ML20033F265
| ML20033F265 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/02/1990 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20033F084 | List: |
| References | |
| PROC-900302, NUDOCS 9003190141 | |
| Download: ML20033F265 (21) | |
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i PROCESS CONTROL PROGRAM 1299.
seguCYAH NUCLEAR PLANT REVISION 0 PLANT MANAGER DATg*
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l TABLE OF CONTENTS
'1. 0 INTRODUCTION 2.0 DEFINITIONS
3.0 REFERENCES
4.0 WASTE CHARACTERISTICS 4.1 Waste Streams 4.2 Waste Form 4.3 Waste Classification 4.4 Waste Containers 5.0 CAPABILITY TO MEET 10 CFR 50 APPENDIX 1 6.0 SHIPMENT MANIFESTS 6.1 Manifest Preparation 6.2 Manifest Tracking 7.0 ADMINISTRATIVE CONTROLS 7.1 Procedures and Surveillance 7.2 Quality Assurance / Quality Control 7.3 Trcining 7.4 Retention of Records 8.0 WASTE TREATHENT 8.1 Evaporator Concentrates Solidification 8.2 Solidification of Sludges, Oil, and Miscellaneous Aqueous and Chemical Wastes 8.3 Miscellaneous Golid Waste Encapsulation 8.4 Spent Rosin 8.5 Filter Elements 9.0 SEM1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTS 10.0 MAJOR CHANCES TO RADIDACTIVE WASTE TREATMENT SYSTEMS (Liquid, Caseous and Solid) 11.0 LICENSEE INITIATED CHANCES TO Tile PROCESS CONTROL PROGRAM APPENDIX A - Location and Arrangement of Equipment APPEND 1K B - Exceptions to or Deviations from Vendor Topical Reports
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1.0 INTRODUCTION
1.1 Scope This Process Control Program (PCp) applies to radioactive waste solidification and dewatering of wet solid radioactive wastes generated as a result of the operation and maintenance of Sequoyah Nuclear Plant (SQN). This PCP does not apply to the treatment of mixed radioactive and hazardous wastes.
1.2 Purpose The PCP provides the controls necessary to ensure that disposal criteria are met by SQN processing techniques, or by vendor supplied systems, if used for dewatering or solidification.
2.0 DKFINITIONS 2.1 Absorb - To take liquid in through pores, or as if through pores or interstices of a material.
2.2 Absorbent - Media or material used to absorb liquid.
2.3 Batch - An isolated quantity of waste to be processed having constant physical and chemical characteristics.
2.4 Container - The primary receptacle in Which processed wastes (dewatered, solidified, or absorbed) are packaged for disposal.
2.5 Dewatered - Wet solid wastes which have had excess water removed.
2.6 Free Liquid - Uncombined liquid not bound by the solid matrix of the solid waste mass; capable of flowing.
2.7 Ilomogeneous - Of uniform composition; the waste is uniformly distributed throughout the container.
2.8 Liquid waste - For the purposes of this PCP, any aqueous or non-aqueous radioactive liquid which requires solidification or absorption before dispoon1. This may include oils, chemicals, water or other liquido uncultablo for inplant cleanup or treatment.
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2.9 Mixed waste - Low-level radioactive wastes containing chemical constituents which ato hazardous under Environmental Protection Agency regulations in 40 CFR Part 261.
2.10 Solidification agent - Materini which, when mixed in prescribed proportions with liquid or wet solid wastes, can form a free-standing product vith no free liquid.
2.11 Solidification - Shall be the convorcion of wet radioactive wastes into a form that meets shipping and burial ground requirements.
2.12 Stability - A property of the wasto form such that it is able to neintain its structural integrity under the expected disposal conditions; stabilized wasto should maintain its gross physical proporties and identity over a 300 year period.
2.13 Wet solid wastes - Evaporator concentrates, filter aid sludge, bead ion exchange resins, and other sludges or olurries consisting of liquids with a high insoluble solid content.
