ML17272A322

Forwards Recommendations for General Contents of Offsite Dose Calculation Manual,To Be Submitted W/Proposed Radiological Effluent Tech Specs

ML17272A322
Person / Time
Site:	Columbia
Issue date:	02/16/1979
From:	Varga S Office of Nuclear Reactor Regulation
To:	Strand N WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
NUDOCS 7903140148
Download: ML17272A322 (13)

Text

(3 Docket No:

50-397 ion:

oc et Fzl s

Local PDR S. Varga H. Silver M. Service (2)

LNR II4 File

Attorney, ELD FEB 16 1979 Mr. Neil 0. Strand Washington Public Power Supply System 300 George Nashington Nay P. 0. Box 968

Richland, Washington 99352

SUBJECT:

CONTENTS OF.THE OFFSITE DOSE CALCULATION hQNUAL (NPPSS Nuclear Project No. 2)

The Radiological Effluent Technical Specifications for PNR and BNR facilities issued in November 1978, require you to provide an Offsite Dose Calculation Manual (ODCM) with your proposed Technical Specifications implementing 10 CFR 50.36a and, other Federal Regulations.

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

The format for the ODCM is left to your discretion.

Sincerely, Original signed by:

S. A. Varga Steven A. Varga, Chief Light Nater Reactors Branch No.

4 Division of Project Management.

Enclosure:

General Contents of the ODCM cc:

See next page 7so3i4o(

(3'M:LNR 84 OSSICd IO DLynch:tlb SURNAME~

OATS~ 2/14/79 Form ARC-318 (RST. 9.53) hECM 0240 D

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)Og Masldington Public Power Supply System ccs:

Joseph B. Knotts, Jr.,

Esq.

Debevoise 8 Liberman 700 Shoreham Building 806 Fifteenth Street, N.

W.

Washington, D.

C.

20005 Richard Q. Quigley, Esq.

Washington Public Power Supply System 3000 George Washington Way P. 0.

Box 968 Richland, Washington 99352 Nepom 8; Rose Suite 101 Kellogg Building 1935 S.

E. Washington Ni lwaukie, Oregon 97222 Vis. Helen Vozenilek 7214 S.

E. 28th Street

Portland, Oregon 97202 Hs. Susan H. Garrett 7325 S.

E. Steele Street

Portland, Oregon 94206 Nicholas Lewis, Chairman Energy Facility Site Evaluation Council 820 East Fifth Avenue Olympia, Washington 98504 FEB 10 879

P'ection 1 - Set Points Provide the eouations and r.ethodolqoy to be used at thy station or unit 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.

Provide the alarm and control P

location, the monitor description, location, power source,

scale, range and identification number, and the effluent isolation control device, its

location, power source and identification number.

If the set point value is variable, provide the equation to be used to predetermine the set point value that will assure that the Specification is met at each release

point, and the value to be used when releases are not in progress.

If dilution or dispersion i,s used, describe the on-site equipment and measurement

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method used during release, the si tp related parameters and the set points used to assure that the Specification is met at each release point, in-eluding any administrative con/rois applicable at the station or unit.

The fixed and predetermined set points should consider'he radjoactive effluent to have

~ radionuclide distribution represented Py normal and anticipated operational occurrences.

Other features, such as surveillance requirements and the calibration method, should be addressed.

Section 2 - Li uid Effluent Concentration Provige thy equations and methodology to be used at the station or unit for each.liquig release point according to the Specification 3.)1. 1. 1.

For

• The format for the ODCH 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.

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continuous and/or batch releases, the assmgptions used for manual and auto-matic termination of releases shoul~!

be provided.,

For batch releases, th calculational

methods, equations and assumptions

used, together with the pre-release and post-release analyses shoul d be provided.

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

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 Specification 3.11.2.1.

Consider the various

pathways, release point elevations, site related parameters and radionuclide contribution to the dose impact limitation.

Provide the equa-tions and assumptions used, stipulating the pathway, 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 0/l}), the site specific parameters and release point elevation.',.

Other

features, such as surveillance requirements, sampling and analysis

program, detection limitations and representative sampling should be addressed.

Section 4 - Li uid Effluent Dose Provide the equations and methodology go be used at the station or unit for each liquid release point according tq the dose objectives 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

points, the equations and assumptions to be used, the site specific parameters to he

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measured and used, the receptor location by direction and distance, and :he method of estirating and updatino cumulative doses due to liquid releas s.

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'he dose factors, pathway transfer factors, oathway usaoe factors, and dilution factors for the points of pathway origin, etc.,

should be. given, as well as receptor age group, water and food consumption rate and other factors assumed or measured.

Provide the method of determining the dilu-tion factor at the'ischarge during any liquid effluent release and any site specific parameters used in these determinations.

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

Section 5 - Gaseous Effluent Dose Provide the equations and methodology to be used at the station or unit for each gaseous release point accordinq 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 assumptions to be used, the site specific para-meters to be measured and used, the receptor location by direction and dis-

tance, and the method estimating 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 qroup, crop yield, grazinq time and other factors assumed or measured.

Provide the method of determining dispersion values (X/g and D/(}) for short-term and long-term releases and any site specific parameters

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and release point elevations used in these determinations.

)lqo, provide the criieri~ for determining short and long tePiil releases.

Othe-features such as surveillance repuirements, sar plina and analysis program"., detection limitations and representative sampling should be addressed.

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 alternate path-ways of treatment according to the specifications, describing the components and subsystems to be used.

Section 7 - 0 erabilit of Equi ment Provide a flow diagram( s) defining 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 con-struction permit applications were filed prior to January 2,

1971, the flow diagram(s) shall be consistent with /he 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 provid( d in Chapter 11 of the Final Safety Analysis 'Report (FSAR) or amendments tt ereto.

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V' Section 8 - Sar:.-le Locations

.'rovide a rap o, the Radioloaical

-"ryiron-,.ental honitorino.'a-pie Locations indicating the numbered sanplino locations aiyen in Table 3.12-1.

Further clarification on. these nu-.,bered sampling locations can be'provided bv a

list, indicatino the. direction.and distance from the center of the buildina complex of the unit or station, and may include a discriptive name for identi fication purposes.

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