ML18092B038
| ML18092B038 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/13/1985 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18092B037 | List: |
| References | |
| PROC-850913, NUDOCS 8603100236 | |
| Download: ML18092B038 (10) | |
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. i ATTACHMENT 1 Revision 1 of the Salem Offsite Dose Calculation Manual The Salem 0ffsite Dose Calculation Manual (ODC~) has been revised in accor~~nce with the renuirements of Anrenrlix
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Technical SrPrification 6.1.14.
With the excention nt the RadioloGi~al fnvironmental Monitorinq Prnnram, the ODCM has ~~on completely refor~atted and reworked.
It is for this roascn that an approval/sinnature block has been added to the front of the ODCM instead of a raqe-by-paqe approval.
Each paqe of the ODCM reflects the revision number and date.
~s with the initially NRC approved ODCM, this revision has been based on the calculational guidance of NUREG-0133.
A summary of the chanqes i~ the following:
Additions/corrections to the areas as identified by the NRC in their December 13, 1984 approval letter:
Expansion of the dose evaluation from a total body and maximu~ nraan concept to a complete Regulatory Guide 1.109 seven orqan dose evaluation; Revisions to the calculated, default alarm setpoints incorporating additional site operational data and orovidin~, in qeneral, a more consistent application of the Technical Specification requirements; Inclusion of guidance on dose calculational methods for releases durinq primary-to-secondary leakage; Inclusion of additional guidance on dose evaluations for compliance with 40 CFR 190; and Inclusion of simplified conservative dose calculatinnal methods that may be used for rr.ovidinq a quick esti~ate of doses attributable to plant effluents lieu of the detailed dose evaluation.
The revisarl alar~ setnoints will be incornorated into the plant radiation monitnrinq system during the next scheduled calibration of the snecified monitor.
This revision also addresses the potential of simultaneous*
releases from Salem Cnits 1 and. 2 and from Hope Creek Nuclear Generatinq Station, which is scheduled to be operational by June 1986.
Corresoondinnly, the determination of allowable release rates include a.u;iit allocation factor -
a factor to ensure that simultaneou~ releases will not exceed the site instantaneous release rate limit le.a., 10 CFR 20 MPC limits for liquid effluents).
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'Hnor chA.nnes in the sarnnle locations as snecifierl i.n ::>er.tinn 4.0, Radi~lnciical ~nviron~ental Monitocinn
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an~ the avail~jilitv of sample type anri.locatinns.
Revision 1 of Pcocess Control Pronrar (PCP)
The revisions to the PCP consisted of addition of the process
- diaqrarn for solid r-adwaste as ner the su(jqestion of the us~;
1~c letter of December 13, 1984.
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SALEM GENERATING STATION, UNITS l & 2 Solid Radioactive Waste Process Control Program I.
Purpose Revision 1 9/13/85 In the processing of radioactive waste with the intention of final disposal at a licensed radioactiv~ waste burial site, it has beccme increasingly imp:>rtant that the waste products be appropriately analyzed, processed and packaged in a manner that meets the regulatory requirements, representing a final waste product that is acceptable for shallow land burial. The purpose of this Process Control Program is to docurrent the radioactive waste processing methods and the quality control steps that are taken at Salem to assure an acceptable waste product.
This Process Control Program covers all major waste processing streams and the final waste products. Operating criteria for waste processing are addressed as are solidification verifications, CC check points and visual examinations of the final waste product.
The waste streams, processing methods and solid radioactive waste products that are covered by this Process Control Program include:
Solidification of resins, Stock Cerrent System; Solidification of evaporator bottan, Stock Cerrent system; Solidification of oil; Cewatering of resins; *
.Packaging of non-eanpactable waste; Compaction of DAW; and Use of contractor for waste processing.
Figure 1 presents an overview of the solid radwaste processing system installed* at Salem.
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II
- Regulatory Overview All waste processing, packaging and shipping are conducted in accordance with approved procedures to assure canpliance with all applicable federal, state and b.Jrial site requirements. Waste processing is perforned within specified bounds with appropriate operating verifications to assure a product meeting applicable waste form characteristics; packaging is in containers meeting IXfI' specifications; and shipnents are conducted in accordance with the requirements of 49 CFR 172-177 and 10 CFR 71.
Ali waste processing is performed in a rnanner consistent with the principles of AIP.RA.
