ML19261B947

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Forwards NRC Recommendations for General Contents of Offsite Dose Calculation Manual Required W/Radiological Effluent Tech Specs from PWR & BWR Facilities
ML19261B947
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 02/13/1979
From: Stolz J
Office of Nuclear Reactor Regulation
To: Barton A
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 7903090122
Download: ML19261B947 (7)


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NUCLEAR REGULATORY COMMISSION

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%..... * 'g FEB 131379 Docket flo: 50-364 Mr. Alan R. Barton Senior Vice President Alabama Power Company 600 fiorth 18th Street Birmingham, Alabama 35291

Dear Mr. Barton:

SlJBJECT:

C0'lTErlTS OF THE OFFSITE DOSE CALCULATIO!1 MAi4UAL - JOSEPH M.

FARLEY NUCLEAR PLANT, UtlIT 2 The Radiological Effluent Technical Specifications for PWR and BWR facilities i~ssued in flovember 1978, require you to provide an Offsite Dose Calculation Manual (0DCM) with your proposed Technical Specifi-cations implementing 10 CFR 50.36a and other Federal Regulations.

The enclosure to this letter describes the staff's recommendations for the general contents of the ODCM.

The format for the CDCM is left to your discretion.

Sincerely,

/

Jo n F. Stolz, Ch f

ght Water Reactors Branch tio. 1 Division of Project Management

Enclosure:

General Contents of the ODCM CC*

See next page 7903090) &

Mr. Alan R. Barton FEB 13 D79 cc: George F. Trowbridge, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W.

Washington, D. C.

20036 Mr. Ruble A. Thomas, Vice President Southern Company Service P, O. Box 2625 Birmingham, Alabana 35202

GENER AL C0hTEMIS OF THE DJ'i

Section 1 - Set Points Provice the enua tions ana rethoddlocy to be used at the sta ticr. ce cc.i t for ea:n alarx and tric set point on each ef fluent release poir. acccedi g to the Speci fications 3.3.3.6 and 3.3.3.9.

Provide the alarn and control location, the monitor description, location, ocwer source, scale, range and identification number, and the ef fluent isciation control device, its location, po..er source and identification nu,ber.

If the set point value is variable, provide the enuation to be used to predetermine the set coint value that will assure that the Specification is met at each release point, and the value to be used when reh.ses are not in progress.

If dilution or dispersion is used, describe the on-site equipment and measurement method used during release, the site related parameters and the set ooints used to assure that the Specification is met at each release point, in-cluding any admir.istrative controls applicable at the station or unit.

The fixed and predetermined set points should consider the radioactive ef fluent to have a radionuclide distribution represented by normal and anticipated operational occurrences. Other features, such as surveillance requirements and the calibration method, should be addressed.

Section 2 - Liquid Effluent Concentration Previde the equations and methodology to be used at the station or unit for each liquid release point according to the Specification 3.11.1.1.

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~ The format for the ODCM is lef t up to the licensee and nay be sinplified by tables and grid printout.

Each page should be numbered and indicate the facility approval and effective date.

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-2 continuous and/or batch releases, the assumptions used for r.anual and autc-s natic terr.ination of releases should be provided.

For batch rel(ases, the calculational rethods, ecuations and assumptions'used, tocether with the pre-release ar.d post-release analyses should be provided.

Otner fea ures, such as surveillance requirenents, sanpling and analysis progran, detection limitations and representative sampling should be addressed.

Section 3 - Gaseous Ef fluent Dose Rate Provide the ecuations and methodology to be used at the station or unit for each gaseous release point according to Specification 3.11.2.1.

Consider the various pathways, release point elevations, site related parameters and radionuclide contr.ibution to the dose inpact limitation.

Provide the equa-tions and assumptions used, stipulating the'pa thway, receptor location and receptor age.

Provide the dose factors to'be used for the identified radio-nuclides released.

Provide the annual average dispersion values (X/0 and D/Q), the site specific parameters and rel' ease point elevations. Other features, such as surveilla ce requirements, sampling and analysis orogran, detection limitations and representative sampling should be addressed.

Section 4 - Liquid Effluent Dose Provide the equations and methodology to be Used at the station or unit for each liquid release point according to the dose cbjectives given in Speci-fications 3.11.1.2.

The section should describe how the dose contributions

'are to be calculated for the various pathways and release poikts, the equations and assumptions to be used, the site specific parameters to be

reasured and used, the receptor incation by direction and oist6nce,

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nethod of esti. atino and updatino cunulative doses cue to licuid relea;;s.

The dese fictors, pathway transfer factors, rathstay usage factcrs, and dilution factors for the Doints of pathway oricin, etc., should be civen, as well as receptor age group, water and food consumption rate and other factors assumed or neasured.

Provide the nethod of detennining the dilu-tkon factor at the discharge during any liouid ef fluent release and any site specific paraneters used in these deterninations.

Other features such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 5 - Gaseous Ef fluent 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 Speci-fications 3.11.2.2 and 3.11.2.3.

The section should describe how the dose contributions are to be calculated for the various pathways and release points, the equations and assunptions to be used, the site specific para-meters to be measured and used, the receptor location by direction and dis-tance, and the method estinating and updating cumulative doses due to gaseous releases.

the location direction and distance to the nearest residence, cow, goat, meat animal, garden, etc., should 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) for short-term and long-term releases and any site specific parameters

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anc release point elevations used in these cete'minations.

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"' criteria for detemining short and icne tirm releases.

Other fe6tures such as surveillance reouirements, sarolino and analysis oropra. cetection

. imitations and representative sarplinc should be adoressed.

Section 6 - Projected Doses Fo'r liquid and gaseous radwaste treatment systems, provide the method of projectino doses due to ef fluent releases for the nomal and alternate catb-ways of treatment according to the specifications, describing the cenpar.ents and subsystens to be used.

Section 7 - Ooerability of Ecuior.e3 Provide a flow diaaram(s) defining the treatnent paths and the ccnponents 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 con-struction permit applications were filed prior to January 2,1971, the flow diagram (s) shall be consistent with the infomation 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 diagran(s) shall be consistent with the infomation provided in Chapter 11 of the Final Safety Analysis Report (FSAR) or amendments ther'eto.

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  • rc*. ide a r.ac o' the Radiel epicii Er.s iror.montal !tni tc ri,g Fa sl e Le:atiar.s indicating the numbered sarpling locations given in Table 3.12-1.

Fur:nce clarification on tnese nu..t.srec sampling locations can : e revidee ey a list, incicating the direction and distance from the center of the buil0ing cecalex of the unit or station, and may include a disc riotive r.r.,e for identification purposes.

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