ML20127E419
| ML20127E419 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/12/1984 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20127E410 | List: |
| References | |
| PGP3-ZO-0017, PGP3-ZO-17, NUDOCS 8506240542 | |
| Download: ML20127E419 (13) | |
Text
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D OU TON LIGHTING AND POWER COMPANY SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION PLANT PROCEDURES MANUAL SAFETY RELATED Radioactive Waste Process Control Program PGP3-ZO-0017' Rev. O Page 1 of 13 APPROVED: (du.
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DATE APPROVED DATE EFFECTIVE This procedure is not described in the FSAR.
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1.0. Purpose and Scope 1.1 Purpose.
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This procedure establishes the Process Control Program for South Texas Project Electric Generating Station (STPEGS) and provides necessary instructions to insure that all Plant generated radioactive wastes are transferred, packaged, and shipped such that applicable Federal Regulations, State Rules and Regulations, and Burial Site Criteria are satisfied.
1.2 Scope This procedure defines criteria for the processing of the following waste streams:
a.
Compressible Wastes b.
Noncompressible Waste c.
Miscellaneous Waste 1.
Repa Filters 2.
Absolute Filters 3.
Activated Charcoal d.
Cartridge Filters (O
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Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. O Page 2 of 13 e.
Resins f.
Evaporator Concentrates 2.0 Definitions
2.1 Batch
A specified volume of waste material of which any portion possesses the same physical and chemical characteristics as the whole.
2.2 Process Control Program (PCP): The program to assure that the solidification of wet radioactive wastes results in a waste form with properties that meet the requirements of 10CFR Part 61 and of low-level radioactive waste disposal sites. The PCP shall identify, either in the program description, or by reference to implementing procedures, process parameters influencing solidification such as pH, oil content, H,,0 content, solids content, ratio of solidification agefit to waste and/or necessary additives for each type of anticipated waste. Acceptable boundary conditions for the process parameters shall be identified for each waste type, based on The PCP laboratory scale and full scale testing or experiences shall also include an identification of conditions that must be satisfied, based on full scale testing, to assure that dewatering of bead resins will result in volumes of free water, at the time of disposal, within the limits of 10CFR Part 61 and of low-level radioactive waste disposal sites.
2.3 Solidification
The immobilization of wet radioactive wastes such as evaporator concentrates, spent resins, sludges, and reverse osmosis concentrates as a result of a process of thoroughly mixing the waste type with a solidification agent (S) to form a free standing monolith.
3.0 Precautions No liquid materials within the scope of this procedure are to be 3.1 packaged unsolidified for offsite shipment.
No package will be loaded for shipment if it has any indication of a 3.2 hole, failure, or weak spot. These packages must either be repacked, or placed in an overpack.
All samples shall be handled and collected in accordance with 3.3 applicable STPEGS procedures and in keeping with ALARA principles.
Any Vendor Process Control Program supplied in support of 3.4 solidification or dewatering services must be reviewed and approved by the Plant Operational Review Committee and must undergo regulatory review in accordance with Licensing commitments.
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Radioactive' Waste Process Control Program PGP3-ZO-0017 Rev. O Page 3 of 13 4.0 Procedure The following waste types may be either solidified, packaged in high integrity containers or packaged in approved containers as specified by specific STPEGS procedures.
4.1 Compresible Waste All contaminated or potentially contaminated compressible waste will be taken to a designated area and will then be compressed into approved strong tight containers. Types of material which would be in non-compliance with the appropriate regulations will not be placed into a package for baling. Each package will be sealed and stored until loaded for shipment and offsite disposal. All materials will be packaged and handled in accordance with PCP14-WS-0004,(Dry Radioactive Waste Operations).
NOTE O
In this vaste type subsection and in all waste type subsections to follow unit numbers will not be referenced in procedure numbers as this PCP is interfaced by both units one (1) and two (2).
4.2 Noncompressible Waste All contaminated or potentially contaminated noncompressible waste will be taken to a designated area where the waste will be placed in an appropriate package. Material which would be in noncompliance with the appropriate regulations will not be placed into a package.
Each package will be sealed and stored until loaded for shipment and offsite disposal. All materials will be packaged and handled in accordance with PCP14-WS-0004 (Dry Radioactive Waste Operations) 4.3 Miscellaneous Waste All contaminated or potentially contaminated miscellaneous vaste will be taken to a designated area where the vaste will be placed in an appropriate package. Material which would be in noncompliance with the appropriate regulations will not be placed into a package.
Each package will be sealed and stored until loaded for shipment and offsite disposal. All materials will be packaged and handled in
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accordance with PCP14-WS-0004 (Dry Radioactive Waste Operations)
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f Radiosctive Waste Process Control Program PGP3-ZO-0017 Rev. O Page 4 of 13 4.4 Cartridge Filters 4.4.1 Filters will be accumulated from one or more of the following systems:
a.
