ML20238C907
| ML20238C907 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/01/1976 |
| From: | TERA CORP. |
| To: | |
| Shared Package | |
| ML17325B791 | List: |
| References | |
| 10562, NUDOCS 8709100444 | |
| Download: ML20238C907 (262) | |
Text
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l k h Prepared for BALTIMORE GAS AND ELECTRIC COMPANY 10500 8709100444 B7090437 TERA CORPORATION PDR ADOCK 050 P
APPENDIX l EVALUATION REPORT CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 & 2 Prepared for BALTIMORE GAS AND ELECTRIC COMPANY Gas and Electric Building Baltimore, Maryland 21203 -.
.i By TERA CORPORATION Teknekron Energy Resource Analysts 2118 MILVIA STREET BERKELEY, CAllFORNIA 94704 -
415-848-1464 October 1,1976
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Table of Contents Section P_ age No. Title Executive Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . i 1.0 Introduction and Background Information. . . . . . . . . . . . . . . 1-1 1.1 Requirement for Appendix I Evaluations. . . . . . . . . . . . . 1-1 1.2 Objectives of the Report. . . . . . . . . . . . . . . . . . . 1-2 1.3 General Site Description. . . . . . . . . . . . . . . . . . . . 1-2 1.4 General Plant Description . . . . . . . . . . . . . . . . . . . 1-5 2.0 Design Description of Liquid and Gaseous Waste Handling Systems. . . 2-1 2.1 Radioactive Liquid Waste System . . . . . . . . . . . . . . . . 2-1 2.1.1 Des i g n Ba s e s . . . . . . . . . . . . . . . . . . . . . . 2- 1 2.1.2 Radioactive Liquid Waste System Description. . . . . . . 2-1 2.2 Radioactive Waste Gas Processing System . . . . . . . . . . . . 2-2 2.2.1 Design Bases . . . . . . . . . . . . . . . . . . . . . . 2-16 2.2.2 Waste Gas Processing System Description. . . . . . . . . 2-16 2.3 Plant Ventilation System. . . . . . . . . . . . . . . . . . . . 2-21 2.3.1 Design Bases . . . . . . . . . . . . . . . . . . . . . 2-21 l 2.3.2 Sys tem Descri ptions . . . . . . . . . . . . . . . . . . .2-21 3.0 Derivation of Plant Effluent Source Term . . . . . . . . . . . . . . 3-1 3.1 Introduction and Evaluation Bases . . . . . . . . . . . . . . . 3-1 3.2 Input Parameters for Source Term Calculation. . . . . . . . . . 3-1 3.2.1 P ri ma ry Sys tem Pa rame te rs . . . . . . . . . . . . . . . . 3- 1 3.2.2 Secondary System Parameters. . . . . . . . . . . . . . . 3-1 3.2.3 Liquid Radwas te Parameters . . . . . . . . . . . . . . . 3-9 3.2.4 Gaseous Radwaste Parameters. . . . . . . . . . . . . . . 3-9 3.2.5 Ven tila tion Parameters . . . . . . . . . . . . . . . . . 3-9
- 3. 3 Description of Calculational Model. . . . . . . . . . . . . . . 3-9 3.4 Eval uation of Res ul ts . . . . . . . . . . . . . . . . . . . . . 3-14 3.4.1 Liquid Effluent Releases . . . . . . . . . . . . . . . 3-14 3.4.2 Gaseous Effluent Releases. . . . . . . . . . . . . . . 3-14 3.4.3 Adjustment for Operational Occurrences . . . . . . . . . 3-17 TERA CORPORATION
Fl, Section Title e Pyg_e,J{o,.. 4.0 Calculation of Maximum Individual Doses. . . . . . . . . . . . . . . 4-1 4.1 Introduction and Evaluation Bases . . . . . . . . . . . . . . . 4-1 4.2 Impact Assumptions / Parameters . . . . . . . . . . . . . . . . . 4-2 , 4.2.1 Effimnt Helease Points. . . . . . . . . . . . . . . . . 4-2 , 4.2.2 Meterolog ical Models/ Parameters. . . . . . . . . . . . . 4-12 4.2.3 Hydrological 1' Parameters (Dilution) . . . . . . . . . . 4-12 m 4.2.4 Location of Maximum Individual Receptcrs . . . . . . . . 4-12 4.2.5 Usage and Bioaccumulation Factors. . . . . . . . . . . 4-12 3 4.2.6 Dose Factors, Stable Element Transfer Data . . . . . . . 4-13 i 4.3 Description of Calculational Models . . . . . . . . . . . . . . 4-13 s 5.0 Evaluation of Plant Radiological Impact - Conclusions. . . . . . . .5-1 5.1 Calculated Plant Radioactive Effluent Releases. . . . . . . . . 5-1 5.2 Calculated Plant Radiological Impact on Maximum Exposed individuals . . . . . . . . . . . ..........5-1 5.2.1 Dozes Resulting from Radioactive Liquid a Ef fl uent Releases. . . . . . . . . . . . . . . . . . . . 5-1 5.2.2 Doses Resulting from Radioactive Gaseous Ef fl uent Releas es . . . . . . . . . . . . , . . . . . . . 5-1 _ 5.3 Evaluation of Calculated Doses. . . . . . . . . . . . . . . . . 5-7 , 6.0 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 ' Appendix A - Responses to NRC Letters Dated February 19, and 25,1976 Regarding Compliance With Requirements of 10CFR50, Appendix I . . . . . . . . . . . . . . . . . . . . . . . . . .A-1 Responses to Enclosure 1 . . . . . . . . . . . . . . . . . . . , , .A-2 Responses to Enclos ure 2 . . . . . . . . . . . . . . . . . . . . . . . A-5 Appendix B - Wind Speed, Direction, and Stability Frequency Tables - '. Calendar Year 1975. . . . . . . . . . . . . . . . . . . . . . .g_1 s
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s LIST OF TABLES _ Table {jtle Page No. A Comparison of Appendix J.' (M'ay 5,1975) and The Staff's iv Proposed Appendir I (RM 50-2, February 1974) to Cal-culated " Maximum Individual" Doses 1.2-1 Annual Design Objectives J b l-3 2.1-1 Reactor Coolant Waste Processing System Sources and Volumes 2-3 I 2.1-2 Miscellaneous Waste Processing System Sources and Volumes 2-4 2.1-3 Liquid Waste Processir.g System G mponent Description 2-5 2.2-1 Waste Gas Processing System Sources and Volumes 2-17 2.2-2 Waste Ga Processing System Component Description 2-18 2.3-1 Plant Vene.ilation System Dest.'gn Conditions 2-22 3.2-1 Input Data - PWR Isotopic Effluent $ource Term 3-2 3.4-1 Calvert Cliffs. - Liquid Effluent Releases 3-15 3.4-2 Calvert Cliffs - Gaseous Effluent Releases 3-16 4.2-1 Input Parameters and Assumptions: ALARA " Maximum 4-3 Individual" Liquid Dose Calculation 4.2-2 Input Parameters and Assumptions: ALARA " Maximum 4-5 Individual" Gaseous Dose Calculation 4.2-3 Special Location Data for Ground Level Release Maximum 4-9 Receptors 6 2-1 Maximum Individual (ALARA) Doses 5-2 5.2-2 Dose to Nearest Aeshbnt from Calvert Cliffs Gaseous 5-4 Effluent Releases 5.2 3 Dose from Gaseous Effluents to Individual at Location 5-5 of Nearest Garden 5.2-4 Dose from Grscous Effluents,at Location of Nearest 5-6 Milk Cow / Meat Animal TERA CORPORATION __ _ _ ___.- -_ - ---_.-._._.-- _ 2. - _ - - . _ . - --
LIST OF TABLES (continued) 5.3-1 Comparison of Appendix I (May 5,1975) and The Staff's 5.8 Proposed Appendix I (RM 50-2, February 1974) to Cal-culated " Maximum Individual" Doses A-1 Effluent Source Terms A-11 l A-2 Actual Site Boundary Nearest Distance Within 5 Miles A-15 l l A-3 Identification by Sectors of Residences Within 3 Miles A-17 of Calvert Cliffs Nuclear Units 1 & 2 A-4 Identification by Sectors of Vegetable Gardens 500 ft2 A-18 or Larger Within 3 Miles of Calvert Cliffs Nuclear Units 1 & 2 l l A-5 Location of Points of Interest Within 3 Miles, Distances A-19 of Vegetable Gardens Miles / Kilometers A-6 Plant Characteristics A-21 A-7 Elevated Releases X/Q, D/Q, and Fumigation Factors A-22 A-8 Elevated Releases X/Q, D/Q, and Fumigation Factors A-23 A-9 X/Q, D/Q, and Open Terrain Factors Ground Level A-24 Ground Level Releases Wake Term Included A-10 X/Q, D/Q, and Open Terrain Factors A-24 Ground Level Releases Wake Term Included A-11 Elevated Releases Relative Concentration A-26 Residences Within 3 Miles A-12 Elevated Releases Deposition Values A-27 Residences Within 3 Miles A-13 Elevated Releases Fumigation Adjustment Factors A-28 Residences Within 3 Miles A-14 Elevated Releases Vegetable Gardens Within 3 Miles A-29 A-15 Elevated Releases Vegetable Gardens Within 3 Miles A-30 A-16 Sea and Land Breeze Influences A-40 A-17 Eliminated Days from Possible Fumigation A-44 TERA CORPORATION
LIST CF FIGJRES
, Figure Title Page No.
2.1 -1 Hping and Instrument Diagram, Reactor geolanL Waste 2-10 Processing System Units No. i & No. 2
^ 1-2
. Piping and In nrument Diagram, Waste Gas and Miscella.- 2-13 neous Waste Processing Systems Units No. 1 & No.~2 2.3-1 Piping and Instrurient Diagram, Containment, Turbine, 2-23 Control Room, and Penetration Room Ventilation Systems u
2.3-2 Piping and Instrument Diagraa, Auxiliary Building 2-25 Ventilation System ! 3.2-1 Decontamination Factors for Shim Bleed and Equipment 3-10 l Drains l 3.2-2 Decontamination Factors for Miscellaneous (Dirty) Wastes 3-11 2 3.2-3 Decontamination Factors for Steam Generator Blowdown 3-12 A-1 Maximum Topographic Elevation Versus Distance from. A-51 l Plant Center (By 221/.? Sector) - SE l A-? Maximum. Topographic Elevation Versus Distance froo A-52 Plant Centi.* (By 221/2" Sector) SSE 4 A-3 Maximum Topographic Elevation Versus Distance from A- 53 Plant Center (By 22 1/2 Sectori - South A-4 Maximun er pographic Elevation Versus Distance from A-54 i l Plant Cer.tw (By 221/2 Sector) - SSW l A-5 Maximum Tcpcgraphic Elt.vation Versus Distance from A-55 Plant Center (By 221/2' %ctor) - SW A-6 Maximum Topographic Elevation Versus Distance from A-56 Plant Center (Bv 221/2 Sector) - WSW A/ Maximum Topographic Elevation Versus Distance from A-57 Plant Centar (By 22 1/2 Sector) - West , A-8 Maximum Topographic Elevation VerJus Distance from A-58 Plant Center (By 22 1/2 Sect.or) FNW A-9 Maximum To;:ographic Elevation Versus Distance from A-59 Plant Center (Gy 22 1/2 Sector) NW TERACORPORATION
EXECUTIVE
SUMMARY
i On June 17, 1975, the NRC transmitted to Baltimore Gas & Electric Company (BG&E) the general require:nents for a demonstration of compliance with 10CFR50, Appendix I for the Calvert Cliffs Nuclear Power Plant (construction permit application filed prior to January 2,1971) which specified submission of the following within twelve months of June 4, 1975:
- 1. Such information as is necessary to evaluate the means employed for keeping radioactivity in effluents to unrestricted areas as low as practicable, including all such information as is required by 10CFR50.34a (b) and (c) not already contained in the application, ,
l and
- 2. Plans and proposed technical specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during normal reactor operations, including expected operational occurrences, as low as practicable.
Specific guidelines for the submission of information in accordance with the requirements of 10CFR50, Appendix I were developed by the NRC staff and trans-mitted to BG&E by letters dated February 19, and 25,1976. These letters each contained two enclosures, the first referencing proposed Regulatory i Guides which define Appendix I evaluation methods acceptable to the staff, 1 the second defining information requirements necessary for f acility evaluation. The following report is an evaluation of the Calvert Cliffs facility, Units 1 and 2, with respect to the requirements of 10CFR50, Appendix I, which contains the detailed information requirements, evaluation methods and results necessary to respond to the NRC letters indicated above, and to demonstrate compliance with the intent of Appendix I. The objectives of this report are:
- 1. To demonstrate, via conservatively calculated plant effluent source terms and " maximum individual" doses, that the Calvert Cliffs Nuclear Power Plant complies with the intent of the design objectives specified by the NRC staff in Docket RM 50-2, as annexed to Appendix I via the September 1975 amendment. !