The procedures that have been developed to cover waste processing operations address apprq;>riate radiation safety measures such as job preplanning (REP}, radiation source shielding, and job prerequisites and material requirements so as to minimize stay times.
III. Solidification of Resins, Stock Cement System The norrnal method of processing spent resins at Salem is dewatering and disposal in an appropriate liner, carbon steel or HIC (See Section VI).
However, the installed Stock Cerrent System is available, if deemed necessary, for the solidification of spent resins fran both the reactor water clean-up system and the miscellaneous (radwaste) waste collection system.
System operation is by fully trained and qualified personnel. Prior to.the processing of resins, appropriate tests are conducted to assure the generation of an acceptable waste product. A laboratory verification of processing parameters is performed for any of the following conditions:
before initial full scale solification of a resin batch; if any resin has been added to the spent resin storage tank since last laboratory verification; and after the final full scale solidification for the day is canpleted.
The laboratory test to verify solidification includes collecting a representative sample of the resin (and water) and blending with a predetermined binder mixture. Mixing ratios for the resin, free standing Page 2 of 7
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water and binder are based on contractor supplied infonnation specifically developed for the solidification of resins. After blending, the sample is allowed to sit undisturbed for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Prior to full scale operation, the mixture is checked to verify solidification.
If the test mixture does not yield an acceptable solidified waste product, IOC>difications are made to the mixture ratios and a retest is conducted.
Final samples are retained for future observation of the solidified product and presence of any free water. A QA and supervisory check is required for the final approval of the solidification mixture prior to full scale processing.
Prior to full scale operation, a decant operation is performed to establish a proper resin/water slurry mixture (i2.5% free standif'.g water) in the decant tank.
Upon ccrnpletion of a resin batch processing, drums containing the solidified resins are stored at least 7 days prior to shiprent for disposal to assure sufficient time has been allowed for the cerrent to fully solidify and cure.
IV.
Solidification of Evaporator Bottcms, Stock Cement System All operations covering the determination of waste-to-cement mixing ratios and the actual evaporator bottans solidification process are covered by approved procedures. Fully trained and qualified personnel are utilized for all required operations. Prior to the full scale solidification of any batch of evaporator bottcms, a laboratory test is conducted to determine appropriate waste-to-cerrent mixing ratios to assure the generation of an acceptable waste*product. A 300-400 ml sample of the bottcrns is collected:
the pH is determined to be within the range of 6.0-9.0.
Based on the results of a l:x:>ron concentration analysis and the pH analysis, appropriate mixing ratios of the evaporator bottoms, cement and sodium metasilicate are selected from a naocx;;iram that has been developed specifically for the solidification of PWR evaporator bottans.
The bottoms sample is blended with the determined ratios of cerrent and sodium metasilicate. After blending, the mixture is allowed to stand for at least Page 3 of 7
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and checked for solidification. A supervisory and QA verification of proper solidification of the laboratory test sample is required prior to full scale operation. Samples of the latoratory test are retained until the waste has been accepted for burial.
Drums from the processing of an evaporator bottans batch are stored at least 7 days prior to shipnent to assure adequate cement curing time.
Radwaste Supervisor and QA sign-off is required prior to release for shipment.
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Solidification of Oil Oily wastes are segregated fran the routine waste processing systems and are processed independently. Oils are solidified in a disposable liner using a predaninantly manual operation. Since radioactive material contamination levels are relatively minor for oils, the use of rercote handling equipment and personnel shielding is not required f ran an AI.ARA standpoint as is for the processing of spent resins and evaporator bottans. Personnel that are fully trained in the procedures for waste oil processing are utilized for the performance of the solidification testing and actual waste processing.
Prior to the processing of any oils, a representative, canposite sample of the oils to be solidified is collected and a latoratory vedfication of
.solidification is performed. The COTiposite sample is analyzed for pH, radioactivity and percent water. A boron concentration analysis is performed on the water that is to be blended with the oil; concentration limits.for boron are <19,700 ppm boron or <120,000 ppm boric acid. If required, water is added to the oil to achieve a minimtnn of 40% water, by volune. A predetermined quantity of an errulsif ier is added at a ratio of 1 part emulsifier to 5 parts oil/water, by volurre. This mixture is blended for a minimum of 5 minutes, longer if needed to achieve a harogeneous mixture.
