ML19247A412
| ML19247A412 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/12/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Berry G POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 7907310459 | |
| Download: ML19247A412 (11) | |
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7 UNITED STATES y*
NUCt. EAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20658
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June 12, 1979 Docket No. 50-333 Mr. George T. Berry General Manager and Chief Engineer Power Authority of the State of New York 10 Columbus Circle New York, New York 10019
Dear Mr. Berry:
By letter dated May 2,1979 you submitted the Radiological Effluent Technical Specifications for the James A. FitzPatrick Nuclear Power Plant.
In this submittal, you indicated that the offsite dose calculation manual (0DCM) and the process control program (PCP) for solidification are within the site Administrative Procedures and would be indexed and available for inspection.
While the site Administrative Procedures may have the type of infonnation we have requested, these procedures usually contain a significant amount of unneeded information. Therefore, it is requested that the Power Authority provide a document specifically prepared for the Technical Specifications.
Attachments A and B provide guidance for ODCM and PCP preparation, respectively.
Your response is requested by July 15, 1979.
If we can be of assistance, please advise.
Sincerely, n
omas/ '
o, Chief Operating Reactors Branch #3 Division of Operating Reactors
Enclosures:
As stated cc w/ enclosures:
See page 2 490 094 790 7310 @j
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Mr. George T. Berry June 12, 1979 cc:
Lewis R. Bennett, Assistant General Manager / General Counsel Power Authority of the State of.'iew York 10 Columbus Circle New York, New York 10019 Mr. Peter W. Lyon Manager-Nuclear Operations Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Mr. J. D. Leonard, Jr.
Resident Manager James A. Fitzpatrick Nuclear Power Plant P. O. Box 41 Lycoming, New York 13093 Director, Technical Developmen+
Programs State of New York Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Oswego County Office Building 46 E. Bridge Street Oswego, New York 13126 George M. Wilverding, Licensing Supervisor Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 490 095
Revision 1 l
February 6, 1979 SOLID WASTE !%f1AGEf4Ef1T SYSTEMS Standard Review Plan 11.4(1) and Branch Technical Position ETSB 11-3(2) 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 ano that the product b
produced by this system contains no free water
- and is a monolithic I
solid.
1 I
Specification 3.11.3.1 of the Model Radiological effluent Technical Specifications (3) require that the solid radwaste system be maintained and used in accordance with the PCP. iiUREG-0133(4) requires that at the time an applicant / licensee submits proposed Radiological Effluent Technical Specifications that he submit the PCP for t'RC review, fiUREG-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 vary from plant to plant.
" Free water is oefined as uncombined water not bound by the solid matrix.
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PROCESS CONTROL PROGPJ41 A " Process Control Program" (PCP) for a solid radwaste systeca shall be a manual de' tailing the program of sampling analysis and formulation determination by which solidification of radioactive wastes from liquid l.
systems is assured. The PCP shall provide assurance that the system is operated as designed and produces a final product that contains no tree water and has completely sbiidified all waste.
If properties of the final product have been determined by the manviacturer the PCP shall also essure that the solidified waste products exh. bit those phy ical and chemical properties (leachability, strength, flammability, etc.) that are charac-teristic of the product as demonstrated by the manuf acturer 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 quicnent (interlocks, alarms, monitors, etc.) which are required to be functional before processing can commence, identify administrative controls or equipment features to assure that opr-ding procedures will be followed, identify the sampling requirements pr.
so processing and identify the various processing steps and process parameters which provide boundary conditions within which the solid radwaste system shall be operated.
Depending upon the type of waste (bead resins, pcwered resins, filter sludge, evaporator concentrates, sodium sulfate solutions, boric acid solutions, etc.) to be solidified and the kind of solidification agent (urer. formaldehyde, cement, cement with sodium silicate, asphalt, paylester, etc.) employed, the process parameters shall include but are not limited 490 097
. to, the type of waste, requirements for sampling prior to processing, pH, oil content, water content, temperature, ratio of solidification agent i
to influent waste and the ratio of solidification agent to chemical additive.
l NOTE:
For operating reactors which have systems installed that are not capable of solidifying the categories of " wet" waste as defined in SRP 11.4, 1
BTP-ETSB 11-
':t' REG-013'3 the licensee shall define the limitations of his present syste... and provide a Process Control Program to cover the waste that can be processed by his existing system.
The licensee shall identify those wastes which cannot be solidified anJ indicate the method of packaging currently being employed (deratered resins, vermiculite, etc.).
In addition, the licensee shall provide a schedule for upgrading his solid waste system to provide the capability to process all types of " wet" wastes as defined in these reference documents.