- 2. To provide the detailed information requirements and/or appropriate l Final Safety Analysis Report (FSAR) and Environmental Report (ER) I references such that the data requirements of Appendix I and the NRC j letters of June 17, 1975 and February 19, and 25,1976 are satisfied. j
- 3. To provide a detailed description of the analytical models used in the evaluation or references to appropriate documents such that the '
evaluation method is well defined and readily understandable. TERA CORPORATION
I Section 2.0 of the report describes the original design bases for the liquid and gaseous waste handling systems. The specific numbers and mode of opera-tion presented are extremely conservative design parameters which do not reflect actual or anticipated experience at C41 vert Cliffs and do not reflect the Appendix I evaluation assumptions of following sections. However, it is i necessary to establish the original bases for design and operation in order to ; effectively evaluate current system performance, operating characteristics, ) and radiological effluent impact. ; I Section 3.0 of the report describes the derivation of the plant effluent ! source term. Station radioactive liquid and gaseous effluent source terms i for Appendix I evaluation were derived, whenever possible, on the basis of l actual plant operational performance and pt acedures. Operating experience 1' was used to determine the expected operational modes, and their effects on overall plart performance parameters such as system flow rates, quantities of waste processed, and holdup times. Where experience was considered insufficient to represent the expected mode of operation or performance parameter, assumptions were made con-sistent with those recommended in appropriate Regulatory Guides. The objective of the source term calculation was to develop a conservative measure of the actual performance of the plant and an appropriate adjust-ment factor to account for anticipated 'perational occurrences. Section 4.0 of the report describes the calculation of annual " maximum individual" doses. These " maximum individual" doses were determined for a variety of liquid and gaseous effluent exposure pathways representative { of actual or potential usage conditions within a five mile radius of the l Calvert Cliffs Plant. The objective of these calculations was to demon-strate compliance with the design objective dose values of the NRC staff's 4 proposed Appendix I given in Docket RM 50-2 (as appended to Appendix I via i the September 1975 amendment). l;
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1 l Whenever possible, calculations were based on existing data for the ' l Calvert Cliffs Plant and its regional environmental characteristics. Where insufficient data existed to substantiate plant / site dependent assumptions, parameters and models reconnended in appropriate Regulatory 4 Guides were used. Gaseous effluent releases were evaluated for the plume shine, ground shine, vegetable, meat, cow milk, and inhalation pathways for adult, teenager, i child and infant receptors. The locations at which these receptors were I evaluated resulted in the maximum possible exposure. Liquid effluent releases were also evaluated at selected locations, and included doses resulting from fish consumption, shoreline activities, swimming, and boating. Doses at each receptor point were calculated for the same individuals and ; organs as for gaseous effluents. ii TERA CORPORATION
Table A summarizes the annual design objectives of 10CFR50, Appendix I, and the NRC staff's proposed Appendix I (Docket RM 50-2, February 1974) and compares these values to calculated values from Tables 3. 4 -1, 3. 4-2, 5.2-1, 5.2-2, 5.2-3 and 5.2-4. The following important items should be noted:
- 1. The calculated liquid effluent and gaseous iodine source terms are well below allowable limits according to Docket RM 50-2.
This source term was developed using the methods and assumptions of Regulatory Guide 1.112 and NUREG 0017 including the 0.15 Ci/yr/ unit adjustment factor. As such, it is considered to be a con-servative representation of the operation of the Calvert Cliffs Plant.
- 2. The calculated doses resulting from liquid effluents at the Calvert Cliffs site are well below the annual design objective values of Docket RM 50-2 (and Appendix I). These doses have been calculated by methods consistent with Regulatory Guide assumptions, and as such are evaluated to be conservative, considering the liquid radwaste system design and plant operating philosophy at Calvert Cliffs.
- 3. Gaseous effluent releases from the plant result in calculated doses well below the annual dose objectives of Docket RM 50-2 (
(and Appendix I). Since these doses were evaluated using the j methods and assumptions of Regulatory Guides 1.109 and 1.111, for both elevated and ground level release models, they are ; considered tc be conservative representations of the radiological l impact of the plant on its environment. j l I 1 iii TERA CORPORATION s _ _ . _ _ _ _ _ _ _
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1.0 INTRODUCTION AND BACKGROUND
INFORMATION 1.1 REQUIREMENT FOR APPENDIX I EVALUATIONS _ Amendments to Title 10, Chapter I, Code of Federal Regulations, Part 50, concerning Appendix I, which sets forth the Nuclear Regulatory Commission's (NRC) decision regarding numerical guides for design objectives and limitino I conditions for operation to meet the criterion "as low as reasonably achievable" { for radioactive materials in light-water-cooled nuclear p~ ower reactors, were published by the Commission on May 5, 1975, (40 FR 19439) and became effec- ' tive on June 4, 1975. On June 17, 1975, the NRC transmitted to Baltimore Gas & Electric Company (BG&E) the general requirements for a demonstration of compliance with
- 10CFRED Appendix I for the Calvert Cliffs Nuclear Power Plant (construction I permit application filed prior to January 2,1971) which specified submission l of the following within twe.ve (12) months of June 4,1975
- 1. Such information as is necessary to evaluate the means employed for keeping radioactivity in effluents to unrestricted areas as low as practicable, including all such information, as is required by 10CFR50.34a (b) and (c) not already contained in the application; and
- 2. Plans and proposed technical specifications developed for the pur-pose of keeping releases of radioactive materials to unrestricted areas during normal reactor operations, including expected opera-tionai occurrences, as low as practicable.
Specific guidelines for the submission of information in accordance with the requirements of 10CFR50, Appendix I were developed by the NRC staff and j transmitted to BG&E by letters dated February 19, and 25,1976. These letters each contained two enclosures, the first referencing proposed Regulatory Guides which define Appendix I evaluation methods acceptable to the staff, ; the second defining information requirements necessary for facility evaluation. j The following report is an evaluation of the Calvert Cliffs facility, Units 1 and 2, with respect to the requirements of 10CFR50, Appendix I, which contains the detailed information requirements, evaluation methods and results necessary to respond to the NRC letters indicated above, and to demonstrate compliance with the intent of Appendix I. i TERA CORPORATION
1.2 OBJECTIVES OF THE REPORT The objectives of this report are:
- 1. To demonstrate, via conservatively calculated plant effluent source terms and " maximum individual" doses, that the Calvert Cliffs Nuclear Power Plant complies with the intent of the design objectives speci-fied by the NRC staff in Docket RM 50-2, as annexed to Appendix I via the September 1975 amendment.
- 2. To provide the detailed information requirements and/or appropriate Final Safety Analysis Report (FSAR) aild Environmental Report (ER) references such that the data requirements of Appendix 1 and the NRC l letters of June 17, 1975 and February 19,ard 25,1976 are satisfied. I
- 3. To provide a detailed description of the analytical models used in the evaluation or references to appropriate documents such that l the evaluation method is well defined and readily understandable. l The summarized annual design objectives of Docket RM 50-2 and Appendix I .
l are presented in the following Table 1.2-1. 1.3 GENERAL SITE DESCRIPTION U)(2)
- The Calvert Cliffs Nuclear Power Plant is located in an excavated section of the Calvert Cliffs in Calvert County, Maryland, on the western shore of the Chesapeake Bay. It is approximately halfway between the mouth of the Bay and its headwaters at the Susquehanna River. l The rolling land areas on and adjacent to the site are forested primarily ,
with deciduous trees and an understory of various grasses, herbs, and shrubs. j Lesser amounts of the land are under cultivation with tobacco and some hay and corn. The site varies in elevation from sea level to about 137 feet with an average elevation of 100 feet. The Bay frontage and several of the small interior streams are characterized by near-perpendicular walls caused by water, wind, and frost action. The ll35-acre plant site is located 10.5 miles southeast of Prince Frederick, Maryland, and 4.5 miles northwest of Cove Point, Maryland. State Highway No. 2 passes adjacent to the site on the west. The plant and associated facilities occupy 75 to 100 acres abutting Chesapeake Bay near the center of the site's 10,000 foot-shoreline. The landward site boundary ranges from 3773 feet in the west-northwest sector to 5433 feet in the west sector. The region in the vicinity of the plant site is primarily rural with a number of small comunities located within a 10-mile radius. Beyond this distance, the population density to the north and northwest continually increases up to a radius of 50 miles which encircles most of the Washington, D.C. metropolitan area; Baltimore is 60 miles to the north.
*All references are listed by number in Section 6.0, " References".
1-2 TERA CORPORATION
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The plant site and its environs are presently devoted to agriculture and forest uses. The major crops are tobacco, corn, and bey. The amount of land devoted to agriculture in the surrounding area is declining, although farming will continue to be a primary land use over the anticipated life of the plant. There are no dairy farms in Calvert County at present. The total 1970 population, including seasonal residents, within 10 miles of the site was estimated to be 16,827. The population is distributed throughout the area and includes many small communities with population less than 1,000. The County Seat, Prince Frederick, is located 101/2 miles northwest of the site and has a total population of about 605. A new community, known as Chesapeake Ranch Estates, is located six miles ' south-southeast of the site. The present (1970) permanent population of this development is approximately 180. In the summer, the population 1s approximately 1,000 during the week, and reaches a maximum cf approximately 2,000 on weekends. Population projections show an increasing population with the largest increases occurring nearer Washington, D.C. However, the area is expected to remain essentially rural. Accompanying the population increase will be an increase in land devoted to residential and commercial use. The climate of the region is marked by generally mild winters and summers. Average daily maximum and minimum air temperatures are about 88 F and 67 F in July, and about 45 F and 28 F in January. The record high tempera-tures for Washington and Baltimore are 101 F and 107 F, respectively. The record lows have been 11 F and 9 F respectively, at the same stations. On the average, the precipitation is uniformly distributed over the year. Local climatological records show winter months have the lowest average precipitation (slightly less than 3 inches), and the highest monthly average occurs in the early fall (around 5 inches). The average annual total is between 40 and 45 inches. Rainfall during the summer occurs mainly in the form of thunderstorms. The average seasonal snowfall is about l 20 inches. Accumulations of more than 10 inches are quite rare and melt off is normally rapid. Violent weather may occur in this region from a number of sources. Thunder-storms have been accompanied by gusts of up to 100 mph and heavy hail on other occasions. About 40 thunderstorms per year may be expected, although the average intensity will be considerably less than these extremes. The effect of hurricanes can be expected to be felt at the present site in the form of high winds, rainfall, and high tides. The frequency of a significant effect of a hurricane is about once every ten years. The diff usion climatology of the site has been studied based on nearby stations and on-site data. The site tends to have a relatively low frequency of stable conditions for onshore winds. An extensive discussion of the diffusion climatology ofVolume the site1,may be foun{I n the Calvert Cliffs Final Safety Analysis Report, Section 2.3 l-4 TERA CORPORATION
Although surface runoff in the area is moderately high, amounting to about 35 percent of the total annuel precipitation, the site is well-drained and not susceptible to precipitt tion induced flooding. A drainage divide extends across the site in a generr.1 nortiesouth direction. The area east of the divide (20 percent of trie site) drains into Chesapeake Bay, whereas the area to the west drains into local tributaries and eventually into the Patuxent l River. The Plant is located east of the dNide, where surface drainage is { toward the Chesapeake Bay. High surface runoff at:d low infiltration are attributed to the impermeable nature of the Miocene subsoils which form an aquiclude between the over-lying unconfined and the underlying confined (artesian) ground water. 1.4 GENERAL PLANT DESCRIPTION (I) l l Both of the nuclear power units utilize identical pressurized water reactors j which are designed and fabricated by Combustion Engineering, Inc. The Unit 1 i turbine-generator was furnished by the General Electric Company, and the Unit 2 turbine-generator was furnished by the Westinghouse Electric Corporation. Both turbine-generators are similar in type and construction and have similar performance characteristics. The design power rating of each unit is 2560 megawatts thermal (MWt) with an ultimate power level not to exceed 2700 MWt. i i The net electrical power output available for distribution for each unit is ' about 845 megawatts (MWe). Each electrical generating unit of the Calvert Cliffs Nuclear Power Plant has three separate water loops. The first or primary coolant loop is a closed piping system and it is through this loop that the pressurized water is cir-culated through the reactor. The water frou1 this loop moderates the fissioning process and transfers the heat, generated by this process, from the reactor to the steam generators. The secondary loop is also a closed system. The water in this loop is converted into steam in the steam generators, is passed through the turbine and, upon leaving the turbine, is condensed back to water and returned to the steam generators. The third loop is an open system where water from the Chesapeake Bay is passed through the condensers, cooling the spent steam leaving the turbine, and then returned to the Bay. 1 1-5 TERA CORPORATION L.-___.._____._____---__ _ _ _ - _ _ _ _ _ _ _ - _ _ _ - _______-_.______._m m.__._ _____._ . _ _ _ _ _ _ . _ _