3.0 REFFRENCES 3.1 Code of Federal Regulations (CFR) Title 10, Parts 20, 61, and 71 (10 CFR 20, 10 CFR 61, and 10 CFR 71) - Energy 3.2 Code of Federal Regulations (CFR) Title 49 (49 CFR) -
Transportation 3.3 Sequoyah Nucicar Plant Final Safety Analysis Report, Chapter 11.5 3.4 Sequoyah Nuclear Plant Technical Specifications 3.5 TVA Office of Nuclear Power Radioactive Material Shipment Manual (RMSM) 3.6 Nuclear Regulatory Commission (NRC) Low-Level Wasto Licensing Branch Technical Position on Radioactivo Wasto Classification, May 1983, Rev. 0 3.7 Nuclear Regulatory Commission (NRC) Technical Position on Waste Form, May 1983, Rev. 0 h.-__________.-.___m_m._.__
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3.8 Solidification Topical Report Referencos 3.8.1 4313-01354P A, Chem-Wuclear Systems, Inc., Mobile Cement solidification System l
3.8.2 Chem-Nuclear Systems, Inc., Topical Report, Waste Form certification Program Report It PMC Binder Chemistry Report 111 Pozzolanic Binder Chemistry Report 1111 Cement Binder Chemistry 3.8.3 Test Results, Waste Form PWR-80, Chem-Nuclear Systems, Inc.
3.8.4 Test Results, Waste Form In-situ P-14, Chem-Nuclear Systems, Inc.
3.9 Solidification Vendor Procedures 3.9.1 CNS1, SD-0P-003-492, Process Control Program for CNSI Cement Solidification Units at Sequoyah 3.9.2 CNS1, SD-OP-022, Operating Procedure for CNSI Portablo Cement Solidification Unit No. 24 (PSU-C-24) 3.9.3 CNS1, SD-OP-026-492, Process Control Program for Cement / Oil Solidification at TVA Sequoyah 3.9.4 CNS1, SD-OP-048, Operating Procedure for In-Situ Solidification of Suspended Objects 3.10 Dewatering Topical Report References 3.10.1 DW-11118-01-P-A, Chem-Nuclear Systems, Inc., CNSI Dewatering Control Process Containcro 3.11 Dewatering Vendor Procedures 3.11.1 CNS1, FO-OP-023, Bead Rosin / Activated Carbon Dewatering Proceduro for CNSI 14-215 or Smaller Liners 3.11.2 CNS1, FO-0P-19, Polyethyleno High Integrity Container Overpack Handling Procedure 3.11.3 CNS1, FO-AD-002, Operating Guidelines for Use of Polyethyleno liigh Integrity Containcro
l 4.1 Waste Streams Eight general waste streams have been identified at SQN.
These are primary Resin, Secondary Resin, Radwaste Resin, Sludges and Evaporator Concentrates, Oil, Miscellaneous Chemical Wastes, Filter Elements, and Dry Active Waste (DAW). This PCp is not normally applicable to DAW.
Other waste streams may be established based upon plant operating characteristics.
primary resins are collected in the spent resin storagc tank for blending, decay, and storage, primary resin sources are Chemical and Volume control System (CVCS) letdown demineralizers, boric acid evaporator demineralizers, and fuel pool demineralizers.
Secondary resin sources are condensato polisher resins and steam generator blowdown domineralizers.
Radwasto resins are contained in the portable radwasto demineralizers.
These domineralizers are fed by several streams including floor drain wastes, equipment drain wastes, laundry and hot shower wastes, and chemical wastes.
Evaporator concentrates are produced by the condensate demineralizer wasto evaporator (radwasto evaporator originally designed to process condensato polisher regenerate waste).
Sources to this evaporator are the same as to the portable radweste demineralizers and include floor drain wastes, equipnent drain wastes, laundry and hot shower wastes, and chemical wastes.
Additionally, the evaporator will process condensato polisher regenerate waste if primary to secondary leakage provento direct release of this waste.
Oil and miscellaneous chemicals are contaminated with radioactivity from various areas within the plant as a result of normal operation and maintenance.
Filter elements are disposed as radwasto from operation and maintenance of systems throughout the plant.
These systems include the reactor coolant system, boron recovery system, fuel pool purification system, and radwasto.
DAW is generated within the plant regulated arono and is not appropriately attributed to the above-mentioned wasto streams. DAW normally includes paper, plastic, wood, metal, and other such material generated as a result of the operation and maintenance of the plant.
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4 4.2 Waste Form Wet solid radioactive wastos consist of bead resins, filter aids (such as activated charcoals or carbons), evaporator concentratos, and slurrios or sludges.
Wastes Which may require solidification may include, but are not limited to, liquids which cannot be processed using installed plant systems, evaporator concentrates, oils, chemicals, aqueous filter media, and decontaminction wastes.