Chemical Volume Control System b.
Spent Fuel Pool Cooling and Cleanup c.
Boron recycle d.
Liquid Waste Processing Systes e.
Steam Generator Blowdown System l
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Miscellaneous 4.4.2 Filters will be allowed to drain, preferably in their
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respective filter housing until they contain i 1% free water.
The filters will then be placed in temporary storage.
O NOTE An initial test program will determine individual t
filterdraintimesrequiredtosatisfythei1%
free water specification 4.4.3 Prior to emplacement in a preselected High Integrity Container (HIC) contact and one (1) meter radiation levels will be measured to ensure compatability of filter with the HIC and to determine total curie content respectively.
4.4.4 All contaminated filters will be packaged and handled in accordance with PCP14-WS-0005 (Liquid Filter Operations) 1 4.5 Resins 4.5.1 Resins will be accumulated from one or more of the following systems.
a.
Chemical Volume Control System b.
Spent Fuel Fool Cooling and Cleanup c.
Boron recycle l
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Liquid Waste Processing system e.
Steam Generator Blowdown System 4.5.2 Spent resins from radioactively contaminated plant demineralizers are transferred to the spent resin storage tanks to await final packaging. Packaging, shipment and offsite disposal of contaminated resins shall be in approved HIC's utilizing Vendor, supplied dewatering services. These activities will be performed under an STPEGS approved vendor l
PCP. The proper cask and HIC to be used during transport will be predetermined prior to sluicing of spent resin to a HIC.
j NOTE Condensate Polisher Demineralizers resins re-quiring processing under the STPEGS approved l
Vendor PCP will be transferred directly from the demineraliser vessels to a vendor supplied dewatering skid.
4.6 Evaporator Concentrates 4.6.1 The Liquid Waste Processing System (LWPS) is designed to collect, transport, and process radioactive liquids either for release to the environment or for solidification. Liquid waste will be concentrated in the LWPS evaporator prior to being solidified in the Hittman inplant cement solidification i
system or transferred to a vendor for solidification.
Evaporator influent will consist principally of either:
a.
Boric Acid (H 50 ) containing liquids 3 4 b.
Sodium Sulfate (Na SO ) containing liquids.
2 4 4.6.2 Borated waste streams are normally either recycled or processed through desineralizers and released to the environment. If release or recycle is not available, this waste stream will be processed by evaporation in the Sodium Tetraborate (Na,B 0 *7H O) form and transferred to the
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Hittman in-plant system or transferred to a vendor for solidification. Borsted waste streams may originate from the Floor Drain Tank, Waste Holdup Tank, Recycle Holdup Tank, or Laundry and Hot Shower Tank.
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i O1 Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. O Page 6 of 13 4.6.3 Condensate Polisher Demineralizer regeneration chemical wastes may be required to be processed through the LWPS in the event of significant primary to secondary leakage. These regeneration solutions are transferred to the Condensate Polishing Regeneration Waste Collection Tank and subsequently concentrated in the LWPS Evaporator. Concentrates in the form of Sodium Sulfate (Na,SO ) are processed either in the 4
Hittsan inplant solidificaEion system or transferred to a vendor for solidification.
4.6.4 All containers will be packaged and handled in accordance
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with PCP14-WS-0003 (Solid Radwaste Processing Systems Operations).
4.6.5 All vendor solidification services will be conducted in accordance with STPEGS approved vendor procedures.
4.7 Collection and Analysis of Samples O
NOTE This section applies to in-plant solidification operations. Vendor solidification services shall be performed in accordance with a STPEGS approved Vendor Process Control Program.
4.7.1 Required Batch Sampling and Analysis 4.7.1.1 Each batch of waste for solidification in the Hittman in plant system shall be sampled and analyzed in accordance with PCP7-ZS-0009 (Local Sampling of Spent Resin Transfer and Solid Waste Systems) and PCP6-ZR-0012 (Determination of Waste Solidification Parameters and Test Sample l
Solidification). Results of this test shall be used to:
I a.
Determine applicable preestablished mix ratios b.
Provide analytical data for applicable regulatory and disposal site criteria c.
Determine alternate solidification mix ratios for those waste streams not previously identified.
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Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. 0
.Page 7 of 13 4.7.2 Technical Specification Sampling and Analysis 4.7.2.1 As required by the Radiological Effluent Technical Specifications (RETS), the solidification of at least one (1) representative test sample from at least every tenth batch of each type of wet radioactive waste processed shall be performed in accordance with PSP 7-WS-0001 (Process Control Program Test Sample Solidification).
