ML19282B140
| ML19282B140 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/12/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 7903090092 | |
| Download: ML19282B140 (2) | |
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- E UNITED STATES 9'
NUCLEAR REGULATORY COMMisslON
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WASHING TON. D. C. 20555 3
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FEB 121979 Docket tio:
50-368 Mr. Williara Cavanaugh, III Executive Director of Generation
& Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
SUBJECT:
C0ilTEtlTS OF THE OFFSITE DOSE CALCULATION f%'lVAL - ARKANSAS tlVCLEAR 1, UtlIT 2 The Radiological Effluent Technical Specifications for PWR and BWR facilities issued in flovember 1978, require you to provide an Offsite Dose Calculation Manual (ODCM) with your proposed Technical Specifi-caticns 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 ODCM is
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left to your discretion.
Sincerely,
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n F. Stolz, Chief
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Light Water Reactors Branch flo. 1 Divisicn of Project Management
Enclosure:
General Contents of the ODCM cc:
See next page O
790309069A
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Mr. William Cavanaugh, III FEB 121979 cc:
Mr. Daniel H. Williams Manager, Licensing Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Philip K. Lyon, Esq.
House, Holmes & Jeweli 1550 Tower Building Little Rock, Arkansas 72201 Mr. E. H. Smith, Project Engineer Bechtel Power Corporation San Francisco, California 94119 Mr. Fred Sernatinger, Project Manager Combustion-Engineering, Inc.
1000 Prospect Hill Road Windsor, Connecticut 06095 Mr. Charles B. Brinkman,~ Manager Washington Nuclear'0perations C-E Power Systems Combustion Engineering, Inc.
4853 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014 Mr. James F. O'Hanlon General Manager - Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801
GEf:ERAL C0lGE!:T5 0F THE 03 i?
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Section 1 - Set Points Provide the ecuations ano rethoddlocy to be used at the sta ticn cr unit i
for each alarm and tric set point on each ef fluent release poir.t 6ccordi g to the Speci fications 3.3.3.8 and 3.3.3.9.
Provide the alarn and control location, the monitor description, location, power source, scale, range and identification number, and the ef fluent isolation control device, its location, po..er 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 ooi.st, 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 use'd during release, the site related parameters and the set coints used to assure that the Specification is met at each release point, in-ciuding any administrative controls applicable at the station or unit.
The fixed and predetermined set points 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 - Liouid Ef fluent Concentration Provide 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 tne ODCM is lef t up to the licensee and nay be s;npli fied by tables and grid printout.
Each page should be numbered and indicate the facili ty approval and ef fective date.
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2 continuous and/or bitch rcleases, the assunctions used for r.anual and auto-catic ten.ination of releases s' ould be provided.
For batch reluses, the r
calculational rethods, ecuations and assumptions used, together with the pre-release and post-release analyses should be provided.
Other features, such as surveillance requirenents, sanpling and analysis program, detection limitations and representative sampling should b.e 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 contribution to the dose inpact limitation.
Provide the coua-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 D/Q), the site specific parameters and release point elevations.
Other features, such as surveillance requirements, sampling and analysis program, detection limitations and re'presentative sampling should be addressed.
Section 4 - Liquid Effluent Dose
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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-fica tions 3.11.1.2.
The section should describe how the dose contributions lare to be calculated for the.various pathways and release poikts, the equations and assumptions.to be used, the site specific parameters to be
neasured and used, the receptor '.ncation by direction a d cistance, and the nethod of estinating and updatina cumulative doses due to liouid relea?.s.
The dose factors, pathway transfer factors, rathstay usape factors, and dilution factors for the points of pathway oricin, etc., should be aiven, as well as receptor age group, water and food consumption rate ano other factors assumed or neasured.
Provide the method of determining the dilu-tion factor at the discharce durinc any liouid effluent release and any site specific paraneters 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 Ef fluent Dcse 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 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 estinating and updating cumulative doses due to gaseous releases.
the location direction and distance to the nearest residence, ccw, scat, meat animal, garden, etc., should 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/O and D/Q) for short-term and long-term releases and any site specific parameters
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4-and release point elevations used in these aeterninations.
Also, previce the criteria for determining short and long tir7. rel ea se s.
0;n.e r f66turis such as surveillance reouir'ements, sa."clino and analysis nrogram, detec tion limitations and representative sarpling should be addressed.
Section 6 - Projected Doses For liquid and gasecus radwaste treatment systems, provice the method of projectino deses due to effluent releases for the normal and alternate cath-ways of treatment according to the specifications, describing the cc.mponents and' subsystems to be used.
Section 7 - Ooerability of Eouiorgnt Provide a flow diagram (s) defining the treatment paths and the ccmponents of the radioactive liquid, gaseous and solid waste management systems that are to b.e 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 ficw 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 af ter January 2,1971, the fl ow diagran(s) shall be consistent with the information provided in Chapter 11 of the Final Sa fety Analysis Report (FSAR) or amendcents thereto.
5 Section 8 - Sam:le Locations 5
Frovide a rae of the Radielepical Er.viror.nental ;' r.itcring.arole Le:atians indicating the nunbered sarpling locations given in Table 3.12-1.
Furtner clarification on tnese nur.bsrsc sar.pling locations can t e prcvidec e,s a
list, indicating the direction and distance from the center of the builoing complex of the unit or station, and may include a discriotive r.a.,e for identification curposes.
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