ML20064K973
| ML20064K973 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Brunswick |
| Issue date: | 10/27/1981 |
| From: | Kreger W Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20064E577 | List: |
| References | |
| FOIA-82-389 NUDOCS 8112020885 | |
| Download: ML20064K973 (2) | |
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DISTRIBUTION:
Docket File 50-325 Docket File 50-324 ETSB Reading File OCT 2 7 1991
-7ETSB Docket files WEKreger CSPau.
Docket f:os. 50-325/324 IEf;0RAf 01El FOR:
T. f ova!:, Assistant Director for Op:rcting fic:.ctcrs, D'.
FRO:;:
!!. E nreser, Assistant Director for Pcdiation Protection, OSI
SUBJECT:
ADDITIO !AL It:FOR:'ATIO:: f!EEDED FOR ETSB REVIEll 0F-BRU :S'!ICK, UilIT i0S.1 A::D 2, SPEilT FUEL POOL EXPA! 510:1 (TAC-43797) tlc have reviewed the licensee's submittal on the proposed second expansion of the spent fuel pool at Brunswick, Unit flos. I and 2, and find that ue need additional information to complete our review.
!!c need infomation concerning the design and expected increase in volume of demineralizer vaste for the spent fuel pool cleanup system, which was not addressed in the licensee's submittal. !!c also need the licensee's estimate of the volume of solid waste, if any, to be 7enerated by scrapping of exist-ing fuel storage racks incident to the re-rock'ing of the storage pool to increase its capacity.
This inforaation is needed by !!ovenber 18, 1981 to enable us to complete our review on schedule.
If there are any questions, contact 11r. J. Boegli (x27634) who is the cognizant reviewer for this facility.
Originni signed byt TN/ Hexeten kr 111111aa E. Kreger, Assistant Director for Radiation Protection Division of Systeas Integration
Enclosure:
Request for Additional Infomation cc:
R. itattson D. Eisenhut T. Ippolito
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~ 1 PROCESS CONTROL PROGRN4
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- A " Process Control Program" (PCP) for a solid radwaste system shall be a m$nual de' tailing the program of sampling analysis and formulation
~ determination by which solidification of radioactive wastes from liquid systems is assured.
The PCP. shall prohide assurance that the system is operated as designed and produces a final product that contains no free water and has completely sblidified all waste.
If properties of the final product hahe been determined by the manufacturer the PCP shall also assure that the solidified waste products exhibit those physical and chemical properties (leachability, strength, flammability, etc[),that are charac-teristic of the product as demonstrated by the manufacturer for producing an acceptable solidified waste product.
The PCP shall identify inter-faces with other plant systems (e.g., liquid and gaseous radwaste systems),
identify equipment (interlocks, alarms, monitors, etc.) which are required to be functional before processing can commence, identify administrative controls or equipment features to assure that operating procedures will be followed, identify the sampling requirements prior to processing and identifythehariousprocessingstepsandprocessparameterswhichprovide boundary conditions within which the solid radwaste system shall be operated.
Depending upon the type of waste (bead resins, powered resins, filter sludge, evaporator concentrates, sodium sulfate solutions, boric acid so'lutions, etc[] to be solidified and the kind of solidification agent (ure$ formaldehyde, cement, cement with sodium silicate, asphalt, poylester, etc.) employed, the process parameters shall include but are not limited
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the equations and assumptions to be used, the site specific parameters to be measured and used, the receptor location by direction and distance, andthemethodofestimatingandupdatingcumulatihedosesduetoliquid releases. The dose factors, pathway transfer factors, pathway usage factors, and dilution factors for the points of pathway origin, etc.,
should be given, as well as receptor age group, uater and food consump-I t'on rate and other factors assumed or measured.
Provide the method of determining the dilution fhttor at the discharge during any liquid effluent i
release and any site specific parameters used in these determinations.
Section 5 - Gaseous Effluent Dose Provide the equations and methodology to be used at the station or unit for each gaseous release point according to.the dose objectives given in Specifications 3.11.2.2 and 3.11.2.3.
The section should describe how the dose contributions are to be calculated for the harious pathways and release points, the equations and assumptions to be used, the site specific 2
parameters.'to be measured and used, the receptor location by direction and distance, and the method to be used for estimating and updating cumula-tive doses due to gaseous releases.
The location direction and distance j
to the nearest residence, cow, goat, meat animal, garden, etc., should I
be given, as well as receptor age group, crop yield, grazing time and other factors assumed or measured.
Provide the method of determining dispersion values (X/Q and D/Q) foi releases and any site specific para-meters and release point elevations used in these determinations.
