ML17298B145

Solid Radwaste Process Control Program

ML17298B145
Person / Time
Site:	Palo Verde
Issue date:	08/07/1984
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17298B144	List: ML17298B143 ML17298B145
References
PROC-840807, NUDOCS 8408130277
Download: ML17298B145 (16)

Text

SOLID RADWASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION 8408i$ 0277 840807

'DR ADOCK 05000528 PDR A,

'7P31A/21PyA)

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TABLE OR CONTENTS Section Title ~Pa e 1.0 PURPOSE 2.0 DEFINITIONS AND ABBREVIATIONS 3.0 PROGRAM DESCRIPTIONS 3.1 Waste Types 3.2 Process Parameters 3.3 Waste Classification 3.4 Waste Preconditioning 3.5 Verification of Solidification 3.6 Stability Requirements 3.7 Data Sheets 3.8 Record Retention 3.9 Radiological Precautions

4.0 REFERENCES

APPENDICES Appendix A Schematic Plow Diagram Appendix B Radwaste Cement Solidification System

1.0 PURPOSE The purpose of the Process Control Program (PCP) for Palo Verde, Units 1, 2 and 3 is to establish a set of process parameters which will provide reasonable assurance of complete solidification of various liquid radio-active "wet wastes" including resin slurries, evaporator bottoms, filter sludges and chemical drains in accordance with the requirements of appli-cable portions of the Palo Verde Quality Assurance Program, Department of Transportation (DOT) regulations, Nuclear Regulatory Commission (NRC) regulations, licensed burial facilities acceptance criteria, and 10 CFR 61 for solidification, packaging and shipment to an approved off-site burial site. There are no Arizona State Regulations applicable to PVNGS.

Toward this purpose the PCP ensures that the solidified substance is a monolith having no free standing liquid and is within the limits as set forth in the above mentioned regulations and acceptance criteria. This PCP will also ensure solidification will be performed to maintain any potential radiation exposure to plant personnel to "as low as is reason-able achievable" ALARA levels.

2.0 DEFINITIONS AND ABBREVIATIONS

a. ~SA As low as is reasonably achievable.

b. Batch A quantity of water type(s) prepared in the waste feed tank for solidification.

c. Bench Laboratory testing of the solidification process on a Test reduced scale with representative mixing ratios and similar operational techniques.

d. Wet waste types are liquid radioactive wastes, sludges and 'ion exchanger resins.

e. Monolith A free standing, solid object.

3.0 PROGRAM DESCRIPTION

a. Appendix "A" "Schematic Flow Diagram" illustrates the different waste types to be processed by the solidification system. They are listed as follows:

1) Chemical regenerative and decontamination waste (evapor-ator concentrates) from a forced recirculation evaporator.

2) Boric Acid waste from the Boric Acid Concentrator.

3) Bead resin waste as a slurry from the Spent Resin Tanks.

4) Chemical Drain Tank waste.

5) Spent filter cartridges.

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b. Typical and atypical wet waste types shall be identified by the "Solidification Process Control" procedure, which provides a record of waste formulations.

c~ When the radiation level of a waste batch is determined to be excessive by ALARA standards, a waste substitute shall be pre-pared in accordance with the "Solidification Process Control" procedure.

3.2 Process Parameters

a. An acceptable waste product for transfer and disposal in accor-dance with 10 CFR 20.311 for Class A, B and C waste shall be provided by compliance with the "Solidification Process Control" procedure and the "Solidified Radioactive Waste Classification" procedure.

b. The process parameters for various class-A wastes shall be based on the "Hittman Radwaste Solidification System (cement) topical report, HN R1109 NP, Rev. 4 and the "Solidification Process Con-trol" procedure. These documents establish boundary conditions to provide reasonable assurance that solidification will be com-plete.

C~ For class-A waste types containing concentrations of chemicals that do not fall within the bound of chemical concentrations for which pre-operational solidification tests have been performed by Hittman Nuclear and Development Corporation, acceptable base data for test solidifications shall be developed in accordance with the "Solidification Process Control" procedure.

'd ~ In the event the inplant system is inoperative due to mainten-ance, repairs or modifications, a portable solidification system will be used to process class A, B and C waste types in accor-dance with the vendor's operating procedures and qualified 10 CFR Part 61 Topical Report.

e. For class-B and class-C waste types a 10 CFR Part 61 qualified solidification process will be used on the installed solid radwaste system in accordance with the "Solidification Process Control" procedure, or a portable solidification system will be used in accordance with the vendor's operating procedures and qualified 10 CFR Part 61 Topical Report.

Process mixing ratios for class-A, B, and C waste types shall be determined for each waste batch in accordance with the "Solidi-fication Process Control" procedure.

3.3 Waste Classification

a. The "Solidified Radioactive Waste Classification" procedure shall provide PWR scaling factors for identifying specific radionuclides as required by 10 CFR 61.55 "Waste Classification".

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b. Scaling factors shall be verified or updated annually by waste stream analysis to ensure acceptable standards are maintained for waste classification.

c. During incident conditions where the use of the existing scaling factors is questionable, the waste shall be classified by corre-lation factors or actual sample analysis in accordance with the "Solidified Radioactive Waste Classification" procedure.