2.0 DESIGN DESCRIPTION OF LIQUID AND GASE0US WASTE HANDLING SYSTEMS This section of the report describes the original design bases for the liquid and gaseous waste handling systems. As such, specific numbers and mode of operation presented are extremely conservative design parameters which do not reflect actual or anticipated experience at Calvert Cliffs and do not reflect the Appendix I evaluation assumptions of following sections. However, it is necessary to establish the original bases for design and operation in order to effectively evaluate current system per-formance, operating characteristics, and radiological effluent impact. Section 5.0 of this report provides a brief review of current operating experience at Calvert Cliffs and evaluates the calculated radiological impacts in terms of expected effluent releases. 2.1 RADI0 ACTIVE LIQUID WASTE SYSTEM (I) 2.1.1 DESIGN BASES 2.1.1.1 Perfonnance Objectives The radioactive liquid waste handling systems provide controlled handling, processing and disposal of liquid wastes. The systems are designed to ensure that plant personnel and the general public are protected against excessive exposure to radiation from wastes, in accordance with limits de-fined in 10CFR20 and guidelines of 10CFR50, Appendix I. The systems minimize or preclude discharge to the surrounding environment of radioactive liquids of station origin. The system design was based upon processing reactor coolant and miscellaneous waste during operation with one percent failed fuel . It was conservatively assumed that 14 system volumes of reactor coolant per unit would be processed annually in order to determine the sizing of waste processing components. At any one time, the waste receiver tanks and waste monitor tanks can accommodate six system volumes of reactor coolant. The design performance for the liquid waste portion of the system was estab-lished by examining seafood consumption routes to determine limiting discharge concentrations. Liquid effluent from the waste processing systems is controlled such that the increases in boron concentration of the circulating l water are minimized. Sampling and release of liquid wastes were designed to be accomplished on a selective tank basis rather than on a continuous basis in order to provide for increased control over effluent discharge. 2-1 TRACORPORATION
i The Reactor Coolant Waste Processing System is designed to process reactor coolant concurrently with the letdown flow from the Chemical and Volume Control System. The liquid systems were designed to provide a variable release rate of waste from the monitor tanks to the circulating water discharge conduits of either or both units in order to maximize the dilution. 2.1.1.2 Radioactive Waste Quantities The volumes of radioactive liquids generated during normal station operation which were assumed for design are presented in Tables 2.1-1 and 2.1-2, along with the assumptions employed to develop them. These values were used for determining equipment capacity and represent a conservative rather than actual charuterization of plant operation. Total volumes presented are for two-unit operations. i 1 2.1.2 RADI0 ACTIVE LIQUID WASTE SYSTEM DESCRIPTION ! i The liquid waste processing systems include the Reactor Coolant Waste Processing I System (RCWPS) and the Miscellaneous Waste Processing System (MWPS). Infor-mation on the design and fabrication of the components of these systems is listed in Table 2.1-3. A description of each system follows. 2.1.2.1 Reactor Coolant Waste Processing System 1 The RCWPS is shcwn in Figure 2.1-1, sheets 1 and 2. Reactor coolant is I diverted to this system when changes in reactor coolant system inventory or boron concentration are necessitated by startups, shutdowns, fuel depletion, draining the reactor coolant system for maintenance, etc. Liquid waste is let down via the Chemical Volume Control System (CVCS) through a filter to reduce insoluble particles and then flows to the degasifier. The degasifier removes hydrogen and fission product gases from the liquid waste and discharges these gases to the waste gas surge tank. The degasified liquid is pumped through reactor coolant bleed ion exchangers, which remove soluble ions, and then flows to the reactor coolant waste receiver tanks. These tanks pro-vide surge capacity if the reactor coolant letdown flow rate is higher than the design flow rate of the evaporator. From these tanks, the liquid is j pumped to a waste evaporator which distills the water and concentrates the ' boric acid. The boric acid concentrate is sampled at the evaporator for I purity, then, depending upon the results, is pumped either to the boric acid l storage tanks for reuse in the reactor coolant system or to the solid waste disposal system for processing and offsite disposal. The evaporator dist" late is pumped to the reactor coolant waste monitor tanks for sampling. If the activity level is unacceptable, the liquid is reprocessed through the ion exchangers and/or evaporators. If the activity level is within discharge limits, the liquid is pumped, at a rate selected over a range of 10-120 gpm, to the circulating water system where it is diluted with the water in the discharge conduits. This liquid can be directed to 2-2 TERA CORPORATION
Table 2.1-1 _ Reactor Coolant Waste Processing System Sources and Volumes Waste Volume Source Generating Operation (gallons /yr-unit) Chemical and Volume Reduction of boron 190,000 Control System Cold shutdown @ 100 days full power 63,000 operation and subsequent startup Cold shutdown 0 200 days full power 76,000 operation and subsequent startup Cold shutdown 0300 days full power 118,000 operation and subsequent startup Six hot shutdowns and subsequent 263,000 startups during cycle Refueling shutdown 0 360 days full 70,000 power operation and subsequent startup Regenerative Heat Subtotal 780,000 Exchanger One shell volume per year 32 Safety Injection ----- 0 Tanks Leakage Loop 11A Drains 1/16 of total primary loop volume per year 4,500 Loop llB Drains 1/16 of total primary loop volume per year 4,500 Loop 12A Drains 1/16 of total primary loop volume per year 4,500 Loop 12B Drains 1/16 of total primary loop volume per year 4,500 Quench Tank Drains Two quench tank volumes per year 3,000 Flange Leakage ----- 0 Detector Drain Loop No. 11 Hot Leg 1/16 of total primary loop volume per year 4,500 Drain Leakoff from Valves ----- 10 in Containment R.C. Pump Seal Leakage ----- 0 TOTAL VOLUME / UNIT 805,542 TOTAL VOLUME FROM UNIT 1 AND 2. . . . (gallons /yr-plant) . . . . . . . . . . . . . 1;611,084 2-3 TERA CORPORATION
I Table 2.1-2 Miscellaneous Waste Processing _ System Sources and Volumes Volume Source (gallons / r I Waste Generating Operation / Area for plant Laboratory Sink Drains 24 samples per day at 2.5 gallons per sample 22,000 l i Spent Fuel Cask Wash- 100 gpm for 30 minutes per week 156,000 down Area Drains Spent Fuel Storage ----- 20,000 j Area Drains Low Point Piping Drains ----- 12,000 Auxiliary Building ----- 10,500 l Gravity Drains Auxiliary Building 84,000 Pumped Sumps Laundry ----- 9,000 Showers 150 showers @ 30 gallons per shower 4,500 Component Cooling ----- 0 System Relief Valves Boric Acid Preparation -- ----- 4,000 Area Drains Equipment Drains ----- 23,000 High & Low Pressure 6 HP pumps and 4 LP pumps at 100 cc/hr each- 120 Safety Injection Pump assume two LP pumps operate for 3 weeks Seal and Bearing Water during refueling Blowdown Tank Drain 2.0 gpm for one year (80% capacity factor) 841,440 Charging Pumps 2 pumps, 24 hrs per day, all year, 18,500 at 0.0176 gpm each T01AL VOLUME (2 Units in operation) 1+205,060 t 2-4 TERA CORPORATION E
i Table 2.1-3 Liquid Waste Processing System Compon:nt Description ) i RCWPS Reactor Coolant Drain Tank Pumps Type Horizontal centrifugal, end suction, mechanical seal Two . Quantity Capacity (gpm) 100 l Head (ft of H20) 113 Material : Case 316 SS Impeller 316 SS Shaft 316 SS Motor 7.5 hp., 3 phase, 60 nz., 460V Code NEMA, ASME - Pumps and Valves for Nuclear Power Degasifier Pumps Type Horizontal, centrifugal, end suction, mechanical seal Quantity Two Capacity (gpm) 150 Head (ft of H 2O) 221 Material: Case 316 SS Impeller 316 SS Shaft 316 SS Motor 20 hp., 3 phase, 60 hz, 460V l Code NEMA, ASME - Pumps and Valves l for Nuclear Power Reactor Coolant Waste Receiver Tank Pumps Type Horizontal centrifugal, end suction, mechanical seal Quantity Two Capacity (gpm) 120 Head (ft of H 7'0) 204 Material: Case 316 SS Impeller 316 SS Shaft 316 SS Motor 15 hp. , 3 phase, 60 bz, 460V Code NEMA, ASME - Pumps and Valves for Nuclear Power 2-5 TERA CORPORATION
i Table 2.1'-3 (continued) Liquid Wa_ste Processing System Component Description l RCWPS Reactor Coolant Waste Monitor Tank Pumps Type Horizontal centrifugal, end suction, mechanical seal Two Quantity Capacity (gpm) 120 Head (ft of H20) 204 Ma terial : Case 316 SS Impeller 316 SS Shaft 316 SS Motor 15 hp. Code NEMA, ASME - Pumps and Valves for Nuclear Power Reactor Coolant Waste Monitor Tank Metering Pump Type Horizontal centrifugal, l end suction, mechanical seal . Quantity One i Capacity (gpm) 10 Head (ft of H20) 60 Material : Case 316 SS Impeller 316 SS Shaft 316 SS Motor 1 hp., 3 phase, 60 bz, 460 V Code NEMA, ASME - Pumps and Valves for Nuclear Power i l Reactor Coolant Drain Tank Type Horizontal i Quantity Two DesignPressure(psig) 50 Volume (gal.) 900 Code ASME Section III Class C Material Type 304 SS 2- 5 TERA CORPORATION
Table 2.1-3 (continued) Liquid Waste Procesling System Compor.ent Description _ RCWPS Reactor Coolant Waste Receiver Tanks Type VerMcal Quantity Two l Design Pressure (psia) 15 i Volume (gal .) 90,000 l Code ASME Section VIII l Material Type 304 SS I l i 1 i Reactor Coolant Waste Monitor Tanks 1 i Type Vertical , Quantity Two 1 Design Pressure (psia) 15 Volume (gal.) 90,000 l Code ASME Section VIII l Material Type 304 SS Reactor Coolant Degasifiers Type Packed Tower Quantity Two Design Pressure (psia) 75 Reactor coolant bleed (gpm) 0-120 Code ASME Section III - Class C, ANSI B31.1 Liquid Waste Evaporators Quantity Three Type Horizontal, vacuum Design Pressure (psia) 30 Design Distillate Flow (gpm) 20 Code ASME Section III, Class C liede of Operation Batch (RCWPS), Continuous (MWPS) Feed Tank Capacity (gal .) 1000 2-7 TERA CORPORATION
l Table 2.1-3 (continued) I Li_ quid Waste Processing System Compnnent Descriptiojl MWPS Miscellaneous Waste Receiver Tank Pump , 1 Type Morizontal centrifugal, end suction, mechanical seal .) Ore Quantity Capacity (gpm) 123 Head (ft of H20) 110 Material: Case 316 SS Impeller 316 SS Shaft 316 SS Motor 7.5 hp., 3 phase 60 bz, 460V. . Code NEMA, ASME - Pumps and Valves for l Nuclear Power Miscellaneous Waste Monitor Tank Pump l Type Horizontal, centrifugal end suction, mechanical seal l One Quantity Capacity (gpm) 120 Head (ft of H 2O) 110 Material: Case 316 SS Impeller 316 SS Shaft 316 SS Motor 7.5 hp., 3 phase, 60 hz, 460V Code NEMA, ASME - Pumps and Valves for Nuclear Power Miscellaneous Waste Monitor Tank Metering-Pump Tyoe Horizontal, centrifugal, l end suction, mechanical seal 2 Quantity One ) Capacity (gpm) 10 ! Head (ft of H20) 60 l Material: I Case 316 SS l Impeller 316 SS ! Shaft 316 SS ! Motor 1 hp., 3 phase, 60 bz, 460V ; l Code NEMA, ASME - Pumps and Valves for Nuclear Power i i i 2-8 I TERA CORPORATION j _ _ _ _ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - - -a
i I Table 2.1-3 (continued) j I Liquid Waste Processing System Component Description MWPS 4 Miscellaneous Waste Receiver Tank Type Horizontal Quantity One Desi0n Pressure Atmospheric Volume (gal.) 4000 Code ASME Section III - Class C Ma ter ial Type 304 stainless steel Miscellar;eous Waste Monitor Tank , Type Horizontal Quantity One Design Pressure Atmospheric Volume (gal.) 4000 Code ASME Ser. tion III - Class C Material Type 304 stainless s teel i Ion Exd angers Type Mixed bed, non-regenerable quantity Five Design Pressure (psig) ' 200 Flow (gpm) 128 Material: Vessei Shell ASME Section III - Clcss C (Caetior. VIII, Para. UW-2a, ?pplies) Vessel head ASME-SA-240 Typa 304 Internals ASME-SA-240 Type 304 Austenitic stain?ess steel Filters Type Cartridge Quantity Five Design Pressure (psig) 125 Flow (gpm) 120 Code ASME Section III - Class C Removal Efficiency for Particle 98 percent Sizes Greater than 0.45 Microns 2-9 TERA CORPORATION
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the discharge conduits of either ur both units. A radiation monitor and re-dundant isolation valves are installed between the waste processing system and the circulating water system. A high radiation monitor alarm, which is annunciated in the control room, automatically shuts the isolation valves and < prevents further discharge. 2.1.2.2 Miscellaneous Waste Processing System ; 1 The MWPS is shown in Figure 2.1-2. Laboratory drains, laundry and other ! miscellaneous soapy drains are collected in a common header which drains directly to the miscellaneous waste monitor tank. All other miscellaneous wastes are collected and drained to the miscellaneous waste receiver tank. If necessary, miscellaneous liquid waste can then be processed by evaporation, filtration and/or ion exchange and pumped to either the reactor coolant waste or miscellaneous waste monitor tanks. Concentrated waste from the evaporator bottoms is pumped to the solid waste system. The liquid in the monitor tank is sampled, and if the activity level is acceptable for discharge, it is pumped to the discharge conduits of either or both units. If the activity level is not within limits for discharge, the contents of the miscellaneous waste monitor tank are reprocessed by evaporation and/or ion exchange. l 2.1.3 LIQUID WASTE SYSTEM DESIGN EVALUATION The following data is presented in order to define the o_riginal design j criteria and assumptions for the Calvert Cliffs liquid waste system design. It is provided for information purposes only and was not used in the Appendix I radioactive source term evaluations in the sections which follow, i In order to evaluate the design of the liquid waste processing systems, it was postulated that both NSSS's were operated continuously with one percent failed fuel. Using these source terms, annual releases of radioactivity from the Calvert Cliffs Nuclear Power Plant were determined. These calculations resulted in an order of magnitude higher annual release than actually expected. A discussion of the assumptions used for calculational purposes to determine the annual releases from all sources in the plant is provided in the folleving sections. 2.1.3.1 Reactor Coolant Waste Processing Sys_ tem Effluents The RCWPS is sized to process 14 reactor coolant system volumes from each unit per year. Table 2.1-1 shows the postualted operations which would result in the generation of this total volume of waste. The design basis equilibrium concentration of radioisotopes in the reactor coolant prior to processing and the associated annual activity discharged af ter processing through the RCWPS were based on one percent failed fuel 2-12 TERA CORPORATION
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in each reactor, the recycle of boric acid, and 14 system volumes of coolant processed annally from each reactor coolant system or a total of 28 system volumes from the plant. The decontamination factors (DF's) used for these calculations are as follows: l 1. Total system filtration DF for corrosion products is 10. This includes the CVCS filter, the degasifier inlet filter and the evap' orator jnlet filter.
