ML19221B099
| ML19221B099 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-11.2, NUREG-75-87, NUREG-75-87 11.2, SRP-11.02, SRP-SRP-11.02, NUDOCS 7907120423 | |
| Download: ML19221B099 (6) | |
Text
NUREG 75/087 en asc
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STANDARD REVIEW PLAN
- s OFFICE OF NUCLEAR REACTOR REGULATION SECTION l1.2 LIQUID WASTE MANAGEMENT SYSTEMS REVIEW RESPONSIBILITIES Pr ma.y - Effluent Treatment Systems Branch (ETSC) i Seconda.y - Radiological Assessment Brc..ch (RAB)
Structural Engineering Branch (SEB)
I.
AREAS OF REVIEW At the construction permit (CP) stage, ETSB reviews the information in the applicant's preliminary safety analysis report (PSAR) in the specific areas that follow. During the operating license (OL) stage of review, ETSB review consists of confirming the design accepted at the CP stage and evaluating the adequacy of the applicant's technical specifications in these areas.
1.
The liquid radwaste treatment system desig1, design objectives, design criteria, methods of treatment, expected releases, and principal parameters used in Lalcula-ting the releases of radioactive materials in liquid effluents. The ETSB review will include *ne system piping and instrumentation diagrams (P& ids), and process flow diagrams showing methods of cperation and factors that influence waste treatment, e.g., system interfaces and potential bypass routes.
2.
Equipment design capacities, expected flow and radionuclide concentrations, expected decantaminatic.1 factors for radionuclides, and available holdup time.
The system design capacity rela ivt to the desig, and expected ir:put ticws, and the period of time the system is required to be in service to process normal waste flows. The availability of standby equipment, alternate processing routes, and intert.onnections between subsystems. This information is used in the ETSB review to evaluate the overall system capability to meet anticipated demands imposed by major processing equipment downtime and waste volume surges due to anticipated operational occurrences.
3.
The quality group classifications of piping, and equipment, and the bases governing the design criceria chcsen. Provisions to prevent, control and collect releases of radioactive material in liquids due to tank overflows from all plant systems, outside reactor containment having the potential to incur such releases. Design and expected temperatures and pressures, and materials of construction of the components of the liquid waste management system.
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USNRC STAND ARD REVIEW PLAN C
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croreto nuc6eer power plente These documente are mode ove* table to ene pubnc en post of the Cnmmies on a pohcv to inform the nucsur movetry and the O
general pwthe of requietory procedures and pohcies Standeed review piene are not evDet'tutes for reguletery evideo or the Cornesee.on a regulet.ons and comphence w*th the w.e not required The stenderd review peen ooctione are hoved to Reviesen 2 of the Stenderd Formet end Content of Sa'ety taetveis Rooorte for Nwcseer power Planie Not eel sectione of the Stenderd Formet have a serreepending review pian Published etendard reweem plane w d be revtsed periodiceity es appropatete to accommodate comenente and to reHect new enformation end superience e
Commente and suggeottene for improvement will be concedered and should be sent to the U $ Nucleer hogusatory Commise'en O'fke of Nucine Reactor Reg.,setion Washangton. O C 20MB
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4.
Design provisions incorporated in the equipment and facility design to reduce leakage and facilitate operation and maintenance in accordance with the guidelines of Regulatory Guide 1.143.
(Ref. 10) 5.
Special design features that would reduce liquid input volumes or discharge of radioactive material in liquid effluents. Spec i t. ' ds_ sign features, topical reports incorporated by reference, and data ont6iaed from previous experience with similar systems which are submitted ith the SAR.
6.
The technical specifications proposed by the applicant fcr process and effluent control will be reviewed at the operating license stage (FSAR).
Design provisions inco porated to sample and monitor radioactive materials ia liquid process and effluent streams are reviewed under SRP Sections 11.5 6nd 9.3.2.
RAB will provide calculated doses based on the ETSB liquid source terms for inclusiot. in the staff's Environmental Impact Statement and Safety Evaluation Report.
SEB evaluates the applicant's proposed seismic design of structures housing the liquid radwaste system for inclusion in the staft's Safety Evaluation Report The consequences nf liquid tank failures having the potential to release radioactive liquids are evaluated in SRP Section 15.7.3.
II.
ACCEPTANCE CRITERIA The applicant's design should meet the following criteria:
1.
The iiquid radw3ste treatment system should have the capability to meet the requirements specified in 10 CFR Parts 20 and 50 and the dose design objectives specified in Appendix I to 10 CFR Part 50, including provisions to treat liquid radioactive waste such that:
a.
