ML18078A882

From kanterella
Jump to navigation Jump to search
Forwards NRC Recommendations for General Contents of Offsite Dose Calculation Manual
ML18078A882
Person / Time
Site: Salem 
Issue date: 02/14/1979
From: Parr O
Office of Nuclear Reactor Regulation
To: Mittl R
Public Service Enterprise Group
References
NUDOCS 7902280233
Download: ML18078A882 (8)


Text

FEB 14 1979 Docket No. 50-3 U *

. Mr.-.R~ L. 'Mittl, General r;1anager

. Licensing and Environment Engineering and Construction Department Public Service Electric arid Gas Company 80 Park Pl ace Newark, New Jersey*' 07101

Dear Mr. Mittl:

  • suB.JECT:. CONTENTS OF THE OFFSITE DOSE. CALCULATION MANUAL *
  • (Salem Nu~1ea*r Generating Station_, Unit 2}

The Radiological Effluent Technical* Speciffcations for PWR and B~JR *

  • *facil i:ties issued in November 1978,. require you to provide an Off site

. D_ose Calculation Manual (ODCM) with_your proposed Technical *spe_dfi-cations implefnenting 10 CFR 50.36a and other Federal Regulattons.

  • The enclosure to this letter* describes the staff's recommendations*

for the genera 1 contents of the ODCM.

The format fat~ the ODCM is left to your discretion.

Enclosure:

Geheral Contents of*

the ODCM cc w/ enclosure:

,See next page

'i 9 0 2 2 8 0 2 33

. Si.ncerely,

  • Original Stgned by..
0. O. Parr
  • *olan D'.

Parr~ Chief

. Light l~ater Reactors Branch No.-. Division *of Project Management

  • Mr. R. L. Mittl, General Manager cc:

Richard Fryling, Jr., Esq.

Assistant General Counsel Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07100 Mark Wetterhahn, Esq.

(onner, Moore & Cober 1747 Pennsylvania Avenue, N.W.

Suite 1050 Was~ington, D.C.

. 20006 Mr. Leif J. Norrholm U. S. Nuclear Regulatory Commission Region I Drawer I Hancocks Bridge, New Jersey 08038 FEB 14 1979

GENERAL CONTENTS OF THE ODCM*

Section l - Set Points ProvidE the equations and ~ethod6lo9y to be used at the station or unit for each alarm and trip set point on each effluent release point accordin9 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 1 ocation, power source and identification nu111ber.

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 releas~s are not in progress.

If dilution or dispersion is used, describe the on-site equipment and measure~ent

  • method used during release, the ~ite related parameters and the set points useq to assure that the Specification is met at each release point, in-eluding any administrative controls applicable at the station or unit.

The fixed and predetermined set points should ~onsider the radioactive effluent to have a radiopuclipe distribution represented by nonnal and anticipated operational occurrences *. Other features, such as surveil 1 ance req~irements and the calibration method, should be address~d.

Section 2 - Liguip Effluent Concentration Provide the equations and methodology to b~ used at the station or unit for each liquiq release point according tp the Specification 3.11.1.1.

For

  • The fonnat 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.

--*" continuous and/or batch rel eases, the assumptions used for r:ianual and auto-matic temination of releases shoulr'. be provided.

For batch relE:ases, the calculational methods, equations dnd assumptions used, to9ether 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 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 gaseoys release point according to Specification 3.11.2 *. 1.

Consider the various pathways, rel ease point elevations, site related parameters and radionuclide contribution to the dose i~pact limitation.

Provide the equa-tions and assumptions used, stipulating the pathway, receptor location and receptor age.

Provide the dose factors ~o be used for the identified radio-n~clides released.

Provide the annual average dispersion values (X/Q and D/Q), the site specific parameters ~nd release point elevation~;. Other features, such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 4 - Liquid Effluent Dose I

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

-1

~

. neasured ~nd used, the receDtor location by dfr&ction a~d distance, and the nethod of esti~ating and updatin9 cumulative doses due to liquirl releases.

The dose factors, pa th'r'1ay transfer factors, oa th\\'iay usa9e factors, and dilution factors for the points of pathway ori~in, etc., should be given, as \\'Jell as receptor age group, water and food consumption rate and other factors assumed or measured.

Provide the method of detenni ning the dil u-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 Effluent Dose Provide the equations and methodology to be used at the station or unit for e~ch gaseous release point according to the dose objectives given in Speci-fic~tions 3.11.2.2 and 3.11.2.3.

The section should describe how the dose contributions are tp be cal ~~lated for the various pathways and rel ea~e 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 group, crop yield, grazing time and other factors assumed or measured.

Provide the method of determining dispersion values (X/Q and DIQ) for short-term and 1 ong-term rel eases and any site specific parameters

\\

and release point elevations used in these determinations.

Also, provide the criterij for determining short and lon9 term releases.

Othe' features such as surveillance requirements, sa~pling and analysis progra~, detection limitations and representative sa~pling should be addressed.

Section 6 - Projected Doses For 1 i quid and gaseous radwa ste treatment sys terns, provide the method of proj ecti n~ doses due to effluent rel eases for the nonnal and al tern ate pa th-ways of treatment according to the speci fi cations, describing the components and subsystems to be used.

Section 7 - Operability of Equipment Provide a flow diagrarn(s) defining the treatment paths and the components of the radioactive liquiq, 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 infonnation provided in conformance with Section V.B.1 of Appendix I to 10 CFR Part 50.

For OL applications whose construction pennits were filed after January 2, 1971, the flow diagrarn(s) shall be consist~nt with the infonnation providf*d in Chapter 11 of the Final Safety Analysis 'Report (FSAR} or amendments ti ereto.

~--- *'"*""' S~ction 8 - Sample Locations Frovide a r.ao of the Radiolosiicc:l C:r.viromental t'ronitoring -~ar-ple Locations indicating the numbered sanpling locations given in Table 3.12-1.

Further clarification on these nu~bered sa~pling 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.

.... ~

j

. -_ -,-.c-. -,_ -

.DISTRIBUTION OF LETTER TO OL APPLICANTS Distribution to be complet~d by Secretaries:

Docket File( s}il{

NRC PDR Local PDR

0. D. Parr LPM M. Rushbrook LWR #3 File Attorney, OELD M. Service Distribution to be completed by M. Service:

Central Files - Fonn Letter File R. Boyd D. Ross D. Vassallo M. Willi ams R. DeYoung R. Vollmer J. Collins I&E BCC:

ACRS * (16)

NSIC TIC