Westes are processed as appropriato to ensure that the mininum physical characteristics required by 10 CFR 61 and disposal sito criteria are met.
All Class B and Class C waste is stabilized.
Class A liquid wastes may be either solidified or packaged in sufficient absorbent material to absorb twice the volume of the liquid, as appropriato to the specific disposal site criteria or license requirements.
On occasion, Class A wasto (such as aqueous filter media with a concentration > 1 uCi/cc of isotopen with half-lives > 5 years) may be solidified or stabilized.
The solid radwasto system shall be used, as applicable, in accordance with a Process Control Program to process wot radioactive wastos to moet shipping and burial ground requirements.
Tests are performed on those waston which are solidified to ensure the adequacy of the solidification agent and/or procedural techniquo.
The Process control Program shall bo used to verify the solidification of at least one representative test specimen from at least overy tenth batch of each type of wet radioactive wasto (e.g., filter sludges, spent rosins, ovaporator bottoms, boric acid solutions, and sodium sulfato solutions).
If any test specimon fails to verify solidification, the solidification of the batch under test shall be suspended until such timo as additional test specimens can bo obtained, alternative solidification paramotors can be determined in accordance with the Procoso Control program, and a subsequent test vorifico solidification.
Solidification of the batch may then be resumod using tho alternative solidification parameters determined by tho Process Control program.
l With the provisions of the process control program not satisflod, suspend shipments of defectively processed, or l
defectively packaged solid radioactivo wastos from tho I
site.
If the initial test specimen from a batch os wasto l
fails to vertfy solidification, the Process Control Program shall provido for the collection and testing of representativo test upocimens from each consecutivo batch of l
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f 4.2 Waste Form (continuc6) the same type of wot waste until at least 3 consecutive initial test specimens demonstrate solifification. The process Control Program shall be modified as required, as provided in scetion 11.0 of this manual, to assure solidification of subsequer.t batches of waste.
Defectively processed or defectively packed solid radioactive wasto shall not be shipped to the disposal site until the waste is reprocessed or ropackaged to moot shipping, disposal site, State and Federal requirements.
The I
provisions of Technical Specification 3.0.3 and 3.0.4 are not applicabic.
l 4.3 Waste Classification scaling factors which relate hard-to-measure isotopes to key isotopes commonly measured at SQN have been developed for each waste stream.
These scaling factors are used in the classification of the wasto for disposal, scaling factors may be developed on an as needed basis depending on changing plant operational conditions. Updates are performed at least every two years for wasto normally considered to bo class A, on an annual basis for other wastes, or when the scaling factors are considered to be high or low by a factor of ten.
Radionuclide concentrations are determined by direct measurement.
Samples or smears, as appropriato, of standard waste streams are sont offsite for analysis.
An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopos which can be readily measured.
Scaling factors are developed on a wasto stream specific basis.
Scaling factors are periodically reconfirmed through sampling and analysis in accordance with reference 3.6.
DAW samples or area smears are taken to establish the relativo percent abundance of isotopos for the DAW wasto stream.
Plant procedures are in place to ensure compliance with 10 CFR 61.55 and 61.56.
Batch samples, ovaporator concentrates samples, or sludge sampics are collected for radiochemical analysis prior to processing the waste for shipment.
Materials which do not fit within the scope of existing scaling factors and waste streams are sampled.
The samples are sent offsito for analysis and development of scaling factors prior to disposal of the materlais.
4 4.4 Waste Containers High integrity Containers (HICs) manufactured by Chem-Nuclear Systems, Inc. (CNSI) are normally usod for packaging primary and radwesto resin and filters, as required for stability. The containers are discussed in a topical report dated December 1983 entitled, " Chem-Nuclear Systems, Inc., Topical Report Polyethylene High Integrity Containers CNSI-HIC-14571-01-NP." CNSI carbon eteel liners are used for packaging secondary and radwesto resins, and solidifying evaporator concentrates, as allowed by stability requirements.
5.0 CAPABILITY TO MEET 10 CPR SO APPENDIX I The dewatering and solidification processes do not cause any direct releases to the environment.
Offges from the processes is processed through the auxiliary building ventilation system described in the FSAR.