The calculated annual total quantity of all radioactive material released from each reactor at the site to unrestricted areas will not result in an es'.imated annual dose or dose commitment from liquid effluents for any individual in an unrestricted area from all pathways of exposure in excess of 3 millirems to the total body or 10 millirems to any organ.
b.
In addition to a. above, the liquid radwaste treatment systems should include all items of reasonably demoastrated technology that when added to the system sequentially and in order of diminishing cost-benefit return, can for a favorable cost-benefit ratio effect reductions in dose to the population rearonably expected to be within 50 miles of the reactor.
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Rev. I 11.p-2
The concentrations of radioactise materials in liquid offluents released to an unrestricted area should not exceed the limits in 10 CFR Part 20, Appendix B, Table II, Column 2.
2.
The liquid radwaste treatment system should bc designed to meet the anticipated processing requirements of the station. Adequate capacity should be provided to process liquid wastes during periods when major processing equipment may be down for maintenance (single failures) and during periods of excessive waste generatien.
ETEB will accept systems that have adequate capacity to process the anticipated wastes and that are capable of operating within the design objectives during normal operation, including anticipated operational occurrences. To meet these processing demands, ETSB will consider interconnections between subsystems, redundant equipment, and reserve storage caoacity.
3.
The seismic design of structures housing liquid radwaste systems, the quality group classification of liquid radwaste treatment equipment, and provisions to prevent and collect spills from indoor and outdoor storage tanks should conform to the guidelines of Regulatory Guide 1.143.
4.
ETSB will accept system designs that contain provisions to control leakage and facilitate operation and maintenance in accordance with the guidelines of Regulatory l
Guide 1.143.
III. REVIEW PROCEDURES The reviewer will select and emphasize material from this review plan, as may be apprnpriate for a particular case.
1.
In the ETSB review of the liquid waste treatment system, the P& ids ano system process flow diagrams are reviewed to determine all sources of liouid input volumes, the points of collection of liquid waste, the flow paths of liquids through the system including all bypasses, the treatment provided, and the points of release of liquid effluents to the environment. This information is used to calculate the quantity of radioactive caterials released annually in liquid effluents during normal operatio:, including anticipated cperational occurrences, using the parameters giveq, the GALE Code, and calculational techniques given in NUREG-0016 and NUREG-0017. A complete Fortran listing of the GALE ccmputer code is given in these reports. The results of this calculation will be useo to determine whether the proposed treatment system design meets the acceptance criterion of II.l.c.
CoTpliance with the acceptance criteria given in subsection II.l.a concerning exposures to the total body of critical organ of an individual in an unrestricted area will be determined based on RAB dose calculations using the ETSB-calculated source term.
Compliance with the acceptance criterion given in II.l.b concerning the cost-benefit analysis will be determined based on RAB man-rem dose calculations in conjur.ction with ETSB cost-benefit studies.
11.2-3 Rev. 1
2.
The ETSB review of the liquid waste treatmenc tem design capacity will encompass three major areas:
The system ca pbility to process wastes in the event of a single major a.
equipment item failure, e.g.,
an evaporator outage.
b.
The system capability to accept additional wastes during operations which result in excessive liquid waste generation.
The system cap 3bility to process wastes at design basis fission pr0Juct c.
leakage levels, i.e.,
from 1% of the fuel producing power in a NR or, in a EWR, consistent with a r.cble gas release of 100 pCi/sec/MWt measured after 30 minutes delay.
ETSB will cortpare the average input flows to the design flows to determine the fraction of time individual subsystems must be online to process normal w3ste inputs.
ETSB will review the operational flexibility designed into the system, i.e., cross connections between subsystems, redundant or reserve processing equipment, and reserve storage capa:ity. Based on the usage factors and operational flexibilities, ETSB will evaluate tne overall system capability to process wastes in the event f (a), (b), or (c), above, by comparing the design flows to the potential prccess routes and equiprent capacities ETSB will assure evaporators are unasailable for 2 c snsecutive days pe' week for maintenance. If two days holdus capacity or an alternative esap3rator are not available for the process stream, ET5B will assume the strem is processed by an alternate route or discharged to the environment, consistent with the gJidelines of NUREG-0016 and NUREG-0017.
3.
ETSB compare-the quality groi.p classification for rad aste systems with the guidelines of Regulatory Guide 1.143.
ETSB assures that the desian includes provisions to prevent and cc!1ect leahge due to overf!cws and spillage frcm indoor and outdoor storage tanks, are in conformance with the guidelines of Regulatory Guide 1.143.
SEB reviews tme seismic design criteria of structures housing the liquid radaaste system in 3ccordance with the design ';uidance identified in Regulatc ry Guide 1.14 3.
4.
ETSB ccTpires the system design, system and building layout, equipment design, method of operatico, and provisions to reduce leakage and facilitate operations and maintenance with the guidelines of Regulatory Guide 1.143.
