ML18031A109

Forwards NRC Recommendations for Preparation of Offsite Dose Calculation Manual & Radiological Effluent Tech Specs

ML18031A109
Person / Time
Site:	Susquehanna
Issue date:	02/14/1979
From:	Parr O Office of Nuclear Reactor Regulation
To:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
References
NUDOCS 7903050080
Download: ML18031A109 (14)

Text

FEB 14 1979 Docket Nos. 50-387/388 Yr. Norman H. Curtis lice President - Engineering and Construction Pennsylvania Pomr and Light Company 2 North hinth Street Allentown, Pennsyl vania 1810T

SUBJECT:

CONTENTS OF THE CFFSITE DOSE CALCULATION MANUAL (Susquehanna Steam Electric Station, Units 1 and 2)

The Radiological Effluent Technical Specifications for NR and BAR facilities issued in November 1978, require you to provide an Offsite Dose Calculation Manual (ODCM) i~ith your proposed Technical Specifi-cations impleventing 10 CFR 50.36a and other Federal Regulations.

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

The format for the ODCM is left to your discretion.

Sincerely, Orlgtnak Signed bY O. D. Parr Olan D. Parr, Chief Light Hater Reactors Branch No. 3 Division of Project Fhnagement

Enclosure:

General Contents of the ODCM cd M/enclosure:

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Mr. Norman W. Curtis FEB 1 4'979 cc:

Hr. Earle M. Mead Project Engineering Manager Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Jay Silberg,, Esq.

Shaw, Pittman, Potts 5

Trowbridge 1800 H Street, N.

W.

Washington, D. C.

20036 Mr. William E. Barberich, Nuclear Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Bryan Snapp, Esq.

Pennsylvania Power 5 Light Company 901 Hamilton Street Allentown, Pennsylvania 18101 Robert H. Gallo Resident Inspector P. 0.

Box 52 Shickshinny, Pennsylvania 18655 Mr. Robert J. Shovlin Project Manager Pennsylvania Power and Light Co.

2 North Ninth Street Allentown, Pennsylvania 18101 Alan R. Yuspeh, Esq.

Shaw, Pittman, Potts 8

Trowbridge 1800 H Street, N.

W.

Washington, D. C.

20036

GEt)ERAL COD EATS OF THE 00"ll*

Section 1 -

~Se Points Provide the e'ouations and nethodology to be used at the station or unit fol each al arm and trip set noint on each effluent rel ease point according to the Specifications 3.3.3.8'and 3.3.3.9.

Provide the alarm and'control

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 is used, describe the on-site equipment and measurement method used during release, the site related parameters and the set points used to assure that the Specification js met at each release point, in-eluding any administrative controls applicable at the station or unit.

The fixed and predetermined set ppints should consider the radioactive effluent 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

> Li uid Effluent Concentration Provide the equations and methodology to be used at the station or unit for e~ch liquid release point according to the Specification 3. 11. 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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con inuous and/or batch releases, the assumptions used for manual and auto-matic termination of releases shoul~! be provided.

For batch releases, th calculational

methods, eouations and assumptions

used, tooether with the pre-release and post-release analyses should be provided.

Other features, such as surveillance requirements, sampling and analysis program, detection limitations and representative samplina 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 accordinq to Specification 3. 11.2. 1.

Consider I

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 Pose factors to be used for the identified radio-

.nuclides released.

Provide the annual average dispersion values (X/0 and

'D/0), 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 to be used at the station or unit for each liquid release point according to 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 be

, I measured and used, the recentor location by direction and distance, and he method of estirating and updating cumulative doses due to liquid releases.

The dose factors, pathway transfer factors, oathway usaoe factors, and dilution -,"actors for the points of 'pathway origin, etc.,

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

Provide the method of determining the dilu-tion factor at the discharge 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 E,ffluent 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 an'd '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 group, crop yield, grazing time and other factors assumed or measured.

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

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and release point elevations used in these determinations.

Also, provide the criteri~ for determining short and long term releases.

Othe" features such as surveillance requirements, sarplina and analysis prograr., 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 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 provide d in Chapter ll of the Final Safety Analysis 'Report (FSAR) or amendments-tt ereto.

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1 Section 8 - Sample Locations

. rovide a rap o, the Radioloaical

".rviron",,ental llonitoring.'a-pie Locations indicating the numbered sanpling locations oiven in Table 3.12-1.

Further clarification on th se nu-.,bered sampling locations can be provided 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.

DISTRIBUTION OF LETTER TO OL APPLICANTS Distribution to be com leted b

Secretaries:

"k' W~

NRC PDR Local PDR 0.

D. Parr LPM M. Rushbrook LWR g3 File

Attorney, OELD M. Service Distribution to be com leted b

M. Service:

Central Files - Form Letter File R.

Boyd D.

Ross D. Vassa'llo M. Williams R. DeYoung R. Vollmer J. Collins ISE BCC:

ACRS '16 )

NSIC TIC

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