- 2. Total system ion exchange DF for all fission products except
, noble gases and tritium is 100. The total system includes the CVCS ion exchangers and reactor coolant waste processing system ion exchangers. This total average DF takes into consideration the variable removal capat ty of resins for different isotopes.
- 3. Total system evaporative.0F for all isotopes except iodine, tritium and noble gases is 250 afp for iodine is 50.
- 4. Total DF for remoial of noble ga es from liquid is 1 x 105, This includes a fact 6r of 1 x 10 across a degasifier and a factor of 10 across an evaporator which is equipped with an exhauster in the condenser.
Therefcre, the total RCWPS DF's are: Corrosion Products 2.5 x 10 3 Fission Products (except tritium) 2.5 x 10 4 Iodine 5 x 10 Noble Gases 1 x 10 5 No radioactive decay was assumed after letdown from the reactor coolant system. 1 1 2.1.3.2 Miscellaneous Wasta Processing System Effluents l The sources and volumes of : miscellaneous wastes assumed to be processed I annually by ,the MWPS are shown in Table 2.1-2. For all liquid except that coming from the blowdown tank drain, the average specific activity was calculated to be twenty-five percent of reactor coolant values. The average specific activity value for this miscellaneous liquid was calculated by assuming the liquid waste draining into the auxiliary building pumped sumps,(84,000 gallons) from the containment sumps has a speci-fic activity equal to'the reactor coolant. The remaining miscellaneous liquid (279,620 gallons) was assumed to have a specific activity equal to 1 percent of the reactor coolqM values. Steam generator blowdown specific activity was calculated based on one percent failed fuel, 50 gallons / day per steam generatcre tube leakage, and 0.5 gallon / minute per steam generator blowdown.
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2-14 TERA CORPORATION
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The calculation of specific activity of the liquid entering the MWPS from the blowdown tank drain included radioactive decay in the steam generators. The noble gases contained in this liquid were assumed to be released via the gaseous pathways and were included in the calculated total gaseous releases. The DF's used for these calculations are as follows: ! l 1. Total ion exchange DF for all fission products except tritium is 100. This total average DF takes into consideration the variable removal capability of resins for different isotopes.
- 2. Total system evaporative DF for all isotopes except iodine and tritium is 500 and for iodine is 100.
The total MWPS DF's are: i i Corrosion Products 5x10f Fission Products (except tritium) 5 x 10 l Iodine 1 x 10 4 l 2.1.3.3 Other Liquid Effluents It will be required to blow down the secondary side of the steam generators to maintain the water chemistry within acceptable limits if condenser tube leaks are excessive. The condensate polishing demineralizers (capable of 50% full power condensate flow) are installed to maintain acceptable chemistry during operation with small condenser tube leaks. Prior to any blowdown, the steam generators are sampled. If the analysis of the sample indicates the gross activity is within limits, blowdown will be commenced to the blowdown tank which will be discharged directly to the circulating water discharge conduits. A radiation monitor is installed in the line from the blowdown tank to the discharge conduits which will alarm on high activity and automatically shut the discharge valve. This feature provides a backup to the anal / sis and also terminates the discharge if the gross activity of the steam generator increases above the level allowable for direct discharge during the blowdown. If the gross activity level is not acceptable for discharge, the contents of the blowdown tank will be drained to the MWPS. The total non-tritium activity discharged directly from the blowdown tanks is recorded and is limited to one curie per year. Additionally, it is expected that there will be leaks in the secondary systems. If there is any iodine or particulate activity in the steam generator, some slight quantities of activity will be carried over and be released by the ! leaks to the turbine buildina. Most of this activity will remain in the i liquid phase and be released via the turbine building drains. ! I i
~
TERA CORPORATION
m- - s I 2.2 RADI0 ACTIVE WASTE GAS PR_0_ CESSING: SYSTEM U) 2.2.1 DESIGN BASES l
- 2. 2.1.1 Performance Objective:
The Radioactive Wast? Gas System provides controlled handling, processt.g and disposal of gaseous westes. The syste,r. is designed to ensure that plant per-sonnel and t.he general public are protected against excessive exposure to ; radiation from wastes, in accordance with limits defined in 10CFR20 and guide- ; 1%es cf 10CFR50, AppenF I. I 1 The systen minimizes discharpe of radioactive gases of station origin to the ) surrounding envirordent. Gases are stored on site for radioactive decay prior { to controlled release, through particulate filters, within the guidelines of i 10CFR50, Appendix I. Sufficient waste gas decay tank capacity is provided to 1 allow 60 days decay for the gases contained in 28 system volumes of reactor ! coolant. I l 2.2.1.2 Radioactive W9te Quantities The volumes of radioactive gases gcnerated during normal station two-unit I operations which werc assumed for design are presented in Table 2.2-1, along with the assumptions employed te develop them, l 2.2.2 WASTE GAS PROCESSIU.G SYSTEM DESCRIPTION I The WGPS is shown in Figure 2.1-2, and its components are described in Tibla 2.2-2. l l Waste gases are collected in three headers. One header collects radiactive gases from containment systems und discharges to the waste gas surge. tank. A second header crilects radicar.tive gases from auxiliary buil(ing sources, in-cluding tne licuid waste processing rystem degasifiers and RCWPS evaporators and directs them to the waste gas surge tank. The third heauer cfilects other vents and 'elief valve discharges and connects to the gas release hEdder prior to the gas discharge monitor. A waste gas :,omprascr takes suctior on the waste gas surge tank and discharges to one of thrra uste gai . decay tanks where the gas is stored at c; design pressure of l'.30 psig. Relief valves on Each gas decay tank dh. charge tt the waste gas surge tank to prevent the unscheduled release of ga m to the atmo-sphere in the event of overpressurization ref the decay tanks. The (ccay tank is nampleo, and when the activity level ha.; decayed to an acceptaole level,
~
the cor/.ent.s are discharged at a ' controlled rate, through the relcase header,, to the plant vents. The release header contains an absolute filter; e radia-tion monitor and redundant, automatic isolation valves. A Ligh radiation woniter alara, eahich is annunciated in the control room, automatically shuts the isolation valves. 2-16 TERA CORPORATION
Table 2.2-1 Waste Gas Processing System Sources and Volumes Volume (ft @ 14.7 psia, 80F , Source _ Waste Generating Operation per year for plant) ) R.C. Drain Tank No. 11 Three R.C. drain tank volumes 360 per year ) R.C. Drain Tank No. 21 Three R.C. drain tank volumes 360 per year l Pressure Quench Tank One quench tank volume per year 2,660 No. 11 Pressure Quench Tank One quench tank volume per year 2,660 No. 21 1 Volume Control Tank Four tank volumes purged per year 6,500 No. 11 Volume Control Tank Four tank volumes purged per year 6,500 No. 21 ' Degasifier No. 11 28 reactor coolant volumes 23,000 and No. 12 processed per year Evaporator No. 11 and 28 reactor coolant volumes 4,200 No. 12 processed per year Miscellaneous Sources Continuous 1,000 TOTAL VOLUME (For 2 Unit operation) 47,240 l 2-17 TERA CORPORATION
Table 2.2-2 Waste Gas Processing System Component Description Waste Gase Surge Tank Type Vertical Design Pressure (psig) 50 3 Volume (ft3 ) 610 l Code ASME Section III - Class C Material Type 304 Stainless Steel Waste Gas Decay Tanks Type Vertical j Quantity Three 1 Design Pregsure (psig) 150 Volume (ft0) 610 g Code ASME Section III - Class C : Material ASTM-A-264, Type 304 SS clad l Waste Gas Compressors j Type Single stage, 1 head, diaphragm Quantity Two Capacity (scfm) 4.0 to 7.0 > Design Discharge Pressure (psig) 150 l Motor 3.0 hp., 3 phase, 60 hz, 460V { Code NEMA .I I l i i i 1
)
2-18 TERACORPORATION I t _ _ _ _ _ _ - - - _ _ _ - __ __ . _ - _ . ._ a
1 1 2.2.3 WASTE GAS PROCESSING SYSTEM DESIGN EVALUATION The following data is presented in order to define the original design criteria and assumptions for the Calvert Cliffs Waste Gas Processing System design. It )- is provided for information purposes only and was not used in the Appendix I , radioactive source term evaluations in the sections which follow. 1 2.2.3.1 Waste Gas Processin g st_em_E_ffluents j The WGPS is sized to holdup for 60 days prior to release of the gaseous isotopes contained in 14 reactor coolant system volumes trom eacn unit per year and other miscellaneous sources of gaseous wastes. Table 2.2-1 shows the sources of this total volume of gaseous wastes. After 60 days decay, Kr-85, Xe-131m and Xe-133 are the only significant gaseous isotopes which contribute to the effluent source term. 2.7.3.2 Other Gaseous Effluents There are other potential sources of gaseous releases from the plant which ) are not collected in the WGPS for holdup. If leaks occur in systems con- J taining reactor coolant, radioactive gases could be released as a result I of purging the :ontainment structures, from the condenser air removal systems, I turbine builoing ventilation systems and aerated tank vents. All of these ) potential sources except the turbine building ventilation are released through I the plant vent. j i
- 1. Both reactors are operated with one percent failed fuel, l and a total of 28 reactor coolant system volumes of waste l are processed from both units per year. {
1
- 2. Leakage from the reactor coolant system to the secondary side I of the steam generators of each unit is 50 gallons per day per steam generator.
- 3. The annual average blowdown rate from each steam generator is 0.5 gallons per minute.
- 4. The release of radiciodine and particulate in the steam exiting from the steam generators is solely a function of moisture carryover which is 0.2 percent of the steam flow.
Additionally, the moisture separators in the steam generators are assumed to be 90 percent efficient in the removal of particulate from the exiting steam.
- 5. Moisture carryover is also the only mechanism for release of radiciodine and particulate from the main condenser air removal and gland seal systems. Moisture carryover from this system is assumed to be 0.5 percent of the flow rate.
1 i 2-19 TERA CORPORATION
i
- 6. The annual average air flow rate from the main condenser air removal and gland seal systems of each unit is 60 SCFM and 600 SCFM, respectively.
- 7. All noble gases leaking from the reactor coolant system to the steam generators are released through the main condenser air removal systems.
- 8. Leakage from the reactor coolant systems to each containment ;
structure is 150 gallons per day.
- 9. Under equilibrium conditions, one percent of the iodine and particulate leaking into the containment remains in the atmosphere and is available for release. The other 99 percent of the iodine is either plated out in the containment or remains in the liquid and is collected in the containment sump.
- 10. The containment filters are operated for five hours prior to purging the containment structures with an iodine removal efficiency of 99 percent, and a particulate removal efficiency of 99.9 percent.
- 11. The containments are purged ten times a year for six hours each to allow personnel access.
- 12. The annual average leakage from radioactive systems into the entire auxiliary building is 200 gallons per day (100 gallons /
day / uni t) . The annual average specific activity of this leakage j is one percent of the reactor coolant value. '
- 13. One percent of the iodine and particulate leaking into the auxiliary building is released to the atmosphere and 99 percent is contained in the liquid collected in the auxiliary building drains.
