. INC.
CDDRISS P. O. Box 726. Barnwell. South Carolina 29812 CARRIE R _ _ ADDRE SS.,
(803)259 1781 RADIOACTIVE SHIPMENT manif EST FORM IE t E MtONE SHINE DAIE
. (11Y STATE SHIPMI NT IVPE SHIPMf NI StfRF ACE E APOStJRt niR. hR (ONTACT PHONE SHIPMI NI NO TINE R SiRIAL NO
.. consigned te
- - - _ _.ta uSE THIS NUMBER ON. _. _... _. _. _ VOL UME At tOCAllON NO PAGE _
DRIVER SIGNATURE DATE CHE M NilCLI AR SYSTE MS INC P O (W 12h OSOORN ROAD All CONilNUATION PAGE S OF
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_ _ESCHNWi t L. S _C 29812 c.. totae ow PROF 1 H SHIPPING NAME & HA/ARD CL ASS SHIPMENT TOT AtS eD est ame n o.
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DAHHOC on( ) Yes ( ) No THis vtHWif l$ CONSIGNED EXCLUSIVE USE LOADING AND UNIOADING MUST BE H S' ' Ce'1'hcatam es heretsy made to ttw Siuth Camhna Departruent ot Heanh and E nvirarwnental Controllhat shis sh.geweit AC(.s.MPL istilD BY CONSIGNOR OR CONSIGNE E OR Hl3 DESIGNATED AGE Ni ul kw level radin4<1 eve waste has tieen enssated in antwdarve with the requwemesits of South Caeolina Hmtusailive M..tenal (w ense No 091 as anierwied..uwt the Nix lear Regulatory Conmuwam's t u ense No I? I 6 h 01 as ne IMPORTANT ' T his is to n e.t.f, th.il the atmve e arned materials are properly classahetj dest retted, p.3(baged, rnar bed
'Inierwled. mM1 the ettet teve Bar nwell Sate Desgmsal Cutena wsthen 48 tumus gwww to sh.gwnent. a.wt hnther r e,tir,( atitwi es aeWj tabeled and are In pr8 sl4-* r af u hielv) IOr IranstMW1atuNiaCcord*ng tO the appMable regulatumsol the Department of nbelle that the mstww tum reve eled tw stems of non connaliarx e with all agt n able laws. sules askt segul etereis l
Transpewtatu m D.ete f4y Smnahoe
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Form No CNS 201 Treen h No t os dhias fiate (9 83)
Waste C1.3% Cemh-sii 10 %5feth iklee.4WW I4 vt W '.410 Perwiensta-l ( agetssure 0
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ATTACHMENT 19 (cont'd)
BARNWELL WASTE MANAGEMENT FACILITY GENERATOR NAME Operated by: CHEM NUCLEAR SYSTEMS, INC.
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c"o =re Pas -> 20747 pAos,Or U j ECOLOE,Y, INC.
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UN2910 u,e,at,.e O Radsosctive Material, speccat form. n o s - Radioacteve Material UN2974 emcrseso si s, Radenactive Materlat, instruments and articles - Radioactive Material UN2911 f8p j7 ',',,'g 'g'O','*' '"d,E","?,* ***fj',';"o* ""'*,'y; 2,'*,,*ge',,",7,"*,*gj *fy,*,,*,,* ",,"l1",,,O,,,g,*,,' ' *j" ' ',y *,"l,",* "
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