ET5B will evaluate special design features provided to control le3kage frca system compenents and topical reports on systems designed on a case-by-case basis.
5.
ETSB reviews the technical specificatians proposed by the acplicant for process and effluent control. The revie-er will determine that the content and intent of the technical specifications are in agreement with the requirements developed as a result of the staft's review.
The review will include the evaluation or O
i$Q Rev. 1 11 2-4
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development of apprcoriate lic'..nq conditions for operation and their bases consistent with the plant design.
IV.
EVALUATICN FINDINGS ETSB Serifies that :ufficient information has beer, provided and that the revie is 3dequate to support conclusions of the following type, to be included in the st3ff's saf ety evaluation report:
"The liquid r3dwaste treatment systems in:lude the equipment and instrumentation to control the release of radioactive materials in liquid effluents."
In our evaluation, we have considered releases of radioactive materials in liquid effluents for noimal operation including anticipated operatio al occurrences based on expected radwaste inputs over the life of the plant for each re3ctor on the site. We have determineu that the proposed liquid radwaste treatment sy m m: are capable of maintdning releases of radioactive materials in liquid effluentb such that the calculated individual doses in an unrestricted area frcm all pathways of exposure are less than 3 millirems to the total body l
and 10 millirems to any organ.
We have also considered the potential effectiveness of aug.nting the prcposed liquid rad *>ste treatment systems using items of reasonably demorstrated technology and have determined that further ef flu?nt treatrent will not ef fect reductiens in the cumulative population dose reas3nably cxpected within a 50 mile radius of the reactor at a cost of less than $1000 per man rem or man-thyroid-rem.
We have also considered the potential consequences resulting from reactor operation, and we have determined the concentrations of radioactive materials in liquid effluents in unrestricted areas will be a small fract.on of the limits in 10 CFR Part 20, Appendix C, Table II, Column 2.
We have considered the capabilities of the proposed liquid rad-3ste treatment system to meet the anticipated demands of the plant due to anticipated operational occurrences and have concluded that the system capacity and design flexibility are adequate to meet the anticipated needs of the plant.
We have reviewed the applicant's quality assurance provisions for th-liquid radwaste systems, the quality group classifications used for system components, and the seismic design applied to structures housing these systems. The design of the systems and structures housing these cystems meet the criteria as set forth in Regulatory Guide 1.143.
We have reviewed the provisions incorpor ated in the applicant's design to control the release of radioactive materials in liquids due to inadvertent tank overflows and conclude that the measures proposed by the applicant are consistent with t M criteria as set forth in Pegulatory Guide 1.143.
14 4U 11.2-5 Rev.
Based on the foregoir.g eG;uat!cr. we conclude thit the preposed liquid radalste treatment system is ac cept %Ie TW basis f or acceptance has been conformance of the applicant's design, design criteria, and design baces for the liquid radioactive wis'e treat"'ent systens to the Ccmmission's regulations and to applicable Regulatory Guides, as reierenced above.
V.
REFERENCES 1.
10 CFR Part 20, " standards for ?rotection Against Radiation," and Appendir 6,
" Concentration in Air and Water Abave h ural Background."
2.
10 CFR s 50.34a, " Design Objectives for Equipment to Crntrol Releases of Radioactive Material in Effluents - Nuclear Power Reactors."
3.
10 CFR 4 50.36a, " Technical Specifications on Effluents from Nuclear Pcwer Reactors."
4.
10 CFR Part 50, Arpendix A, " General Design Criteria for Nuclear Power Plants."
5.
10 CFR Part 51, " Licensing and Regulatory Policy and Procedures for Er.vironmental Protection."
6.
10 CFR Part 50, Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Practicable" for R3dioactive Material in Light-Water-Cooled N.. clear Po er Reactor Ef fluents.
7.
Regulatory Guide 1.21. " Measuring, Evaluating, and Reporting R3dioactivity in Solid n'astes and Releases of Radioactive M3terials in Liquid and Gaseous Effluents from L ight-Water-Cooled Nuclear Power Plants. '
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8.
NUREG-0017, " Calculation of Releases of Ridicactive Materials in Gaseous and Liquid Ef fluents f rom Pressurized Water Reactors (PnRs). "
l 9
NUREG-0016, " Calculation of Releas^s cf Radioactive Materials in Gaseous and Liquid Efriuents f rom Boiling Witer Reactors (E'*Rs ). "
10.
Requ!atcry Guide 1.143, " Design Guidance for Radioactive Waste Mar,agement Systems, Struc+ures and t.omonents in Light-Water-Cooled Nuclear Reactor Power Plants."
Rev. 1 11.2-6