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Section 6 - Projected Doses 7;
For liquid and gaseous radwaste treatment systems, provide the method of projecting doses due to effluent releases for the normal and alter-nate pathways of treatment according to the specifications, describing
[U the components and subsystems to be used.
i Section 7 - Operability of Equipment Provide a flow diagram (s) ' defining the treatment paths and the components c
l of the radioactive liquid, gaseous and solid waste management systems
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that are to be maintained and used, pursuant to 10 CFR 5b'36a, to meet Technical Specifications 3.11.1.3, 3.11.2.4 and 3.11.3.1.
Subcomponents D[' :.,. -
of packaged equipment can be identified by a list. For operating reactors whose construction permit applications were. filed prior to January 2, 1971, the flow diagram (s) shall be consistent with the information provided in conformance with Section V.B.1 of Appendix I to 10 CFR Part 50.
For OL applications whose construction permits were filed after January 2,1971, the flow diagram (s) shall be consistent with the information provided in Chapter 11 of the Final Safety Analysis Report (FSAR) or amendments
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thereto.
I Section 8 - Sample Locations Provide a map of the Radiological Environmental Monitoring Sample Loca-tions indicating the numbered sampling locations gihen in Table 3.12-1.
Further clarification on these nurtbered sampling locations can be provided
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y by a list, indicating the direction and distance from the center of the building complex of the unit or station, and may include a discriptive sL.
name for identification purposes.
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5 SOLID 3!ASTE 11A!!AGEl1 Erit SYSTEf15 -
Standard Review Plan 11.4 II) and Branch Technical Position ETSB 11-3(2)
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require that each applicant for an operating license provide a detail description' of a Process Control Program (PCP) to assure that the solid
- waste system will perform its intended function and that the product produced by this system contains no free water
- and is a monolithic solid.
Specification 3.11.3.1 of the inodel Radiological effluent Technical Specifications (3) require that the solid raduaste system be maintained and used in accordance with the PCP.
14UREG-0133(4) requires that at the time an applicant / licensee submits proposed Radiological Effluent Techni' cal Specifications that he submit the.PCP for flRC review.
NUREG-0133 further requires that the PCP be documented in the plant operating procedures.
To meet this commitment, the staff has prepared a general description of a PCP giving the essential points that should be covered by the applicant / licensee in making this submittal.
Due to variations in system design and operation, the applicant / licensee should not interpret this outline to be all inclusive.
The PCP is plant specific and must be established on a case-by-case basis since waste characteristics will
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vary from plant to plant.
- f ree water is defined as uncombined water not bound by the solid matrix.
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to, the type of waste, requirements for sampling prior to processing, pH, oil content, water content, temperature, ratio of solidification agent A
to influent waste and the ratio of solidification agent to chemical additive.
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for operating reactors which have systems installed that are not capable l
i of solidifying the categories of " wet" waste as defined in SRP 11.4, -
I BTP-ElSB 11-3 or fiUREG-013'3 the licensee shall define the limitations 'o i
his present system and provide a Process Control Program to cover the l'
The licensee shall waste that can be processed by his existing system.
identify those wastes which cannot be solidified and indicate the method ofpackagingcurrentlybeingemployed(dewateredresins,hermiculite,etc.)
j In addition, the licensee shall provide a schedule for upgrading his solid
.i waste system to provide the capability to process all types of " wet" -
wastes as defined in these reference documents. -
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REQUEST FOR ADDITIONAL INFOR!% TION FROM ETSB Q.
What volume of solid radioactive waste is expected to be generated as a result of re-racking of the Brunswick, Unit Nos. I and 2, spent fuel pool? Estimate the volume, as prepared for shipment (in drums, boxes
. or wrapped) to the disposal site.
Estimate the curie content of this
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waste.
Q.
Our records indicate that the spent fuel storage pool cleanup system contains two 500 gpm, 300 ft head, 60 HP pumps upstream of two heat exchangers and two filter /demineralizers. At what inlet water temperature do the pumps cavitate?
Please indicate if your design for the proposed modifications includes any change to the automatic backwash of the filter /demineralizers or automatic bypass to maintain a minimum total flow of 1000 gpm through the SFP system (Figure 8-1).
Also, indicate if the proposed expansion is expected to have any impact on the anticipated annual volume of demineralizer resin waste from this source; i
if so, provide your estimate of the annual volume and curie content.
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REFT.REtiCES
(-1)
Standard Review Plan 11.4, Revision 1, Solid Naste l'anagement Systems, !!UREG-75/087.
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(2)
Branch Technical Position - ETSB 11-3, Revision 1, Design Guidance for Solid Radioactive Waste fianagement Systems Installed in Light-Water-Cooled T-luclear Power Reactor Plants, flUREG-75/087.
Draft Radiolooical Effluent Technical Snecifications for PWRs and (3)
BURS, flUREGs 0472 and 0473.
(4)
Preparation of Radiological Effluent Technical Spe,cifications fo.
r fluclear Power Plants, fiUREG-0133.
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