2-20 TERA CORPORATION
l i 2.3 PLANT VENTILATION SYSTEM (I) i 2.3.1 DESIGN BASES The plant ventilating systems are designed to provide a suitable environ-ment for equipment and personnel with a maximum amount of safety and { operating convenience. Potentially contaminated areas are separated from 1 clean areas. Air-flow patterns originate in areas of potentially low ] contamination and progress toward areas of higher activity. Negative , pressures are maintained in potentially contaminated areas and positive pressures in clean areas. The ventilating systems in the containment, { waste processing and fuel-handling areas are designed for containment of I radioactive particles. The path of the discharge from all potentially contaminated areas is directed into the respective plant vent where the radioactivity level is monitored. The equipment in most critical systems is redundant in character and detailed descriptions are presented where this occurs. Basic temperature design criteria and flow capabilities are listed in Table 2.3-1. l 2.3.2 SYSTEM DESCRIPTIONS The plant ventilation systems discussed in this section are shown on Figures 2.3-1 (Sheets 1 and 2) and 2.3-2. 2.3.2.1 Containment Ventilation Containment Purge System There is a separate, identical purge system for each containment. In each system an air-handling unit, located in the auxiliary building, supplies filtered and tempered air to the containment through a supply duct. I i One exhaust fan for each containment structt'e, located in the auxiliary l building, draws air from the containment through an exhaust duct and HEPA J filters, and discharges it into the respective main plant exhaust plenum ] where the fans force it into the plant vent. The air-operated butterfly l valves which fail closed are located in the supply and exhaust ducts on each side of the containment penetration for these ducts to provide con-tainment isolation when necessary. Upon a containment isolation signal or containment radiation signal, the containment purge isolation valves close, and the purge system fans are shut down automatically. l A recirculating charcoal filtration system consisting of three 20,000 cfm i trains, each containing upstream HEPA filters and downstream charcoal adsorber i beds (2 inch depth) is available in the containment should airborne iodine j concentrations reach unacceptably high levels. This system is not used under normal operating conditions. 2-21 TERA CORPORATION
TABLE 2.3-1 PLANT VENTILATION SYSTEM DESIGN CONDITIONS Main Plant Vent Flow Capability j Type Summer ( W) Winter (OF) Unit No. 1 Unit No. 2 f System System Inside Outside Inside Outside (cfm) (cfm) Turbine Building HV 110 95 60 0 Contairnent Cooling AC 120 95 60 0 Pressurizer Compartment AC na na na na Cavity Cooling AC na na na na na na na I AC na CE0MCooling(1) Purge System na 60 0 50,000 50,000 V na l Pipe Penetration Rooms (2) V 130 na na na 2,000 2,000 I Auxiliary Building Auxiliary Feedwater Pump Room HVAC 90 na na na 95 Control-Cable Rms. HVAC 75 75 C Access Control Area na 13,900 l l Health Physicist HVAC 75 95 75 0 Hot Laboratory HVAC 75 95 75 0 Other Controlled Rms. HV na na 75 0 Clean Rooms HV na na 75 0 Main Stm. Pen. Areas V 110 95 60 0 l i Switchgear Rooms HV 104 95 104 0 I l Diesel Gen. Rooms HV 120 95 60 0 l Spent Fuel Pool HV 110 95 60 0 32,000 na l Radwaste Area HV 110 95 60 0 49,500 49,500 ) ECCS Pump Room HVAC 110 95 60 0 3,000 3,000 l l l Intake Structure HVAC 104 95 104 0 l l l Service Building l 1 Office Area HVAC 75 95 75 0 l Locker Room HV na 95 80 0 Warehouse HV 110 95 60 0 Shop HV 110 95 60 0 136,500 118,400 Notes: (1) In operation only when containment is occupied l (2) Operated intermittently as required and during LOCI i l l l 2-22 TERA CORPO9ADQN
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i l Cavity Cooling System Two redundant fans supply air from the containment air cooler plenum through i ducting to the reactor cavity distribution manifold where it is used to cool l the neutron detectors, the primary shield penetrations and the primary shield. ] Systam performance is adjusted by manual balancing. High efficiency filters ' are installed to protect each branch which serves a neutron detector. l 2.3.2.2 .A_uxiliary Building Ventilation Systems Waste P_rocessing, Spent Fuel Pool and Emergency Core Cooling l Punip Room Area Ventilation l A negative pressure with respect to surrounding areas and the outside l is maintained at all times in this area. I l A common air supply system consisting of three 50% capacity air-handling i units positioned on the west side of the auxiliary building at elevation l 69'-0" supplies tempered air for ventilation of the common waste processing i area. A system of ductwork assures a uniform distribution throughout I this area. Separate exhaust systems for Units 1 and 2 draw air from their respective waste processing araas by means of ductwork and force it through HEPA fiiters after which it is discharged into the main plant exhaust plenums provided for each unit. From here, the main plant exhaust fans force the air past the radioactivity monitors and out through the exhaust stacks. These exhaust fans are 100% redundant but the filters are not redundant. A separate air supply consisting of two 50% capacity air handling units, positicned at elavation 86' directly above the other three supply units, serves the Spent Fuel Pool area with tempered air for ventilation. The Emergency Core Cooling System (ECCS) pump rooms for Unit 1 and 2 are served by the common waste processing area ventilation supply system. Separate exhaust fiiters and ducting are provided for the Spent Fuel Pool and both Unit 1 and 2 ECCS puinp room areas. In each exhaust system, the air is directed through HEPA filters. The spent fuel pool exhaust may then either be sent directly to the main plant exhaust plenums, or directed by means of dampers through charcoal filters before being tent to the main plant exhaust plenums. The ECCS pump room exhausts, however, empty directly irito the nuin piant vent. The ECCS pump room exhausts may be directed through a charcoal filter prior to emptying into the main plant vent. A negative pressure is maintained in the waste processing and ECCS pump room areas with respect to ambient and surrounding areas of the building. Fan-Coil coolers are installed in each ECCS pump room to provida additional cooling, if necessary, during pump operation. 2-26 TERA CORPORATION
a i
}
Spent F,uel Pool Supply and Exhaust Syltem Two air-handling units supply tempered outside air to one side of the spent fuel pool area at elevation 69'-0". A separate exhcust system picks up ; air through a manifold, located on the opposite side of the pool, draws it I through HEPA filters, and feeds it into the main plant vent of Unit 1. During the refueling period, this air can be manually diverted by dampers into ! charcoal filters after it leaves the HEPA filter bank. In this system the i exhaust fans are redundant but the filters are not. Unit heaters are used maintain a minimum temperature of 60 F in the wintertime. Control Room l The control room (elevation 45'-0") and the cable spreading room (elevation 27'-0") are incorporated into one year-round air-conditioning system serving both Units 1 and 2. Air handling and refrigeration equipment are redundant. l A positive pressure is normally maintained in the control room and the excess ! air is exhausted outside the plant. If airborne contamination occurs at the j fresh air intake, a high radiation signal from the fresh air monitor auto- l matically will close the fresh air damper and start the post LOCI filter fans and open their associated discharge dampers. Under these conditions, 2000 cfm of circulated air passes through the HEPA and charcoal filters. Instrumentation is provided to continuously indicate system performance such as excessive pressure drop through the air handling unit, fan failure or high radiation level. Access Control Area This area is located on elevation 69'-0" in the auxilisry building and serves both Units 1 and 2. It is divided into " clean" and " controlled" zones and l consists of rooms such as locker rooms, washrooms, office and laboratory areas. Part of the " controlled" zone is air-conditioned and part is heated i l and ventilated only. The " clean" zone is heated and ventilated. This is a 100% outside air system. No air is recirculated from any part of the area. l The direction of air flow between rooms is carefully controlled and moves i from " clean" to " controlled" areas. One air handling unit supplies " tempered" makeup air to all zones except the " air conditioned" area. Another unit supplies " tempered" air at a temperature not lower than 60 F to each of the Laboratory Exhaust Hoods for " primary ventilation air." All of the primary air plus a percentage of air drawn through ;he " Hoods" from the room is co pinuously being exhausted into the main plant exhaust plenum after passing through HEPA filters which are placed in the discharge duct from each " Hood." Electric heating coils located in the ductwork are used to heat each zene separately. A separate cooling and heating unit serves the Health Physics and Hot Laboratory area. 2-27 lERA CORPORATION i
l Duriag normal operation exhaust from all areas is directed through a HEPA filter bank and then fed into Unit #2 main plant exhaust plenum. !!owever, during the hottest part of the summer, additional cooling in the " clean" area is required. Local fresh air supply and exhaust fans will be used which exhaust directly to the outside. i 2.3.2.3 T_urbine Building Ventilation System When Units 1 and 2 are both in operation, the turbine building requires . cooling all year round. Outside air is used for this purpose since it will normally be at least 15 degrees below the turbine building maximum design air temperature. Twelve fans, one in each vertical air shaft at i elevation 95'-0", supply air from mixing boxes through ducting to all levels of the turbine building and heater bay area. The proportioning of ; fresh air and recirculated air, which is accomplished by means of dampers ' located in the mixing box, is controlled by a room thermostat located on the operating floor level. The walls of the vertical shafts are louvered above the fan level, thus permitting them to serve as an intake plenum. All Turbine Building ventilating fans are manually controlled. Plant operations personnel determine the number in operation at any one time. Two of the four ~.haust dampers located near the center of each horizontal air shaft open automatically when one supply fan is started and close when the fan is stopped. When the fan is stopped the fresh air damper closes and the associated recirculation damper opens. In case of fire this control system is overridden and the exhaust dampers move to the full open position while the other dampers remain or return to their fan-off positions. No HEPA or charcoal filtration of turbine building exhaust is provided. 2-28 TERA CORPORATION
f 3,0 DERIVATION OF PLANT EFFLUENT SOURCE TERM l
3.1 INTRODUCTION
AND EVALUATION BAS _ES_
]
The Calvert Cliffs Nuclear Power Plant, Unit 1, completed its first year of I commercial operation in May 1976. Unit 2 has not yet begun operation. Thus j the plant effluent source term has been calculated rather than taken from l operating data. However, station radioactive liquid and gaseous effluent source terms for the Appendix I evaluation were derived, whenever possible, on the basis of actual plant operational performance and procedures. Operating experience was used to determine the expected operational modes, and their effects on overall plant performance parameters such as system flow rates, quantities of waste processed, and holdup times. Where experience was considered insufficient to represent the expected mode of operation or performance parameter, assumptions were made consistent with , those recommended in Regulatory Guide 1.ll2(W (formerly Draft Regulatory j Guide 1.BB). The objective of the source ter.n calculation was to develop a l conservative measure of the actual performance of the plant and hn appropriate l adjustment factor to account for anticipated operational occurrences. Descriptions of the original design of each of the plant systems associated , with liquid and gaseous effluents are provided in Section 2.0, together with I I their design bases. The actual parameters used to calculate the source terms are presented in Table 3.2-1 below, and c9mpared to the original FSAR/ER and NRC Final Environmental Statement (FES)(O parameters. A detailed discus' ion of these parameters is given in Appendix A. l l 3.2 INPUT PARAMETERS FOR SOURCE TERM CALCULATIONS 1 3.2.1 PRIMARY SYSTEM PARAMETERS Parameters used in the source term calculations to indicate the performance characteristics of the primary coolant system are provided in Table 3.2-1 and Appendix A. Those parameters include such items as reactor power level, mass of coolant, letdown rate, and letdown demineralized decontamination factors. 3.2.2 SECONDARY SYSTEM PARAMETERS Parameters used in the source tem calculations to indicate the performance characteristics of the secondary system are provided in Table 3.2-1 and Appendix A. These parameters include such items as the masses of liquid and steam in the steam generators, total steam flow rate, total mass of secondary coolant, steam generator partition factors, main condenser / air ejector partition factors, and condensate demineralized performance para-meters. 3-1 TERA CORPORATION
Table INPUT DATA = EFFLUENT 3 Original Calvert Cliffs Value NRC (AEC) Evaluation f input Data Item from ER/SAR (One Unit) Value FES/SER 1 A. Parameters built into code:
- 1. Plant capacity factor 0.80 0.80
- 2. Radionuclides concen- Failed fuel = 0.1% Failed fuel = 0.25%
trations in primary Primary to seconoary leak = Primary to secondary laak = coolant and main steam 50 gpd 20 gpd
- 3. Leakage to containment 150 gpd 120 gpd building ;
I
- 4. Containment building'~ 12/yr (for 6 hours) 12/yr Purge Frequer!.y 3 cold shutdowns l' 5, Primary system volumes 14/yr 14/yr )
I degassed per year l l 6. Auxiliary building 200 gpd 20 gpd ] leakage (1.0% of PCA)
- 7. Steam Generator par- 0.002 N/P tition factors (recircu- 0.0002 lating U-tube)
- 8. Main condenser / air 0.005 N/P ejector partition fac tor for iodines
- 9. Containment internal 5 hours of operation 5 hours of operation cleanup (recirc.) DF = 100 for iodine Airborne iodine reduced to . 0% of initial value l system (2) DF = 1000 for particulate
- 10. Radioactive particulate See Amendment 1 to E.R. N/P Supplement 3/13/72, Table 4.1 l
w TI l 4 APERTURE CARD l Also Avdlable Om Aperture Nd L.____.__-.._
I- 1 6R' ISOTOPIC RCE TERi4 TERA Evaluation Value NRC Reg. Cuide Value (Recommended) Notes
. m .
_c- - - _ - asummm 1 0.80 0.80 ea NUREG OC17. Tables 2-2 A.G. Arough 2-8 (same as ANSI )>237 ) . ' ailed fuel = 0.12% _ _C%/ day of primary coolant sbie gas inventory; 0.001%/ day 8 R G-7 iodine invr:ntory
) 4 purges /yr during shutdown 1) 4 purges /yr for shutdowns ) ) Operating purges based on 2) 20/yr operation (1) (1) Tech specs allow 24 hours per I applicant's design quarter for plant ource I 1 ) 2/yr for cold shutdown 1 2/yr for cold shutdown l
- ) Plus volumes degassed by 2 Plus 14/yr for continuous stripping j continuous stripping 160 lbs/ day R.G.
ertition factor 0.0075 for @ dine @ dine 0 01 i R.G. lan-volatiles 0. 0 01 ).15 for volatile R. G. ).0 for non-volatile G hours of operation 16 hours of operation (2) Engineered Safety System )F = 10 for iodine R.G. for DFs and mixing f = 100 for particulate efficiency Mxing efficiency 70% R.G. ; BUREG 301~7 rable 2-18 Notes N/P = Not Provided N/A = Not Applicable indicates no value provided or required R.G.= Reg, Guide 1.112 and NUREG 0017 PCA = Primary Coolant Activity O lO04 - TERA CORPORATION
% % Table 3.2 a INPUT DATA-EFFLUENT -l i:
I Original Calvert Cliffs Value NRC (AEC) Evaluation Input Data Ite'" Value FES/SER l from ER/SAR (One Unit) _ , ,- .m 1
- 11. Decontamination N/A N/P Factors for CondensateDemin.(3,4) )
I 12. Primary Coolant Anion Cs,Rb Other N/P
! Purification Sys. Dem(5,,
100 100 100 l 13. Releases of radio- N/P N/P active material in liquid waste from Turbine Bldg. floor drains
- 14. Non-volatile par- N/P N/P titioning in moisture separators
- 15. Condensate Demin. N/A N/P Regeneration Assumptions
- 16. Adjustments to liquid N/p Liquids normalized to source term for an- 5.0 Ci/yr.
ticipated operational occurrences
=
- 17. Steam leakage rate to N, P N/P the Turbine Bldg. (6)
TI g APERTURE CARD Also .Availabic Om
Aperture Card
1(continued) y PWR IS0 TOPIC OURCE TERM NRC Reg. Guide Value TERA Evaluation Value (Recommended) Notes Anion Cs,Rb Other Deep Bed 10 2 10 N/A (3) Regeneration frequency is zero for powdex filter / Powdex 10 2 10 demineralized Mixed Bed 10 2 10 R.G. (4) Condensate demin. not used (Li,803) to clean-up fission products Plant will shut down to Cation 1 10 10 plug S.G. leaks. 7200 gpd at main steam R.G. (5) Letdown demin, only; { activity full 40 gpm flow. 35% in main steam removed R.G. after HP Turbine. (They follow extraction steam used to preheat feedwater.
