ML16341C863
| ML16341C863 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/03/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Morrissey J PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7901100076 | |
| Download: ML16341C863 (16) | |
Text
JAN Docket Nos. 50-275~
and 50-323 Hr. John C. Morrissey Vice President 8 General Counsel Pacific Gas 5 Electric Company'7 Beale Street San Francisco, California 94106
Dear Nr. Norrissey:
istribution Docket Fi e
-NRC -PDR Local PDR "979R.
S.
Boyd D.
B. Vassa1lo F. J. Milliams J
~ Stolz D. Allison E. Hylton R. J. Nattson J.
P. Knight
'S.
Hanauer R.
Tedesco R.
DeYoung V. A. Moore R.
H. Vollmer H. L. Ernst R.
P.
Denise ELD
-IE -(3.)
V. Stello B. Grimes bcc:
J.
R. Buchanan, NSIC T.
SUBJECT:
CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (Diablo Canyon )nuclear Poorer Plant, Units 1 and 2)
The Radiological Effluent Technical Specifications for PWR and BMR facilities issued in Novzmber1978, require you to provide an Offsite Dose Calculation ttanual (ODQ<) 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 ODCN.
The format for the ODCfh is left to your discretion.
Sincerely, P1 lginnl Signed by, JOhn I". Stqh'I John F. Stolz, Chief Light Mater Reactors Branch No.
1 Division of Project Management
Enclosure:
General Contents of the ODCN cc:
See pago 2 OPPICK~
SURNAMCW LMR JStol r
1/Q/79 wozxo NRC FORM 518 (9-7G) NRCM 0240 4 UI 8, OOVERNMR~ PRINTINCI OPPICEI IOT6 02~24
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Mr. John C. Morrissey aA~
cc:
Mr. John'arrs Managing Editor San Luis Obispo County Telegram - Tribune 1321 Johnson Avenue P. 0. Box 112 San Luis Obispo, California 93406 Philip A. Crane, Jr., Esq.
Pacific Gas 8 Electric Company 77 Beale Street San Francisco, California 94106 Janice E. Kerr, Esq.
California Public Utilities Coranission 350 McAllister Street San Francisco, California 94102 Mr. Frederick Eissler, President Scenic Shoreline Preservation Conference, Inc.
4623 More Mesa Drive Santa Barbara, California 93105 Hs. Elizabeth E. Apfelberg 1415 Cazadero San Luis Obispo, California 93401 Hs. Sandra A. Sil ver 1792 Conejo Avenue San Luis Obispo, California 93401 Mr. Gordon A. Silver 1792 Conejo Avenue San Luis Obispo, California 93401 Paul C. Valentine, Esq.
321 Lytton Avenue Palo Alto, 'California 94302 Yale I. Jones, Esq.
,19th Floor 100 Van Ness Avenue San Francisco, California 94102 Alan S. Rosenthal, Esq.
Atomic Safety 8 Licensing Appeal Board U. S. Nuclear Regulatory Coranission Washington, D. C.
20555 Elizabeth S. Bowers, Esq.,
Chairman Atomic Safety
& Li'censing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Hr. Glenn 0. Bright Atomic Safety
& Licens i ng Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Tolbert Young P. 0. Box 219 Avila Beach, California 93424 Richard S. Salzman, Esq.,
Chairman Atomic Safety 8 Licensing Appeal Board U. S. Nuclear. Regulatory Coranission Washington, D. C.
20555 Dr.
W. Reed Johnson Atomic Safety 8 Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Hr. Richard Hubbard HHB Technical Associates 366 California Avenue P al o Alto, C al iforni a 94306
Mr. John C. Morrissey cc:
Ms. Raye Fleming 1746 Chorro Street San Luis Obispo, California 93401 Brent Rushforth, Esq.
Center for Law in the Public Interest 10203 Santa Monica Boulevard Los Angeles, California 90067 Arthur C. Gehr, Esq.
Snell 8 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Mr. James
- 0. Schuyler, Project Engineer Pacific Gas 8 Electric Company 77 Beale Street San Francisco, California 94106 Bruce Norton, Esq.
3216 North 3rd Street Suite 202
- Phoenix, Arizona 85012 Mr. W. C. Gangloff, Westinghouse Electric Corporation P. 0.
Box 355 Pittsburgh, Pennsylvania 15230 Michael R. Klein, Esq.
Wilmer, Cutler 8 Pickering 1666 K Street, N.
W.
Washington, 0. C.
20006 David F. Fleischaker, Esq.
1025 15th Street, N.
W.
5th Floo'r Washington, D. C.
20005 Dr. William E. Hartin Senior Ecologist Battelle Memorial Institute
- Columbus, Ohio 43201
I
ENCLOSURE, GENERAL CONTENTS OF THE ODCt1*
Section 1 - Set Points Providq ghee, equations and methodology to be used at tne station,or ygj4 for each alarm an'd trip set point on each effluent release 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 eauipment and measurement method used during release, the site related parameters and the set points 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 - Li uid Effluent 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. l.l.
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.
I
continuous and/or batch releases the assumptions used for manual and auto-matic 4q~ipation. of releases should be provided.
For hatch re)capes, tIle calculational
- methods, equations and assumptions
- used, together 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 Pate Provide the equations 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 impact limitation.
Provide the equa-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/(} and D/(}), the site specific parameters and release point elevations.
Other
- features, such as surveillance requi rements',
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
4) measured and used, the receptor location by direction and distance, and the method of estimating and updating cumulative doses due to liquid,releases.
The dose factors, pathway transfer factors, pathway usage factors, and dilution factors for th points of pathway origin, etc.,
should be given, as well,as receptor age group, water and food consumption rate and other factors assumed or measured.
Provide the method of determining the dilu-tion factor at the discharoe during any liquid effluent release and any site specific parameters used in these determinations.
Also, provide the criteria for determininq -short and long term releases.
OtIier 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 qaseous 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 t
as'receptor age group, crop yield, grazing time and other factors assumed or measured.
Provide the method of determining dispersion values (X/0 and D/0) for short-term and long-term releases and any site specific parameters
4
and release point elevations used in these determinations.
Other features such as surveillance reaui rements, sampling and analysis program, detection limitations and representative samplino 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 Equipment 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.l 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 provided in Chapter 11 of the Final Safety Analysis Report (FSAR) or amendments thereto.
Section 8 - Sam le Locations Provide a map of the Radiological Envirorxnental Monitoring Sample Locations indicating the numbered sampling locations given in Table 3.12-1.
Further clarification on these numbered sampling locations can be provided by a list, indicatino the dir ection and distance from the center of the building complex of the unit or station, and may include a discriptive na~e for identification purooses.