490 098
REFEREriCES l
(1)
StandardRehiewPlan11.4,Rehision1,SolidWasteManagement Systems,flUREG-75/087.
l (2)
Branch Technical Position - ETSB 11-3, Revision 1, Design Guidance j
for Solid Radioactive Waste Management Systems Installed in Light-Water-Conled fluclear Power Reactor Plants, fiUREG-75/087.
i
'3)
Draft.diological Effluent Technical Specifications for PWRs and
(
BWRs,fiUREGs 0472 and 0473.
j (4)
Preparation of Radiological Effluent Technical Specifications for 1
Nuclear Power Plants, flVREG-0133.
P 490 099
February 8, 1979 GENERAL CudTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (ODCM*)
i Section 1 - Set Points Prohidethe,equationsandmethodologytobeusedatthestationorunit i
for each alarm and trip set point on each effluent release point according to the Specifications 3.3.3.8 and 3.3.3.9.
The instrumentation for each
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alarm and trip set point, including radiation monitoring and sampling i
systems and effluent contrbl features, should be identified by reference to the FSAR (or Final Hazard Summary).
This information should be con-sistent with the recommendations of Section I of Standard Review Plan 11.5, NUREG-75/087,(Revism;1).
If the alarm and/or trip set point value is variable, provide the equation to determine the set point value to be used,' based on actual. release conditions, that will assure that the Speci-fication is met at each release point; and provide the value to be used when releases are not in progress.
If dilution or dispersion is used, state the on-site equipment and measurement method used during release, the site related parameters and the set points used to assure that the Specification is met at each release point. The fixed and variable setpointsshouldconsidertheradioactiYec'fluenttohaYearadio-nuclide distribution represented by normal and anticipated operational occurrences.
Section 2 - Liquid Effluent Concentration Provide the equations and methodology to be useo at the stat' ion or unit "The format for the ODCM is.left up to the licensee and may be simplified by tables and grid. printout. Each page should be numbered and indicate the facility approval and effective date.
490 100
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for each liquid release point according to,the Specification 3.11.1.1.
For systems with continuous or batch releases, and for systems designed tomonitorandcontrolbothcontinuousandbatchreleases,proYidethe as.sumptions,and parameters to be used to compare the output of the i
monitor with the liquid concentration specified. State the limitations for combined discharget to the same release point.
In addition, describe
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themethodandassumptionsforobtainingrepresentatihesamplesfromeach I
batch and the use of previbus post-release analyses or composite sample
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analyses to meet the Specification.
f Section 3 - Gaseous Effluent Dose Rate Provide the equations and methodology to be used at the station or unit for each gaseous release point according to Specificaticn 3.11.2.1.
Con-sider the various pathways, release point elevations, site related para-meters and radionuclide contribution to the dose impact limitation.
Provide the equations and assumptions used, stipulating the pathway, receptor location and receptor age.
Prohidethedosefactorstobeused for the identified radionuclides released.
Providetheannualaherage dispersionhalues(X/QandD/Q),thesitespecificparametersandrelease point elevations.
Section 4 - Liquid Effluent Dose Prohidetheequationsandmethodologytobeusedatthestationorunit foreachliquidreleasepointaccordingtothedoseobjectihesgihenin Specification 3.11.1.2.
The section should describe how the dose contri-butionsaretobecalculatedforthehariouspathwaysandreleasepoints, 490 101 e
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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
,he dose factors, pathway transfer factors, pathway usage releases.
T factors, aad dilution factors for the points of pathway origin, etc.,
should be given, as well as receptor age group, water and food consump-
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tion rate and other factors assumed or measured. Provide the method of k
determining the dilution fhttor at the discharge during any liquid effluent i
I release and any site specific parameters used in these determinations.
l 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 thedosecontributionsaretobecalculatedforthehariouspathwaysand release points, the equations and assumptions to be used, the site specific 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 begiYen,aswellasreceptoragegroup,cropyield,grazingtimeand other factors assumed or measured. Prcvide the method of determining dispersion values (X/Q and D/Q) for releases and any site specific para-metersandreleasepointelehationsusedinthesedeterminations.
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Section 6 - Projected Doses 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 the components and subsystems to be used.
I.
Section 7 - Operability of Equipment 1
Provide a flow diagram (s) ifefining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems that are to be maintained and used, pursuant to 10 CFR 50.36a, to meet Technical Specifications 3.11.1.3, 3.11.2.4 and 3.11.3.1.
Subcomponents 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 thereto.
Section 8 - Sample Locations Provide a map of the Radiological Environmental Monitoring Sample Loca-tions indicating the numbered sampling locations given in Table 3.12-1.
Further clarification on these numbered sampling locations can be provided 490 103
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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 name for identification purposes.
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