- 1) Liquid has main steam N/A activity
- 2) All activity is removed from resins
- 3) 3400 gpd of chemical regenerant
- 4) Regenerant waste activity accounts for decay and daughter buildup in resins.
- 1) Increase calculated source by 0.15 Ci/yr/ unit with R.G.
same isotopic distribution
- 2) Evaporators unavailable for 2 consecutive days a ,
week for maintenance 1700 lbs/hr at main steam activity R.G. (6) Releases may be reduced by Iodine partition factor 1.0 a factor of 5.0 if clean steam seal or if vacuum leakoff is used. TERA CORPORATION
- _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ __ _ T - _ - _ _
Table 3.2 - INPUT DATA EFFLUENT' Original Calvert Cliffs Value NRC (AEC) Evaluation input Data item fromER/SAR(OneUnit) Value FES/SER B. Input Parameters 1 l
- 1. Reactor Name Calvert Cliffs Calvert Cliffs
- 2. Thermal power level 2560 MWt 2560 MWt i (MWt) at safety evaluationlevel(7) 3
- 3. Mass of coolant in 3 11,101 ft N/P primary system (10 lbs)
- 4. Primary system letdown 40 gpm -40 gpm rate (gpm, avg.)
- 5. Letdown cation N/A N/P demineralized flow rate (gpm, annual average)
- 6. Number of steam 2 2
- generators
- 7. Total steam flow 11.27 N/P (106lb/hr.)
- 8. Mass of steam in N/P N/P each stem generator (103 lbs)
- 9. Mass of liquid in N/P N/P each steam generator (103 lbs) _
- 10. Total mass of N/P N/P secondary coolant (103 lbs)
- 11. Steam generator 1.0 gpm 1.0 gpm blowdown rate and Anion demineralized blowdown treatment l
method (1bs/hr) W lI C_________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
(continued) " "' " PWR IS0 TOPIC URCE TERM TERA Evaluation Valae NRC Reg. Guide Value (Recorrmended) Notes Calvert Cliffs 2700 MWt ( 7) Adjust all power dependent parameters to this level 470.2 3 40 gpm N/A 2 11.27 6.4i 217.6 2082.5 ih 'j. Blowdown rate R.G. g as fraction
'y of main steam 0.2% of main s*eam flow 'fg ! ',. U-tube flow (volatile chem.'stry) +g3
- ,i Volatile SAR/ER value CAftD 1, chemistry ce r Mao AvailaMe O.
, i. Aperture Card t
Once-throuah S.G. - N/A ; L TERA CORPORATION---
~
~~._ ' Table 3.2-INPUT DATA EFFLUENT Original Calvert Cliffs Value. NRC (AEC) Evaluation input Data Item from ER/SAR (One Unit) Value FES/SER
- 12. Condensate deminer- N/A N/A alizer regeneration time
- 13. Fraction of feedwater N/A N/A through condensate demin.
- 14. Plant dilution flow, N/P 5490 cfs average (103 gpm)
- 15. Liquid Radwaste Treatment System Input Parameters for six (6) inlet streams:
- a. Shim Bleed Provide information Provide information
- b. Equip. Drain Waste specified in 16 thru 18 specified in 16 thru 18
- c. Clean Waste
- d. Dirty Waste
- e. Blowdown Waste
- f. Regenerant Mastes
- 16. For 15a through 15f: Flow Fraction
- 1. hame of waste stream S urce Rate of PCA 1. N/P
- 2. Flow rate of inlet 1) Pri-stream (gpd) mary 2. N/P
- 3. Activity of stream ant
- 3. N/P as fraction of P
TWM ac y a) Letdown 40 gpm 1.0 b) Equip. 120 gpm 1.0 Note ( 8) drains
- 2) Misc.
Wastes 4000 gpm a) compo- N/P nent Drains b) Equip- N/P ment w Drains a c) Blowdown N/P d) Sample N/P Drains
- e) Lab drains N/P
~ . -
}l(continued) >"" PWR ISOTOPIC lURCE Q TERM 1 l TERA Evaluation Value l NRC Reg. Guide Value (Recommended) Notes l l Deep-bed - 3.5 day frequency per demineralized times number of demins. , (7 day frequency for N/A ! ultrasonic resin cleaning.) I Powdex Filter /Demin. - N/A N/A l 1200 per unit P Provide information Provide information specified in 16 thru 18 specified in 16 thru 18 Flow Rate Fraction Flow Fraction
.. Source (gpd) of PCA Source M of PCA (8) Recommended values provided by plant staff.
Contat. 40 1.0 Shia 400 1.0 Bldg. Bleed . (g) All clean wastes included in Sump Equip. 2600 0.6 shim bleen and equip. drains, Aux. Bldg. 200 0.1 Drains Fir. Drain Clean ( 9 ) 0.0 0.0 Lab. Drain 400 0.002 Dirty 7000 0.015 Dr B1 wdown (calculated by code) Regenerant 0.0 0.0 Tr 7200 Calcula.ted Drain CARD Misc. 700 0.01 D rgent AQAggg Aperture Card TERA CORPORATION
._ __ _I_ _
1
'"' ^ 2-TablebA1,Ao INPUT
. EFFLUENT M c
Original Calvert Cliffs Value 'I NRC (AEC) Evaluation 1 Input Data Item from ER/SAR (One Unit) Value FES/SER 1 2 3
- 17. For 15a through 15f' Reactor SE3 2.5E4 2.5E4 ,
- 1. DF for iodine Waste ), gjp Treatment ,
4
- 2. DF,for CS and Rb 2* N/P I
Miscellaneous 1E4 SE4 SE4 !
- 3. OF for others Waste Treatment 3. N/P
' * - ' (overall' system DFs) ]
- 18. For 15a through 15f:(10) ,
- 1. Waste collection N/P 1. N/P time (days) prior to processing
- 2. Waste processin9 N/P 2. N/P and discharge times (days) s
- 3. Average fraction N/P 3. N/P '
of wastes to be discharged after processing
- 19. Letdown system Continuous Continuous (identify continuous or not continuous)
- 20. Xenon holdup time 60 days 60 days for stripped g, fissiori gases (days) __
- 21. Krypton holdup 60 days 60 days time for stripped fission gases (days)
- 22. Fill time for N/P N/P system (days)
- 23. Waste gas particulate HEPA - No HEPA - No releases (HEPA filter, "yes" or "no")
- 24. Auxiliary Bldg. Charcoal - No Charcoai - No gaseous releases (charcoal and HEPA HEPA - Yes HEPA - Yes filters, "yes" er "no")
y ' 0%
a it k [hhihk k =-
~
RCE TERM i T i TERA Evaluation Value NRC Reg. Guide Value (Recommended) Notes Source Halogens Cs,Rb Other Shim 1E07 4E05 1E08 l lystem decontamination Equip. 1E07 4E05 1E08 I hetr g see NUREG 0017 Dirty 1E05 4E01 1E05 Blow- '1E02 1E01 1E02 down j i Shim
& Dirty $ee NUREG 0017 for calc. Equip. Waste Blowdown (10)Recommendedvalues methods. provided by plant
- 1. 24 .46 (Recirculated staff.
to condensate TI
- 2. 9.7 7.2 system)
' APERTURE
- 3. 1. 0 1.0 CARD Also Available On Aperture Card Continuous 60 days 60 days f
1 i 30 days J Yes Charcoal - No l HEPA - Yes l TERA CORPORATION 4 2'?O9/OOVVV-0
^
Table 3.2 -
' ~ ~
INPUT DATA a EFFLUENT 3 Original Calvert Cliffs Value NRC (AEC) Evaluation Input Data Item from ER/SAR (One Unit) Value FES/SER 6
- 25. Containment free 2.0 X 10 N/P volume (106 ft3)
- 26. Containment internal 1. 0.10% failed fuel 1. N/P cleanup system flow rate (103cfm) 2. No 2. N/P
- 3. 5 hours 3. N/P
- 4. Iodine DF = 100 4. N/P Particulate DF = 1000 Mixing efficiency = N/P
- 5. N/P 5. N/P 20,000 ctm - 60,000 cfm
- 27. Containment Bldg.
Iodine Releases - 1. Charcoal - No 1. Charcoal - tio High Volume Purge (exclusive of 2. HEPA - Yes 2. HEPA - Yes recirc.) (Charcoal. HEPA 3. 12 purges /yr 3. 12 purges /yr filters, "yes" or "no") Number of purges per year during operation
- 28. Containment Bldg. N/A N/P Iodine Releases -
Low Volume Purge l (exclusiveof I recirc.) Continuous Venti-lation flow rate (cfm) (Charcoal.HEPA filters, "yes" or "no") Y w
'M W
7m
.m -~
7 7
'1 ,
} L (continwtif - @WR ISOTOPIC o - URCE TERM .
, i 1
TERA Evaluation Value i , NRC Reg.' Guide Value (Recommended) Notes '!
- nummmmmmmmmmmmmmerm-wmen- _ a mmmmmmmmmmm mmmmmmune 2.0 m
- 1. Primary coolant iodine l !
leakage rate = 0.001% 1. R.G. l ! per day I '
, j
- 2. Continuous normal 2, flo ventilation flow of i
1000 cfm .
- 3. 16 hours cf operation 3. 16 hours prior to purge
- 4. Iodine DF = 10 4- fL G.
Particulate DF = 100 Mixing efficiency = 70% B. Continuous primary 5. R .. G. ' coolant leakage durir,9 Flow rate = 60,000 cfm ' system operation l
- 1. Charcoal - No
- 2. HEPA - Yes . j
-- i
- 3. 4 cold shutdevns
, 20 operat.!onal purges ..,
~
a ; I I N/A f t
- v j
}
}
l } lT v 7 i
) ,
t _ ._w _ _w== t j
.g .
APERTURE u ;
/ CARD .
i Also Asakkle On ; Aperfere Car /*i TERACORPORATION #. i
,c , . - P, 4 i
~
( '
Table 3.2 - INPUT DATA < EFFLUENT 1
~
Original Calvert Cliffs Value NRC (AEC) Evaluation Input Data item from ER/SAR (One Unit) Value FES/SER
- 29. Steam generator blowdown tank ver.. Vent to condenser Vent to condenser q
- 1. No treatment l
- 2. Vent to t.ondenser
- 3. Vent to air ejector
- 4. Once-through steam generator
- 30. Fraction of Iodine Charcoal filter - Chercoal Filter -
released from the condenser air ejector No No offgas treatment l system (with or without charcoal adsorber) On-site laundry On-site laundry n te 1 u r,
" " " No treatment No treatment ysteim 1
Y m i
%ehne
) I(continued) -
- PWR ISOTOPIC IURCETERM TERA Evaluation Value NRC Reg. Guide Value (Recommended) flotes i
Vent to condenser No On-site laundry No treatment 1 w l l N
- APERTURE CARD Alm AnJh,hle On Aperfure Card TERACORPORATION
~~
2'?O 9/OOW5L/3
3.2.3 LIQUID RADWASTE PARAMETERS Parameters used in the source term calculations to indicate the performance characteristics of the various systems which handle and contribute to liquid radwaste sources are provided in Table 3.2-1 and in Appendix A. Additional l design data and flow diagrams are provided in Section 2.1 of this report. { Figures 3.2-1, 3.2-2, and 3.2-3 describe the derivation of total decontamination ' factors for the shim bleed, miscellaneous waste,and steam generator blowdown sys tems , respec ti vely. 3 { 3.2.4 GASE0US RADWASTE PARAMETERS Parameters used in the source term calculations to indicate the performance characteristics of the system which collects, stores and releases radioactive gaseous products are provided in Table 3.2-1 and in Appendix A. Additional , design data and flow diagrams are provided in Section 2.2 of this report. l 3.2.5 VENTILATION PARAMETERS Parameters used in the source term calculations to indicate the performance j characteristics of the various ventilation systems which process plant effluent 1 air are provided in Table 3.2-1 and in Appendix A. Additional design data 1 and flow diagrams are provided in Section 2.3 of this report. I
- 3. 3 D_ES UIPTION OF CALCULATIONAL MODEL l
The calculational model used to determine the radioactive gaseous and liquid ! source terms for the Calvert Cliffs Facility is based on Regulatory Guide 1.112 l " Calculation of Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Power Reactors," American National Standards Source ' Term Specification N237, " Radioactive Materials in Principal Fluid Streams of Light-Water-Cooled Nuclear Power Plants," and the GALE computer code which ! implements thpcq guides and standards. (The GALE code description may be found j inNUREG-0017d>). i i i The model develops primary and secondary coolant fission, corrosion,and activa-tion product concentrations including letdown and leakage effects; evaluates various liquid radwaste streams including shim bleed, equipment drain, clean waste, dirty waste and regenerant waste; accounts for the individual system decontamination and holdup effects; includes miscellaneous liquid losses such as turbine building drains and detergent wastes; and evaluates gaseous releases from gas stripping, building ventilation paths and the air ejector. l 3-9 l TERACORPORATION
Figure 3.2-1 Decontamination Factors for , Shim Bleed and Equipment Drains (I DF's Halogens Schematic Equipment Item (Anion) Cs,Rb Other
, i EE E 23 mm ' 2 o
1 [ I I l F Filter 1 1 1 { Degassifier 1 1 1 j
)
D Primary coolant letdown 10 2 10 1 cemineralizers (mixed-bed, D non-regenerable) 10 10 10 3 T Tank (receiving) 1 1 1 I i
- I 2 3 3 E Evaporator (vacuum)(2) 10 10 10 1
1 T #11 Tank (monitorino) 1 1 1 J 2 2 i D Radwaste Demineralizers 10 2 10 j (mixed-bed,non- 3 D regenerable) 10' 10 10 T #12 Tank (monitoring) 1 1 1 Total DF 1 x 10 7 4 x 105 1 x 10 8 1 to circ. water 3-10 TERA CORPORATION i
l l l Figure 3.2-2 Decontamination Factors for Miscellaneous (Dirty) Wastes DF's Halogens l Schematic Equipment Item (Anion) Cs,Rb Other l m! $
.E ';;
TC aC h b 14 m 5 g & R j, v> $ $ YYYY T Waste Receiver Tank F Filter 1 1 1 2 2 D Radwaste Demineralized 10 2 10 (mixed-bed,non-regencrable) l T #11 Tank (monitoring) 2 2 D' I Radwaste Demineralized 10 2 10 i (mixed-bed,non-D regenerable) 10 10 10 T- #12 Tank (monitoring) 1 1 1 Total DF'c 1 x 10 5 4 x 10 1 1 x 10 5 Y to circ. water 3-11 TERA CORPORATION
Figure 3.2-3 Decontamination Factors for Steam Generator Blowdown (3) i Halogens Schematic Equipment Item (Anion) Cs.Rb Other
^
J c 6 3 E
's e 8
2 V
^
cn e L *r= 4 B B# C, s- , E T< 9"
.!" 2 23 8t _e CD NGe By 3 G3 E88 Em ~e SE 3 "* $ S ,5 V V if F Filter 1 1 1 ]
i 2 2 D Demineralized 10 10 10 2 2 )
%b Total DF's 10 10 10 0.8 i
'; e
;3
.E $
" ?u e&
Y 3-12 TERA CORPORATION !