6.0 SHIPMENT MANIFESTS I
6.1 Manifest Preparation l
Manifests are prepared for each shipment of radioactive waste for disposal. Procedures for manifest preparation implement the specific requirements of 10 CFR 20.311, Transfer for Disposal and Manifests.
6.2 Manifest Tracking Acknowledgment of receipt for each shipment to a disposal site is sent to SQN Radwasto Section by the disposal site.
Shipments for which acknowledgment is not received within the timo limits allowed in 10 CFR 20.311 are traced by the TVA office of Nuclear Power, Corporate Water and Waste processing Department.
7.0 ADMINISTRATIVE CONTROLS 7.1 Procedures and Surveillanco Detailed procedures are maintained by SQN which cover plant process systems, waste packaging, and shipment l
requirements.
Surveillance Instructions aro used to verify l
that requirements for solidification are mot.
l Programmatic guidance is provided through the TVA Of fice of Nuclear Power, Water and Waste Proccocing Department.
The Water and Waste Proccasing Department maintains the Radioactive Material Shipment Manual.
7.2 Ouality Assurance /Ouality Control Quality assurance audits are conducted by the SQN sito Quality Assuranco organization, and by the Corporato Quality management, ganization. ensuring prompt corrective actions when nooded.
Assurance or Audit findings are reviewed by SON r
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7.2 Quality Assurance /Ouality control (continued)
Quality control nessures include site review of all radwaste vendor procedures before use and verification by SQN personnel of end points or acceptance criteria in vendor procedures.
Quality control of solidification methods is performed through controlled testing of a minimum of one sample from each batch to b's solidified. Proportions of solidification agents are established which meet the standards for waste form and free liquid criteria, rs 7.3 Trainina j
Personnel involved in processing radioactive waste for shipment are trained in sito procedures, regulatory requirements, and disposal site criteria applicable to the individual's responsibilitics.
Training and retraining sessions are held when needed to support operations.
Retraining is required on an annual basis to maintain qualification.
personnel found not complying with procedures may have their qualifications revoked by the
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Radwaste Manager.
Qualifications may be reestablished through completion of retraining, and approval of the Radwasto Manager.
7.4 Retention of Records Records are maintained to furnish documentation of items or activities affecting quality.
Quality assurance records are stored in accordance with plant and corporate instructions.
Retention times for radwesto records are established in the Radioactivo Material Shipment Manual.
8.0 WASTE TREATMENT 8.1 Evaporator Concentrates Solidification Waste is transferred to the cement solidification fillhead through an appropriately sized flexible hose.
Flow to the liner is controlled by a pneumatically-controlled valvo.
The hoso is connected to the fillhead by quick disconnect fittings.
A remote television monitor is used tu monitor the waste icvol in the stcol liner and a temperature recorder is used to monitor temperature in the linor during transfer, chemical addition, and the solidification exotherm.
The vent from the fillhead is connected to a portable scrubber and a HEPA unit.
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8.2 Solidification of Sludges, 011, and Miscellaneous Aqueous and Chemical Wastes The same solidification unit is used for solidifying sludges, oil, and miscellaneous aqueous and chemical wastes. The unit has the same plant / equipment interfaces except that the waste is not normally transferred to the liner through installed plant equipment. Liquid wastes are normally pumped from a storago container to the liner with an air-driven diaphragm pump.
8.3 Miscellaneous Solid Waste Encapsulation Encapsulation of miscellaneous waste is accomplished by loading waste in a basket inside the solidification liner.
The premixed cement formula is then transferred to the liner from a cement truck.
8.4 Spent Resin Spent resin is dewatered to moot the free-standing water limitations of licensed disposal facilities.
Resin can also be solidified.
8.5 Filter Element Radioactive filter elements are air dried for a minimum of r
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The elements are then visually inspected to ensure the filter is dry.
If the filters require stabilization by the disposal site license, the filters are disposed of either in a high integrity container or encapsulated.
If the filters do not require stabilization, they may be disposed as DAW, 9.0 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORTS The Semiannual Radioactivo Effluent Releaso Reports include the following information for each type of solid waste identified in Regulatory Guide 1.21, Revision 1 Table 3, Part A, which is shipped offsite during the report period:
a.
Total volume of containers, b.
Total curic quantity (specify whether determined by measurement or estimate),
s c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Type of quantity (e.g., LSA, Type A Typo B, etc.)
NOTE:
AddLLional information to bo included involving liquid and gaseous releases is described in the offsite Doso calculation Manual (ODCM).