4.7.2.2 For high activity wastes, where handling samples could result in personnel radiation exposures which are inconsistent with ALARA principles, representative non-radioactive samples which are as close to waste chemical properties as possible may be test solidified.
4.8 Test Solidification Sample Preparation The Laboratory scale test solidification is representative of the full scale solidification process. When required by the PCP, test O
sample solidification is performed to confira established six ratios for routine waste streams, or establish acceptable six ratios for non routine waste streams. The following is a general outline of the requirements of the Test Solidification Sample Preparation. The detailed procedure for the aforementioned is found in PSP 7-WS-0001 (Process Control Program Test Sample Solidification).
The following is a general outline of the requirements of the test sample preparation.
4.8.1 Obtain a sample solution which is the same chemically and physically as the unadjusted solution to be processed. The sample should be at the same temperature as the actual waste.
4.8.2 Adjust pH of waste as follows:
1.
pH 2, 9; 12% Sodium Tetraborate 2.
pH 2,13; 25% Sodium Sulfate 4.8.3 Determine the amount of waste and cement to be used in the verification test. As a starting point refer to the mixing ratio graph contair.ed in PCP14-WS-0003 (Solid Radwaste Processing Systems Operations) whose formula most closely resembles the actual waste. Use a point on the center of
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this band for the initial test.
Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. 0 Page 8 of 13 4.8.4 Mix cement, waste and additives as required in a disposable beaker using a mechanical mixer or similar mixing tool.
4.8.5 Seal container well, and set aside. Observe setting of cement thirty (30) minutes after preparation, then again after twenty-four (24) hours.
4.8.6 A sample whose mixing ratios show the criteria in section 4.9 at thirty (30) minutes and twenty-four (24) hours will produce the same results on a larger scale.
4.8.7 Record the results of this section as instructed in PSP 7-WS-0001 (Process Control Program Test Sample Solidification).
4.9 Test Solidification Acceptance Criteria The purpose of the test solidification samples prepared in section 4.8 is to produce a product which meets the following acceptance criteria:
4.9.1 A firm set, with no free water, thirty (30) minutes after preparation and, 4.9.2 A hard, dry, free standing monolith which will avoid (resist) penetration, twenty-four (24) hours after preparation.
NOTE For the purpose of this procedure "No" free water shall be defined as 1/2 of 1% by volume.
4.10 Test solidification Unacceptability If any test fails to meet the acceptance criteria in section 4.9 in the given time frame the following guidelines should be followed:
If any sample fails to solidify, solidification of the batch a.
under test shall be suspended until such time as additional test samples can be obtained, alternate solidification parameters can be determined, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternate solidification parameters.
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Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. 0 Page 9 of 13 b.
Representative test samples shall be collected from each consecutive batch of the same type of waste until three (3) consecutive specimens demonstrate solidification using the alternate parameters.
The detailed procedure for the aforementioned test failure is found in PCP6-ZR-0012 (Determination of Waste Solidification Parameters and Test Sample Solidificaton).
NOTE Alternate solidification parameters must be ap-proved by the Radwaste Foreman or his/her designee.
4.11 Waste Solidification Data Sheet
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A Waste Solidification Data Sheet (PCP14-WS-0003-1) shall be maintained for each package of solidified radioactive waste s
material. Detailed instructions for completing the aforementioned are contained in PCP6-ZR-0012 (Determination of Waste Solidification Parameters and Test Sample Solidification) and PCP14-WS-03 (Solid Radweste Processing Systea Operations).
4.12 Shipping Requirements All Federal Regulations, State Rules and Regulations, and Burial Site Criteria which are applicable to the waste forms which have been addressed in this procedure will be included in PCP1-ZA-0026 (Shipment of Solid Radioactive Waste). This procedure will provide detailed instructions and required documentation to insure waste shipped from STPEGS for offsite disposal meets compliance requirements.
4.13 10CFR 61 Compliance Methodology i
4.13.1 All radioactive vastes generated at the STPEGS will meet the waste classification and waste form stability requirements established in Title 10 Code of Federal Regulations (Energy)
Part 61 (10CFR61). The detailed procedure for classifying waste types is contained in PCP1-ZA-0025 (Weste Stream Sample Collection and Classification).
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Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. O Page 10 of 13 4.13.2 Waste types will be classified using the following methodology:
4.13.2.1 Compressible Waste, Noncompressible Waste, and Miscellaneous Waste:
a.
A reactor coolant liquid sample will be sent to an offsite Laboratory for the required analysis of 10CFR61.55.
b.
Upon receipt of the Laboratory analysis the principle gamma emitters will be determined and a percent abundance calculated,for each. These principle gamma emitters will be redetermined on i
an annual basis or as required.
c.