Notes to Figures (3.2-1,3.2-2,3.2-3) (1) Credit for 40 gpm letdown demineralized upstream of shim bleed point is taken in calculation of primary coolant activity. (2) Gaseous component f rom vacuum evaporator is processed by a con-denser and a deep bed charcoal filter before venting to plant vent. 4 Due to upstream demineralizers, condenser, and deep bed filter, this potential gaseous iodine source term is considered to be negligible. (3) Blowdown is curroatly released to circulating water or misce'llaneous radwaste. Future plans call for blowdown to be processed by a filter and demineralized and returned to the shell side of the feedwater , heater (to be implemented at first refueling). Blowdown tank vents 1 are returned to the condenser. This flow path has been evaluated according to the new design to be implemented. i l 3-13 TERACORPORATION
Methods and assumptions used to develop system decontamination factors, holdup times, and filter efficiencies are consistent with Regulatory Guide 1.112 and NUREG-0017. Liquid leakage assumptions for the primary and secondary coolant systems to the containment, auxiliary, and turbine buildings also follow the Regulatory Guide. Primary and secondary coolant fission product concentrations are calculated in pCi/ml, while effluent releases are calculated in Curies per year. 3.4 EVALU_ATION 0_F RESULTS The results of the radioactive liquid and gaseous effluent source term calculations for the Calvert Cliffs plant are presented in Tables 3.4-1 and 3.4-2, respectively. These source terms represent the expected annual releases of radionuclides for one unit operation and are used in the dose 4 calculations of Section 4.0 which follow. (The effluent release values of I the tables are multiplied by a factor of two to account for operation of j both Units 1 and 2.) i 3.4.1 LIQUID EFFLUENT RELEASES , i Table 3.4-1, Liquid Effluent Releases, indicates a calculated total adjusted i release (except tritium) of 0.62 Curies per year per unit, including deter- I gent waste releases. Approximately two-thirds of this source is the result j of miscellaneous waste releases, with most of the remainder resulting from j the " unplanned release" adjustment factor and detergent wastes. Primary } coolant radwaste system releases are negligible. This calculated source ' term is a factor of eight less than the Docket RM 50-2 annual design objective of 5 Ci/yr/ unit. ! Of the 0.62 Curies per year, approximately 0.58 Curies are cesiuni and barium isotopes. The next most significant isotope is 0.01 Curies of iodine-131. Based on the NRC model, 530 Curies per year of tritium are l estimated to be released via liquid pathways. This value is considered to be overly conservative when compared to the calculated Calvert Cliffs ! FSAR value of 682 total -curies of tritium released per unit per year for i the equilibrium cycle. (A value of 340 Curies per year per unit in liquid effluents was used as the evaluation basis in the dose calculations which follow. ) 3.4.2 GASEOUS EFFLUENT RELEASES From Table 3.4-2, Gaseous Effluent Releases, it is apparent that the holdup time for decay in the offgas system (60 days) and the use of HEPA and charcoal filters on important ventilation pathways greatly reduces the quantities of gaseous radioactive effluents released to the atmosphere. l l { 3-14 I TERA CORPORATION i
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The most significant noble gas isotopes are krypton-85 (1,900 Curies /vear mainly from gas stripping and reactor purge); xenon-131m (69 Curies / year, mainly from containment purge); xenon-133m (43 Curies / year, mainly from containment purge); and xenon-133 (6400 Curies / year, mainly from containment purge and auxiliary building ventilation). The total plant gaseous iodine source term is 2.2 x 10 -2 Curies / year and airborne particulate releases are negligible (approximately 2 x 10-3, Curies / year). Airborne tritium releases were calculated on the basis of two models. The first model used the assumptions provided in Regulatory Guide 1.112 and NUREG 0017 and resulted in a calculated airborne release of 540 Curies / year. The second model used as a basis the evaluation of tritium generation provided in the Calvert Cliffs FSAR and resulted in a calculated airborne release of 340 Curies / year (see Table 3.4-2). This latter number is used as the evalua- ! tion oasis in the dose calculations which follow. 3.4.3 ADJUSTMENT FOR OPERATIONAL OCCURRENCES It is expected that during the operation of a nuclear power plant certain events will occur which might result in the unanticipated release of small quantities of radioactive materials in addition to planned or " normal" re-leases. The magnitude of the radioactive effluent releases associated with these " operational occurrences" depends to a large degree on the contents of storage vessels and systems which may be unexpectedly released to the envi ronment. Reactor operating data over a 213 year period, January 1973 through June 1975, representing 102 reactor-years of operation were evaluated by the NRC staff to determine the frequency and extent of unplanned liquid releases. During the period evaluated, 27 unplanned liquid releases occurred,12 due to per-sonnel errors, 7 due to component failures, and the remainder due to miscel-laneous causes such as procedural errors and design errors. The findings indicated that approximately 0.15 Ci/yr/ reactor should be expected to occur as unplanned releases. The Staff considers the tanks most likely to be relcased to be low level monitor tanks and,therefore, the calculated liquid source term radionuclides distribution is applied to the releases. In the calculated liquid effluent source term and in the dose calculations which follow, the NRC adjustment for " operational occurrences" is included ) for each reactor unit (e.g., an addition of 0.30 Ci/yr to the total station 1 source term). I TERA CORPORATION
~
4.0 CALCULATION OF MAXIMUM INDIVIDUAL DOSES 4.1 IiGRODUCTION AND EVALUATION BASES
" Maximum individual" annual doses have been calculated for a variety of liquid and gaseous effluent exposure pathways representative of actual or potential usage conditions within a five mile radius of Calvert Cliffs Plant. The objective of these dose calculations is to demonstrate compliance with the design objective dose values of the NRC staff's pro-posed Appendix I given in Docket RM 50-2 (as appended to Appendix I via the September,1975 amendment).
Whenever possible, calculations were based on existing data for the Calvert Cliffs Plant and its regional environmental characteristics. Where in-sufficient data existed to substantiate plant / site dependent assumptions, parameters and models recommended in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," or Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the Purpose of Implementing Appendix I," were used. (The above Regulatory Guides are listed as References 6, 7, and 8 respectively. The following discussion of parameters, models, and resulting radiological impacts is intended to demonstrate consistency with the currently accepted philosophy and methods for evaluating routine releases of reactor effluents, as recommended in the applicable R69ulatory Guides. 4.2 IMPACT ASSUMPTIONS / PARAMETERS The following discussion provides specific information and/or references regarding the data used in the Appendix I dose calculations for the Calvert Cliffs Plant. Tables 4.2-1, 4.2-2 and 4.2-3 list these parameters and assumptions for the liquid effluent and gaseous effluent dose calculations. In addition, Apoendix A to this report contains substantial additional information regarding the meteorology, topography, dose receptor locations, and deposition effects assumed in these analyses. Radiation doses to the " maximum individual" were evaluated assuming two unit plant operations. Exposure to radioactive liquid effluents released from the plant was assumed to occur from consumption of fish and invertebrates (sheilfish), from shoreline silt, and from recreational activities including swimming and boating. Since Calvert Cliffs is a saltwater site, the drinking water and 4-1 TERA CORPORATION
I irrigation pathways were not considered. Exposure to radioactive gaseous effluents released from the plant was assumed to occur from air submersion (plume shine), froa inhalation and ground shine, and from deposition of radioactive particulate and iodines on food plants which have a pathway to man via ingestion of the plants directly or by ingestion of animal products including milk and meat. 4.2.1 EFFLUENT RELEASE POINTS All plant gaseous effluents were assumed to be released from a single release point, the Unit 2 main plant vent. The characteristics of this vent are described in Table A-6 of Appendix A. (At the receptor distances of interest, the Unit 1 and Unit 2 plant vents appear to have essentially the same character-istics from a meteorological standpsint.) Gaseous effluent releases were evaluated using two methods; the first assuming realistic elevated release characteristics with fumigation but no wake dilution effect, consistent with the model of Regulatory Guide 1.111, Section C.2.6 (7); the second assuming ! a highly conservative ground level release with wake dilution and an open l terrain effect consistent with Regulatory Guide 1.111. The " straight-line i trajectory" model of Regulatory Guide 1.111 was used in both instances. A j detailed description of the methods used is provided in Appendix A. j All plant liquid effluents were assumed to be released on a batch basis, diluted in a total plant dilution flow of 5400 cfs, and released to Chesapeake Bay where further dilution occurs. l 4-2 TERA CORPORATION
1 Table 4.2-1 INPUT PARAMETERS AND ASSUMPTIONS: ALARA " MAXIMUM INDIVIDUAL" LIQUID DOSE CALCULATION 4 l l G_EN_ERAL PARAMETERS l
)
- 1. Plant type - PWR, saltwater site 1
- 2. Total plant liquid discharge - 5400 cfs (ref. #1) '
- 3. 50-mile total population 2.31 x 100 (ref. #1) 1 l 4. Fraction of adult - 0.66 (ref. #6) .
1
- 5. Fraction of teenager - 0.14 (ref. #6) i
)
- 6. Fraction of child - 0.20 (ref. #6) j
- 7. Isotopic source terms - from Section 3.4 and Table 3.4-1
- 8. No reconcentration of liquid radioactive effluents occurs at the Ca? vert Cliffs site. l ALARA DETERMINATION
- 1. Standard usage and consumption factors - based on NRC Regulatory Guide 1.109, Table A-2.
- 2. Shore width factor (nominal ocean site) - 0.5 (R.G. 1.109)
- 3. Dilution for aquatic foods - 5.0 (prompt dilution near surface,R.G.1.109)
- 4. Diiution for shoreline - 5.0 (prompt dilution near surface, R.G. 1.109)
- 5. Discharge transit time - 0.01 hours (assumed)
- 6. Transit time to receptor - 24.0 hours (ref. #4) 4-3 TERA CORPORATION !
-l
Table 4.2-1 (continued) , _SPECIAL LOCATION " MAXIMUM INDIVIDUAL" (Swimming, boating, high shcreline activi+ c)
- 1. Usage and consumption factors - based on NRC Regulatory Guide 1.109, Table A-2 together with 100 hours swimming activity (ref. #4).
- 2. Dilution to special location - 5.0 (same as ALARA receptor)
- 3. Transit time to special location - 24.0 hours (ref. #4)
- 4. Shorewidth factor (nominal ocean site) - 0.5 (R.G.1.109)
OT_HER LIQU_ID DOSE PARAMETERS _
- l. Adult, teenager, child, infant ingestion dose factors from Regulatory Guide 1.109, Tables A-3, A-4, A-5, A-6, respectively.
- 2. Bioaccumulation Factors from Regulatory Guide 1.109, Table A-8.
- 3. External dose factors for standing on contaminated ground (shoreline) from Regulatory Guide 1.109, Table A-7.
1 4-4 TERA CORPORATION
i Table 4.2-2 INPUT PARAMEltRS AND ASSUMPTIONS: ALARA " MAXIMUM INDIVIDUAL" GASE0US DOSE _ CALCULATION i GENERAL PARAMETERS _
- l. Fraction of fresh leafy vegetables grown locally - 1.0 l
- 2. Fraction of the year milk cattle, goats and beef cattle are on pasture - 0.75
- 3. Fraction of the vegetation intake grown in garden - 0.76 4 Fraction of the daily intake of animals derived from pasture ,
while on pasture - 1.0 I
- 5. Air-water concentration - 8.0 g/m (The above are NRC " default" parameters, ref. #6, except for the fraction of year on pasture, ref. #4.)
- 6. Isotcpic source terms - from Section 3.4, and Table 3.4-2.