9.0 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTS (continuid)
The Semiannual Radioactivo Effluent Release Report shall include any changen to the process Control program made during the reporting period.
It includes the type of solidification agent used, if applicable.
The Semiannual Radioactive Effluent Release Report includes major changes to radioactive wasto treatment systems in accordance with section 10.0.
10.0 LICENSEE INITIATED MAJOR CHANGES TO THE RADIOACTIVE WASTE SYSTEMS (LIQUID. GASEOUS AND SOLID):*
f Shall be reported to the Commission in the Semiannual Radioactive
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Rffluent Release Report f or the period in which the evaluation was reviewed in accordance with Technical Specification 6.5.1A.
s The discussion of each change shall contain:
a.
a summary of the evaluation that lod to the determination that the change could be made in accordance with 10 CFR 50.59; b.
sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.
a detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.
an evaluation for the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid wasto that differ from those previously predicted in the licenso application and amendments thereto; e.
an evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that. differ from thoso previously estimated in the licenso application and amendments thereto; f.
a comparison of the predicted releases of radioactive materials, in liquid and gaseous offluents and in solid waste, to the actual releasco for the period prior to when the changes are to be made;
- Submittal information required by this coction may be mado as part of the annual FSAR updato.
i 10.0 LICENSEE INITI ATED MAJOR CHANCES TO THE RADI0 ACTIVE WASTE SYSTEMS (LIOUID. GASEOUS AND SOLID):* (continued) g.
an estimate of the exposure to plant operating personnel as a result of the change; and h.
documentation of the fact that the change was reviewed and found acceptabic in accordance with Technical Specification 6.5.1A.
Shall became effective upon review and acceptanco in accordance with Technical Specification 6.5.1A.
11.0 LICENSEE INITIATED CHANGES TO THE PCP Shall be submitted to the Commission in the Semiannual Radioactive Effluent Rolcaso Report for the period in which the change (s) was made.
This submittal shall contains a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, b.
a determination that the chango did not reduce the overall cot.formance of the solidified wasto product to existing criteria for solid wastes; and c.
documentation of the fact that the change has been reviewed I
and found acceptable in accordance with Technical Specification 6.5.1A.
Shall become offective upon review and approval in accordance with Technical Specification 6.5.1A.
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1 APPENDIX A LOCATION AND ARRANGEMENT OF EQUIPMENT t
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Encapsulation, evaporator concentrates, or radwaste resin liner in shielding Solidification-cement trailer 4
Solidification Control Panel I
i 1-i FIGURE 1 LAYOUT EUR DENATERING RADWASTE RESIN, CEMENT SOLIDIFICATIG3 OF WEr WASTES, OR ENCAPSULATING MISCELLANEOUS RADWASTE IN TIIE AUXILIARY BUILDING RAILROAD BAY PLAN ELEVATIQi 706' s
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. Resin liner on trailer with overflow capacity i
TURBINE BUILDING CONDENSATE DEMINERALIZER BUILDING FIGURE 4 LAYOUT EUR DENATERING SECONDARY RESIN AT THE CONDENSATE DEMINERALIZER BUILDING e..
PLAN ELEVATION 701' mm__.,-
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APPENDIX B EXCEPTIONS TO OR DEVIATIONS FROM VENDOR TOPICAL REPORTS e
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APPEND 1K B EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT DATED DECEMBER 1983.
SQN dowaters bead resin and activated carbon using Chem-Nuclear Procedures FO-OP-023, " Bead Rosin / Activated Carbon Dewatering Procedure for CNSI 14-215 or smaller Linces." The dewatering system was fabricated by TVA to meet the equipment specifications in FO-OP-023 and Topical Report CNSI-DW-11118-01-NP. The TVA dewatering system differs from the Chem-Nuclear system in that:
(a)
SQN's system has no offgas collector.
The containers are open e
to the auxiliary building railroad bay during filling and dewatering.
Air from this room is normally discharged through the Auxiliary Building ventilation system as described in the FSAR.
(b) The valves on the pump suction manifold are manually operated. The system is not operated remotely. However, primary resih containers are enclosed behind a shielded wall or inside a shielded cask during filling and dowatering to keep radiation levels in the vicinity of the system near background.
(c) There is no automatic icvel control in the TVA dewatering system. Level is determined by visual observations and by level indicating instrumentation in the liner.
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