Cement (432 grams) and anhydrous soditnn metasilicate (50 grams) are blended in and allowed to stand for a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The product represents an acceptable solid waste if there is no visual or drainable water, holds its shape upon renoval fran the container, and resists penetration by a rigid rod. If unacceptable, the mixing ratios are adjusted and another laboratory test is conducted.
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Based on the latoratory determtnation of acceptable-waste and solidifying rredium ratios, the batch of oil is processed.
1\\.io ( 2) grab samples of the final waste product are collected from the liner. SOlidification is acceptable if upon visual examination the waste appears solid, resists penetration by a rigid rod and contains no visual free standing water. The 2 grab samples are also verified to constitute an acceptable solid waste product. A supervisor and QA verification is required of the final waste product.
VI. Cewatering of Resins
'Ihe processing of certain waste water by ion exchange resins results in a waste product that is more appropriately dewatered in a suitable disposable liner (carton steel or high integrity container) rather than solidified by the Stock Cenent System. Most reactor water clean-up resins and miscellaneous radwaste demineralizer resins are processed and disposed of in this manner. All dewatering processes are conducted in accordance with approved pr.ocedures with appropriate verifications and QA checks to assure a waste product with as little free standing water as possible tut in no case in excess of 1% by volurre. Prior to the dewatering of a resin liner, verifications are conducted of all temporary hose connections and of a suitable drain path for the rerroved water.
The procedure for the dewatering process requires an initial continuous 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> pumping of the liner to remove free standing water. The liner is allowed to stand for 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />s: dewatering is conducted at least 2 more times (rrore if needed) to rerrove any residual water that may have resulted from settling of interstitial water in the resin matrix. A record is kept of the volume of water rerroved on the third and subsequent de.waterings. The dewatering process is continued until rerroval of essentially all free standing water.
An acceptable volume of water from a de.watering operation that verifies rerroval of essentially all free standing water is <2000 ml. A QA inspect~on point is included in the dewater~ng procedure to verify the
<2000 ml removed water for the final dewateiing process.
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VII. Packaging of Non-Compactable waste Non-canpactable radioactive waste materials are segregated fran other DAW.
No oils, liquids or chemicals are allowed. Non-canpactable wastes are packaged in plastic or herculite lined I.SA boxes.
An inspection of the box is conducted prior to packaging to verify integrity. All materials are surveyed by Health Physics personnel prior to inclusion in a box. 'llle box is secured, weighed, numbered, surveyed and appropriately labeled for transportation.
VIII Canpaction of ~
Mos~ all cc:mpactable solid waste is processed by a box CCJTipactor prior to shipnent for turial so as to minimize the voll.llte.
DJring the canpaction process reasonable effort is made to ensure that no oils, liquids or chemicals are included. Boxes are inspected to assure a strong, tight container. Each box is secured, weighed, numbered, surveyed and appropriately labeled for tranportation.
IX.
Use of Contractor for Waste Processing Contractor supplied services may 'ce used at Salem for the processing of radioactive waste.
For the operation of such process systems, it may be desirable to use process control measures and procedures developed by the contractor specifically for the system. Therefore, previously addressed process control measures for a particular waste stream may 'ce superseded by contractor supplied rreasures as appropriate. The folla,..ring discussion addresses the administrative controls that are imp:>sed to assure that contractor supplied services for processing radioactive waste for disposal at
. a burial site are canpatible with plant operations, procedures and regulatory requirerrents.
Prior to the use of any contractor for the processing of waste at Salem, a managerrent review of the contractor's process controls and operating procedures is performed for the purpose of assuring a safe operation in accordance with plant procedures and applicable regulatory requirements.
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the processing of waste that i~ intended to be shipped for disposal to a licensed radioactive waste burial site, additional precautions are taken to assure a final waste product that meets the appropriate waste characteristic requirerrents for solidification or dewatering.
In ~rticular, the fella.Ying items are to be documented by the contractor (or Salem manuals or procedures) prior to utilization for solid waste processing at Salem:
a general description of the solidification process, including type of solidification agent, major process equipments and interface with plant equiprrent, type of wastes that can be processed, and operating
~rarreters:
~ a process control program that provides for the verification of the generation of a suitable waste product, including items such as representative sampling, latoratory tests to establish waste-to-process rredium ratios, and criteria for evaluating acceptability of lab test; specifically approved procedures for the operation of the process equipnent that will assure operation within the tounds as determined by the process control program; and,
~ppropriate QA check point and acceptance criteria for evaluating the acceptability of the final waste product.
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