ML19282B138
| ML19282B138 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 02/12/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Borgman E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7903090088 | |
| Download: ML19282B138 (7) | |
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NUCLEAR REGULATORY COMM!sSION n
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WASHING TON. D. C. 20555
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FEB 121979 t
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50-358
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Mr. Earl A. Borgmann Vice President - Engineering Cincinnati Gas & Electric Company P. O. Box 960 Cincinnati, Ohio 45201
!ar Mr. Borgmann:
SUElECT:
CONTEtlTS OF THE OFFSITE DOSE CALCULATION ttatiUAL - WM. H. ZIMMER flVCLEAR PCWER STATION, UNIT 1 The Radiological Effluent Technical Specifications for PWR and BWR facilities issued in tiovember 1978, require you to provide an Offsite Dose Calculation Manual (CDCM) with your proposed Technical Specifica-tions implerrenting 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 left to your discretion.
Sincerely, b
Jo/ght Water Reactors Branch No. 1 n F. Stolz, Chief Division of Project Management
Enclosure:
General Contents of the CDCM cc:
See next page 79030Soogg
- 37 -
Mr. Earl A. Borgmann FEB 121979 cc:
Troy B. Conner, Jr., Esq.
David B. Fankhauser, PhD Conner, Moore & Corber 3569 Nine Mile Road 1747 Pennsylvania Avenue, N. W.
Cincinnati, Ohio 45230 Washington, D. C.
20006 Thomas A. Luebbers, Esq.
Mr. William J. Moran Cincinnati City Solicitor General Counsel Room 215, City Hall The Cincinnati Gas and Electric Cincinnati, Ohio 45202 Company P. O. Box 960 Mr. Stephen Schumacher Cinnati, Ohio 45201 Miami Valley Power Project P. O. Box 252 Mr. William G. Porter, Jr.
Dayton Ohio 45401 Porter, Stanley, Arthur and Platt Ms. Augusta Prince, Chairperson 37 West Broad Street 601 Stanley Avenue Columbus, Ohio 43215 Cincinnati, Ohio 45226 Mr. Peter H. Forster, Vice President Charles Bechhoefer, Esq., Chairman Energy Resources Atomic Safety & Licensing Board The Dayton Power and Light Panel Company U. S. Nuclear Regulatory Commission P. O. Box 1247 Washington, D. C.
20555 Dayton, Ohio 45401 J. Robert Newlin, Counsel The Dayton Power and Light Company P. O. Box 1247 Dayton, Ohio 45401 Mr. James D. Flynn Manager, Licensing Environmental Affairs The Cincinnati Gas and Electric Company P. O. Box 960 Cincinnati, Ohio 45201 Mr. J. P. Fenstermaker Senior Vice President-Operations Columbus and Southern Ohio Electric Company 215 North Front Street Columbus, Ohio 43215
GENEP.AL C0b!EUTS OF THE 0];i?
Section 1 - Set Points Provide the euuations ano rethoddiopy to be used at the sta ticn cr unit s
for each alarm and tric set point on each ef fluent release poir.t accordi.g to the Speci fications 3.3.3.8 and 3.3.3.9.
Prov:de the alarm and control location, the monitor description, location, oower source, scale, range and identification number, and the ef fluent isolation contrcl device, its location, po..er source and identification nu,ber, if the set point value is variable, provide the enuation to be used to predetermine the set ooint 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 ooints i
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 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 - Liquid 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.
For
'*The format for the ODCM is lef t up to the licensee and nay be sinplified by tables and grid printout.
Each page should be numbered and indicate the facility approval and effective date.
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2-Continuous and/or batch releases, the assunctions used for rangal ad auto-matic teer.ination of releases sFould be provide.
For batch rel: eses, the calculation 01 rethods, ecuations and assumptions used, tocether tcith the pre-release ar.d post-release analyses shoul d be provided.
Other features, such as surveillance requirenents, sampling and analysis program, detection limitations and representative sampling should be addressed.
Section 3 - Gaseous E f fluent Dose Rate Provide the ecuations 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 contribution to the dose inpact limitation.
Provide the ecua-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 paramaters and release point elevations.
Other features, such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.
Section 4 - Liquid 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-fica tions 3.11.1.2.
The section should describe how the dose contributions
'are to be calculated for;the various pathways and release poikts, the equations and assumptions to be used, the site specific parameters to be z
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4 reasured and used, the rcce.ntor location by direction a,d oi3thoce, and the nethod of estir.ating and updatino cumulative doses oue to liouid relea?:s The dose factors, pathway transfer factors, nathstay usape factcrs
, and dilution factors for the coints of pathway origin, etc., should be given as well as receptor age group, wa ter and food consumption rate and other factors assumed or neasured.
Provide the method of determining the dilu-tion factor at the discharoc during 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 Effluent 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 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 i
D/Q) for short-term and long-term releases and any site specific parameters O
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anc release point elevations used in these deterninations.
Al so, previce the criteria for deternining short and long tira releases.
0 ner fea turi s such as surveilTance recuirements, sarolino and analysis orogram, detection limitations and representative sarpling should be addressed.
Section 6 - Projected Doses For liquid and gaseous radwaste treatnent systems, provide the method of projectina doses due to effluent releases for the normal and al ternate cati ways of treatr.;ent according to the specifications, describing the ccmponents and subsystens to be used.
t Section 7 - Operability of Eouioment Provide a flow dianram(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 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 pennit 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 infornation provided in Chapter 11 of the Final Sa fety Analysis Report (FSAR) cr amendments thereto.
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5 Sec tior, 8 - Snt:le Loca tions Fro'. ide a rae of tre Radiolepical Enviror.nental 'tritcrin s
g Sarsle Lc:ations indicating the nunbered sarpling locations given in Table 3121 Further clarification on tnese nur.t.erec sa.pling locations can :e proviced list, inoicating the direction and distance from the center of the buil i o ng complex of the unit or station, and may include a discriptive na.me for ider.tification curposes O
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