ML19282B145

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Forwards Recommendations for General Content of Offsite Dose Calculation Manual (ODCM) Required W/Radiological Effluent Tech Specs for PWR & BWR Facilities
ML19282B145
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 02/13/1979
From: Stolz J
Office of Nuclear Reactor Regulation
To: Jens W
DETROIT EDISON CO.
References
NUDOCS 7903090106
Download: ML19282B145 (7)


Text

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NUCLEAR REGULATORY COMMISSION

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FEB 131379 Docket No:

50-341 Dr. Wayne H. Jens Assistant Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226

Dear Dr. Jens:

SUBJECT:

CO:iTEilTS OF THE OFFSITE DOSE CALCULATION MANUAL - ENRICO FERMI ATOMIC PCWER PLANT, UNIT 2 The Radiological Effluent Technical Specifications for PWR and BUR facilities issued in November 1978, require you to provide an Offsite Dose Calculation Manual (ODCM) 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 CDCM.

The format for the CDCM is left to your discretion.

Sincerely, C IA /

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John F. Stolz, Chief daht Water Reactors oranch No. 1 Division of Project Management

Enclosure:

General Contents of The ODCM cc:

See next page 730309 0/04

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Dr. Wayne H. Jens cc: Eugune B. Thomas, Jr., Esq.

Mrs. Martha Drake LeBoeuf, Lamb, Leiby & MacRae 23,0 Fairview 1757 N. Street, N.W.

Petoskey, Michigan 49770 Washington, D. C.

20036 Peter A. Marquardt, Esq.

Co-Counsel The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. William J. Fahrner Project Manager - Fermi 2 The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Larry E. Schuerman Licensing Engineer - Fermi 2 Detroit Edison Company 2000 Second Avenue Detroit Michigan 48226 Charles Bechhoefer, Esq., Chairman Atomic Safety & Licensing Ocard Panel U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. David R. Schink Department of Oceancgraphy Texas A & M University College Station, Texas 77840 Mr. Frederick J. Shcn Atomic Safety & Licensing Board Panel V. S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. David Hiller University of Michigan Law School Hutchins Hall Ann Arbor, Michigan 48109 Mr. Jeffrey A. Alson 772 Green Street, Building 4 Ypsilanti, Michigan 48197

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GENEP. AL CONTEl:TS CF InE DXi'.'

Section 1 - Set Fnints Provide the ecuations anc rethoddlocy to be used at the staticn cr ur.it for each alarm and trip set point nn each ef f1 pent release point accordi.g to the Speci fications 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 ef fluent isciation control device, its location, po..er source and identification number.

If the set point value is variable, provide the eciuation to be used to predeterm.ine the set ocint 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 coints used to assure that the Specification is met at each release point, in-cluding any administrative 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 - Liouid Effluent Concentration Provide the equaticns and methodoloay to be used at the station or unit for each liquid release point according to the Speci fication 3.11.1.1.

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The format for the OCCM is lef t up to the licensee and nay be simplified by tables and grid printout.

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

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. continuous and/or batch releases, the assunations used for nanval and autc-catic terr.ination of releases should be provided.

For batch rel(ases, the calculational rethods, equations and assumptions used, tocether with the pre-release ar.d post-release analyses should be crevided. Other features, 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 ecua tions and methocology 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 asswaptions 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 dispersic, values (X/0 and 0/Q), the site specific parameters and release pc.nt elevations.

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

Section 4 - Licuid 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 pa thways and release points, the equations and assumptions to be used, the site specific parameters to be

reasured and used, the receptor incation by direction a d oistance, and the nethod of estir.ating and updating cumulative doses cue to licuid releas:s.

The dose factors, pathway transfer factors, patbilay usage f actors, and dilution factors for the points of pathway oricin, etc., shoulc be given, as well as receptor age group, v.ater and food consumption rate ano other factors assumed or neasured.

Provide the nethod of determining tne dilu-tion factor at the discharge during any licuic effluent release and any site specific paraneters used in these deterninations.

Other features sucn as surveillance requirecents, sampling and analysis program, cetec tion limitations and representative sampling should be addressed.

Section 5 - Gaseous Ef fluent Dese 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 :ne dose contributions are to be calculated for the various pathways and release points, the equations and assurptions 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 lccation direction and distance to the r.earest residence, ccw, goat, meat animal, garden, etc., shoul d be given, a s 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 n

D/Q) for short-term and long-term releases and any si te speci fic parameters

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anc release point eleva tions used in these deterninations.

Al so, peceice the criteria for ceteraining short and lenc tira releases.

pteer fea ture s such as surveillance recuirements, sa."olino and analysis oregram, cetection limitations and representative sarpling should be adcressed.

Section 6 - Projected Doses For liouid and gaseous radwaste treatment systems, provide the method of projecting ~ deses due to ef fluent releases for the normal and alternate cath-ways of treatnent according to the speci'fications, describing the ccmponents and subsystens to be used.

Section 7 - Ooerability of Ecuice.qnt Provide a ficw diagram (s) defining the trea tment pa ths and the components of the radioactive liquid, gaseous and solid waste management systems that are to be maintained and used, pursuant to 10 ChR 50.36a, to meet Technical Specifications 3.11.1.3, 3.11.2.4 and 3.11.3.l.

Subcor.ponents of oackaged equipment can be identified ~ by a list.

For cperating reactors whose con-struction pennit applications were filed prior to January 2,1971, the flow diagram (s) shall be consistent with the information provided in conformance with Section Y.5.1 of Appendix 1 to '10 CFR Part 50.

Fce OL applications whose construction permits were filed af ter January 2,1971, the ficw diagram (s) shall be consistent with the infornation provided in Chapter 11 of the Final Sa fety Analysis Report (FSAR) er anendments thereto.

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-5 Section 8 - Sa.:le locations t

F rctide a r.ac of the Radiol ogic al Er.viror. mental I'sr.i tc ring Farpl e Lc:a ti ar.s indicating the nunbereri sarpling locations given in Table 3.12-1.

Furtner clarification on nese,:u..t.erec sampling iccations cen t e provicec ey a list, indicating the direction and distance frco the center of tr.e buticing ccmplex of the unit or station, and may include a discrictive r.ar.e for ider.ti fication corposes.

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