3.4 Waste Preconditionin

a. The "Operation of Solidification System" procedure shall desig-nate the required mixing/recirculation times and system opera-tions to ensure a representative sample is obtained after chemi-cal addition and prior to process initiation.

b. Adjustment of the waste solution pH shall be in accordance with the "Operation of Solidification System" procedure.

c. The "Operation of Solidification System" procedure shall desig-nate when heat tracing is required to ensure chemical suspension.

3.S Verification of Solidification

a. Solid Radwaste S stem

1) The solidification bench tests per Hittman Topical Report Radwaste Solidification (cement) System, HN-R1109-NP, Rev.

4, provides the solidification bench testing base data for the "Solidification Process Control" procedure and class-A waste type.

2) 'The solidification bench tests per a 10 CPR Part 61 quali-fied vendor's Topical Report will provide the bench test-ing base data for the "Solidification Process Control" procedure and class-B and C waste type.

3) During solidification system operations, additions to the waste feed tank, waste feed pump operations and process mixing ratio adjustment shall be in accordance with the "Operation of Solidification System" procedure.

i. No additions will be made to the waste feed tank while the tank is being recirculated for sampling or pro-cessing.

ii. The waste feed pump will not be stopped during samp-ling.

4) A periodic solidification bench test shall be performed as specified by and in accordance with the "Solidification Process Control" procedure for verification of an accept-able solidification process.

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5) If any solidification bench test is found not to be accep-table, subsequent operations and testing shall be in accordance with the "Solidification Process Control" procedure.

6) The solidification bench test Acceptance Criteria shall be in accordance with the "Solidification Process Control" procedure.

7) Solidification product quality is assured by the performance of the "Operation of Solidification System" procedures.

b. Portable Solidification S stem The portable solidification vendor will verify proper solidifi-cation of the waste product in accordance with the vendor's operating procedures and Topical Report.

c. Handling of unacceptable solidified waste containers shall be in accordance with the "Operation of Solidification System" pro-cedure.

3.6 Stabilit Re uirements The "Solidification Process Control" procedure shall identify the stability specifications as set forth in 10 CFR 61.56 "Waste Char-acteristics", and Branch Technical Position ETSB 11-3, Rev. 2, July 1981, "Design Guidance for Solid Radioactive Waste Installed in Light Water Cooled Nuclear Power Plants".

Management'ystems 3.7 Data Sheets

a. For each solidification bench test actually used for waste pro-cessing, a test data record shall be maintained in accordance with the "Solidification Process Control" procedure.

b. For each batch solidification process a feed rate determination shall be completed in accordance with the "Solidification Process Control" procedure.

c. For each batch solidification process, record shall be used for recording the unique batch information in accordance with the "Solidification Process Control" procedure.

d. For each batch solidification process, a waste classification record shall be completed in accordance with the "Solidified Radioactive Waste Classification" procedure.

3.8 Record Retention i

For each batch solidification proc'ess, all records generated shall be maintained 'in accordance with the "Document and Record Turnover procedure.

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3.9 Radiolo ical Precautions The radiological precautions necessary for implementing the Process Control Program shall be followed and are covered in the "Radiation Protection Program" procedure.

4.0 REFERENCES

a. NUREG-0472, Radiological Technical Specifications for PWR.

b. 10 CFR 20, Standards for Protection Against Radiation.

c. 10 CFR 71, Packaging of Radioactive Material for Transport.

d. PVNGS Unit One Interim Technical Specifications, Oct. 28, 1983.

e. 49 CFR Subchapter C, "Department of Transportation Hazardous Mat-erials Regulations".

f. Palo Verde Nuclear Generating Station Final Safety Analysis Report, Section 11.4, 12.1 and 12.3 (Amendment 12).

g. "AIBA Program" procedure.

h. "Operational equality Assurance Program" procedure, Rev. l.

Standard Review Plan 11.4, Rev. 2, July 1981. "Solid Waste Manage-ment Systems" procedure.

"Solidification Process Control" procedure.

k. "Operation of Solidification System" procedure.

1. "Solidified Radioactive Waste Classification" procedure.

m. "Document and Record Turnover" procedure.

n. Hittman Radwaste Solidification (Cement) Topical Report HN-R1109-NP, Rev. 4, Apr. 1977,Section VII, "Cement Solidification Process Chem-istry".

o. Branch Technical Position ESTB 11-3, Rev. 2, July 1981, "Design Guidance for Solid Radioactive Waste Management Systems Installed in Light Water Cooled Nuclear Power Plants".

p. 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste".

q. "Radiation Protection Program" procedure.

APPENDIX A EVAPORATOR CONC NT ATE MONITOR TANKS WASTE FEED TANK CHEMICAL DRAIN TANKS CEMENT AND ADDIT VE WASTE/CEMENT PROCESSOR SPENT DRUM OR RESIN LINER TANKS SPENT FILTER CARTRIDGES SCHEMATIC FLOW DIAGRAM

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APPENDIX B CEMENT TANK ADDITIVE ROTARY VALVF ADDITIVE FEED CONVEYOR CEMENT ROTARY VALVE INPUTS AND CONVEYOR MIXER WASTE FEED TANK WASTE l CEMENT PROCESSOR DRUM OR LINER RADWASTE CEMENT SOLIDIFICATION SYSTEM

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