Prior to shipment of each package a contact radiation level and one (1) meter radiation 1evel will be taken. The one (1) meter radiation level is for the determination of package curie content.
d.
The gamma isotopic content may then be calculated from the percent abundance of each contributing isotope. The four (4) principle beta emitters (H-3, C-14, Tc-99, I-129) may then be either calculated using established r
correlation factors or the results from the offsite Laboratory analysis may be utilized for classification purposes.
4.13.2.2 Cartridge Filters A reactor coolant crud sample will be sent to an a.
offsite Laboratory for the required analysis of 10CFR61.55.
l b.
Upon receipt of the Laboratory analysis the principal gamma emitters will be determined, and a percent abundance calculated for each. These l
principal gamma emitters will be redetermined on an annual basis or as required.
c.
Prior to shipment of each filter a contact radiation level and one (1) meter radiation level will be taken. The one (1) meter radiation level is for the determination of each filters curie content.
PCP3-ZO-0017 Radioactive Waste Process Control Program
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Rev. 0 Page 11 of 13 d.
The gamma isotopic content may then be calculated from the percent abundance of each contributing isotope. The four (4) principle beta emitters may then be either calculated using established correlation factors or the results from the offsite Laboratory analysis may be utilized for classification purposes.
Each filters individual radionuclide curie e.
content will then be summed over the entire package to obtain a total activity for each nuclide present.
4.13.2.3 Resins i
A representative resin sample, typical of that a.
transferred to a vendor for dewatering will be l
sent to an offsite Laboratory for analysis.
Results of this analysis will be used to correlate easy to measure gamma emitting nuclides with those nuclides which are difficult l
to measure with equipment available on site, For each batch of resin shipped a representative b.
sample of resin will be taken for gamma isotopic Results of this analysis will be analysis.
utilized to calculate an isotopic abundance for i
j each radionuclide present.
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A one (1) meter radiation level reading of a one c.
hundred (100) al. sample representative of the batch to be shipped will be used to calculate the total curie concentration for gamma emitting The percent abundance determined in isotopes.
step b. of this section and the total curie content will then be used to calculate individual nuclide concentration. Documentation of curie content and nuclide distribution is contained in PCP1-ZA-0026 (Shipment of Solid Radioactive Waste).
The four (4) principle beta emitters (H-3, C-14, d.
Tc-99, 1-129) may then be either calculated using established correlation factors or the results from the offsite Laboratory analysis may be utilized for classification purposes.
Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. O Page 12 of 13 4.13.2.4 Evaporator Concentrates a.
A sample (S) of both Sodium Sulfate and Sodium Tetraborate liquid waste forms will be sent to an offsite Laboratory for the required analysis of 10CFR61.55. Results of this analysis will be used to correlate easy to measure gamma emitting i
nuclides with those nuclides which are difficult to measure with equipment available on site.
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b.
The gamma isotopic content and tritium content will be determined on a per container basis, in accordance with PCP1-ZA-0026 (Shipment of Solid Radioactive Wasta).
c.
The remaining three (3) principle beta emitters may then be either calculated using established correlation factors or the results from the offsite Laboratory analysis may be entered.
4.13.3 Waste form stability requirements will be met either by packaging stability (HIC's) or by a documented testing program which verifies that solidified waste products meet the requirements of 10CFR61.56.
4.13.4 For the purposes of this section waste streams will be reanalyzed on an annual basis to verify established nuclide distribution and correlation factors unless a ten (10) percent change in the waste stream is noted.
4.13.5 For the purposes of this section a ten (10) percent change in waste stream will be defined as a ten (10) percent change (increase) of failed fuel.
i 5.0 References i
5.1 Code of Federal Regulations 49CFR Transportation 5.2 Title 10 Code of Federal Regulations Energy l
5.3 TRCR Part 45, " Licensing Requirements for Near-Surface Land Disposal of Radioactive Waste".
l 5.4 PCP14-WS-0003 " Solid Radwaste Processing System Operations" 5.5 PCP14-WS-0004 " Dry Radioactive Waste Operations" 5.6 PCP14-WS-0005 " Liquid Filter Operations" s
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Radioactive Waste Process Control Program PGP3-ZO-0017 Rev. O
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Page 13 of 13 5.7 PCPI-ZA-0026 " Shipment of Solid Radioactive Waste" 5.8 PSP 7-WS-0001 " Process Control Program Test Sample Solidification 5.9 PCP1-ZA-25 " Waste Stream Sample Collection and Classification" 5.10 PCP7-ZS-0009 " Local Sampling of Spent Resin and Solid Waste Systems 5.11 PCP6-ZR-0012 " Determination of Waste Solidification Parameters and Test Sample Solidification" 5.12 Radiological Effluent Technical Specifications - STPEGS 6.0 Addenda None O
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