- 7. Dose factors for noble gases and daughters from Regulatory Guide 1.109, '
Table B-1. '
- 8. Adult, teenager, child, infant inhalation dose factors from Regulatory Guide 1.109, Table C-1, C-2, C-3, C-4, respectively.
l 9. Stable element transfer data from Regulatory Guide 1.109, Table C 10. Open terrain correction factor for X/Q from Regulatory Guide 1.111, Figure 2.
- 11. Plume depletion effect for grcund level releases from Regulatory Guide 1.111, Figure 3.
- 12. Relative deposition for ground level releases from Regulatory Guide 1.111, Figure 7.
4-5 TERA CORPORATION
Table 4.2-2 (continued) SPECIAL LOCATION DATA, ELEVATED REl. EASE MAXIMUM RECEPT 0RS* Location #1_
- l. Name - Site Boundary l
- 2. Cardinal Compass Point - SE
- 3. Distance in miles - 0.80 l
-7
- 4. Normal X/Q (sec/m ) - 3.5 x 10 3
- 5. Decayed X/Q (sec/m ) - 3.5 x 10" i
- 6. Depleted X/Q (sec/m 3
) - 2,.9 x 10 -7
- 7. Deposition (m-2) - 5.9 x 10-9 Location #_2
- 1. Name - Resident j
- 2. Cardinal Compass Point - SE
- 3. Distance in miles - 1.3. ,
3 -7
- 4. Normal X/Q (sec/m ) - 2.1 x 10
- 5. Decayed X/Q (sec/m 3
) - 2.1 x 10 -7
~
- 6. Depleted X/Q (sec/m ) - 1.6 x 10
- 7. Deposition (m-2) - 2.4 x 10-9 3 l
c i
- All X/Q and deposition data is from Appendix A. !
I l 1 4-6 TERACORFORATION
l Table 4.2-2 (continued) SPECIAL LOCATION-DATA, ELEVATED RELEASE MAXIMUM RECEPT 0RS Mcation_ #3_
- l. Name - Milk Cow / Meat
- 2. Cardinal Compass Point - SW
- 3. Distance in miles - 4.17
- 4. 3 -8 Normal X/Q (sec/m ) - 3.6 x 10
- 5. Decayed X/Q (sec/m 3
) - 3.6 x 10 -8
- 6. Depleted X/Q (sec/m 3
) - 2.3 x 10 -8
- 7. Deposition (m-2) - 2.2 x 10-10 Location #4_
- l. Name - Garden
- 2. Cardinal Compass Point - S
- 3. Distance in miles - 1.78 l 4. Normal X/Q (sec/m ) - 1.6 x 10" 3
- 5. Decayed X/Q (sec/m ) - 1.6 x 10~7
- 6. Depleted X/Q (sec/m 3
) - 1.1 x 10 -7
- 7. Deposition (m-2) - 1.8 x 10-9 4-7 TERA CORPORATION 1
_ - . . - ~ _ _ _ _ . _ _ - - - . _ _ ___.-- _
Table 4.2-2 (continued) l Location #5 1
- 1. Name - Goat j i
- 2. Cardinal Compass Point - S j
- 3. Distance in miles - 5.00 (no goats within 5 miles of site) i
-8 j
- 4. Normal X/Q (sec/m ) - 6.3 x 10
- 5. Decayed X/Q (sec/m3
) - 6.3 x 10 -8 l
l 6. Depleted X/Q (sec/m 3
) - 3.9 x 10 -8 l
- 7. Deposition (m-2) - 3.5 x 10-10 l
4-8 TERA CORPORATION
1 l Table 4.2-3 1 1 SPECIAL LOCATION DATA FOR GROUND LEVEL RELEASE MAXIMUM RECEPT 0RS Location #1
- 1. Name - Site Boundary i
- 2. Cardinal Compass Point - SE
- 3. Distance in miles - 0.80
)
3 -6
- 4. Normal X/Q (sec/m ) - 7.3 x 10
- 5. Decayed X/Q (sec/m 3
) - 7.3 x 10 -6 j l
3
- 6. Deplete:1 X/Q (sec/m ) - 5.3 x 10-6
- 7. Deposition (m-2) - 4.4 x 10-8 i '
Location #2
- 1. Name - Resident
- 2. Cardinal Compass Point - WNW
- 3. Distance in miles - 0.93 3 -6
- 4. Normal X/Q (sec/m ) - 4.0 x 10 3
S. Decayed X/Q (sec/m ) - 4.0 x 10-6
- 6. Depleted X/Q (sec/m 3
) - 3.2 x 10 -6
- 7. Deposition (m-2) - 1.2 > 10-8
*All X/Q and deposition data is from Appendix A.
4-9 i TERA CORPORATION
l
)
Table 4.2-2 (continued) ;
~ GROUND LEVEL RELEASE
} i Location #3
- 1. Name - Milk Cow / Meat
- 2. Cardinal Compass Point - SW f i
- 3. Distance in miles - 4.17 ;
1 4. 3 -7 Normal X/Q (sec/m ) - 1.9 x 10 3
- 5. Decayed X/Q (sec/m ) - 1.9 x 10-7
- 6. Depleted X/Q (sec/m 3
) - 1.3 x 10 -7 i
- 7. Deposition (m-2) - 3.9 x 10-10 i l
Location #4
- 1. Name - Garden
- 2. Cardinal Compass Point - WNW
- 3. Distance in miles - 0.95 4.
3 -6 Normal X/Q (sec/m ) - 3.8 x 10
- 5. Decayed X/Q (sec/m 3
) - 3.8 x 10 -6 3
- 6. Depleted X/Q (sec/m ) - 3.1 x 10-6
- 7. Deposition (m-2) - 1.1 x 10-8 4-10 TERA CORPORATION
Table 4.2-2 (continued) GROUND LEVEL RELEASE l Location #5
- 1. Name - Goat i
- 2. Cardinal Compass Point - SE
- 3. Distance in miles - 5.00 (no goats within 5 miles of site) j 4.
3 -7 Normal X/Q (sec/m ) - 1.8 x 10
- 5. Decayed X/Q (sec/m 3
) - 1.8 x 10-7 3
- 6. Depleted X/Q (sec/m ) - 1.2 x 10-7
- 7. Deposition (m-2) - 5.8 x 10-10 l
I 4-11 TERA CORPORATION
4.2.2 METEOROLOGICAL MODELS/ PARAMETERS j A detailed discussion of the meteorological data and models used in these evaluations is provided in Appendix A of this report. One full year of data (January 1975 - December 1975) was reduced and employed to develop joint frequency distributions by Pasquill Category and X/Q's for both elevated and ground level release mechanisms based on the " straight-line trajectory" l model of Regulatory Guide 1.111, Section C.1.C, as discussed in Section 4.2.1 I above. Open terrain correction factors, plume depletion factors, and deposition values were obtained as necessary from the appropriate sections of Regulatory Guide 1.111. Comprehensive joint frequency distribution tables and X/Q tables j for ground level and elevated releases at selected receptor points (0-5 miles 1 for ground level releases, 0-3 miles for elevated releases) are presented in j Appendixes B and A, respectively. l I 4.2.3 HYDROLOGICAL PARAMETERS (DILUTION) For liquid effluent batch releases from the Calvert Cliffs Plant, dilution in the total condenser cooling water discharge of 5,400 cfs was assumed. No reconcentration effects occur at the site. A factor of 5.0 for prompt dilution of the total plant discharge near the surface of a large body of water (Chesapeake Bay) was assumed, based on provisions of Regulatory Guide 1.109. Shoreline activities, swimming, boating,and fish consumption were assumed to be performed using radioactive liquid effluent diluted by these factors. 4.2.4 LOCATION OF MAXIMUM INDIVIDUAL RECEPT 0RS The locations of maximum individual receptors for radioactive gaseous effluents were determined by a recent survey performed by BG&E. These i locations are provided in Appendix A, Tables A-2, A-3, A-4 and A-5. No i goats exist within 5 miles of the site. Until early June 1976, milk cows existed at a single location approximately 4.2 miles from the plant site in the southwest sector. Although these animals were sold at that time, this location was evaluated as a potential location for milk cows in the analyses which follow. Meat animals still exist at this location, however. No credit was taken for radioactive decay during travel time from the plant vent to the receptors for gaseous effluents. Individuals exposed to plant liquid effluents were assumed to conduct their activities on the shoreline of Chesapeake Bay near the plant site, and thus do not receive the benefit of effluent dilution in the total Bay flow. 4.2.5 USAGE AND BI0 ACCUMULATION FACTORS These parameters were obtained directly from Regulatory Guide 1.109 and implemented as library data in dose computation codes. 4-12 TERA CORPORATION
I i 4.2.6 DOSE FACTORS, STABLE ELEMENT TRANSFER DATA These parameters were obtained directly from Regulatory Guide 1.109 and ; implemented as library data in the dose computation codes.
4.3 DESCRIPTION
OF CALCULATIONAL MODELS The calculational models used to evaluate dispersion of liquid and gaseous effluents in the environment and the resulting annual doses to selected receptors are based on Regulatory Guides 1.109 and 1.111, and the GASPAR and LADTAP computer codes which implement these guides. The " Straight-Line Air Flow" model described in Regulatory Guide 1.111, equation (3) was used in conjunction with the meteorological data of Appendix A to derive plume dispersion parameters (X/Q) to be used with the gaseous ef-fluent dose code. The individual dose equations from Appendixes A, B,and C of Regulatory Guide 1.109 were used to derive the annual exposure for appro-priate maximum individuals from liquid and gaseous effluents. These calculated maximum individual doses are presented in Section 5.0 and are evaluated with respect to the appropriate annual design objectives. l i 4-13 TERA CORPORATION
]
5.0. EVALUATION OF PLANT RADIOLOGICAL j IMPACT - CONCLUSIONS i ju 5.1 CALCULATED PLANT RADI0 ACTIVE EFFLUENT RELEASES
.The calculated annual radioactive liquid and gaseous effluent source terms are presented in Tables- 3.4-1 and '3.4-2. . These values represent expected plant performance based on actual system configurations and conservative decontamina-tion, holdup and discharge parameters.- Adjustments to the calculated liquid effluent value for " anticipated operational occurrences" should be commensu-rate with the design bases and capabilities of the plant systems and the plant operating design basis for liquid effluent releases. The NUREG 0017dd just- 1 ment factor of 0.15 Ci/yr/ unit appears to be consistent witn.the desi,qn !
capability of the Calvert Cliffs Plant. 1 1 5.2 CALCULATED PLANT RADIOLOGICAL IMPACT ON MAXIMUM EXPOSED INDIVIDUALS
,1 5.2.1 DOSES RESULTING FROM RADI0 ACTIVE LIQUID EFFLUENT RELEASES ]
I Maximum individual (ALARA) doses, based on the calculated liquid effluent i source term from Table 3.4-1, are presented in Table 5.2-1.. These doses were .J computed for the individual who lives near the plant and therefore spends a significant amount of time at shoreline activities, swimming and boating, and also eats fish and invertebrates which live in diluted plant effluent. The resulting maximum total body dose is 4.3E-03 mrem /yr to an adult. The i maximum calculated organ dose is 7.0E-03 mrem /yr to the liver of a teenager. The most significant contributors to the doses are the isotopes of cesium. Tritium was determined to contribute less than 3% to the various " calculated ., doses. ' i An evaluation of the significance of these liquid effluent doses with respect to the annual design objectives of Appendix I and Docket RM 50-2 is presented in Section 5.3. f 5.2.2 DOSES RESULTING FROM RADI'0 ACTIVE GASE0US EFFLUENT RELEASES Doses due to radioactive gaseous effluent releases have been computed for a realistic elevated relene model and for a highly conservative ground -l 1evel release model at receptors including the p1w.t Site boundary, the nearest resident, the nearest- potential milk cow / meat" animal location and . the nearest (or maximum exposed) garden. The following paragraphs, describe ' the results of the calculations. d j I j 5-1 i _ TERA CORPORATlON !i q
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- 2. l.
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5.2.2.1 Site Boundary Doses Annual beta and gamma air doses were computed for both elevated and ground level release models. The calculated air doses resulting from the elevated release model were 0.24 mrads/yr beta and 0.06 mrads/yr ganma at a distance of 0.80 miles in the southeast sector. The calculated air doses resulting from the ground level release model were 4.9 mrads/yr beta and 1.2 mrads/yr gamma at a distance of 0.80 miles in the southeast sector. 5.2.2.2 Nearest (or maximum exposed) Resident Doses Doses for the maximum exposed resident are dependent on the model chosen for gaseous effluent release. The calculated annual total body, skin, and thyroid inhalation doses for the elevated release model were 0.027 mrem /yr, 0.09 mrem /yr,and 0.021 mrem /yr, respectively to a resident located 1.33 miles southeast of the plant. The calculated annual total body, skin and thyroid inhalation doses for the ground level release model were 0.52 mrem /yr,1.8 mrem /yr and 0.46 rem /yr, respectively to a resident located 0.93 miles to the west northwest. Table 5.2-2 summarizes these dose estimates. 5.2.2.3 _ Nearest Garden and Milk Cow / Meat Animal Doses , Tables 5.2-3 and 5.2-4 list the calculated total body and organ doses re-sulting from the elevated release of gaseous effluents at the nearest gar-den and milk cow / meet animal location, respectively. The total body and skin doses shown are substantially less than those calculated for the nearest resident (see 5.2.2.2 above). The maximum calculated organ dose for these , pathways is shown to be the infant thyroid dose resulting from milk consump- ' tion 0.65 mrem /yr. All other organ doses are less than this value at both locations. The infant thyroid dose from milk consumption using the ground level release < model for the gaseous effluents is 1.2 mrem /yr. (No goats exist within five l miles of the plant site; thus, this pathway was not considered in these l eveiuations). An evaluation of the significance of these gaseous effluent doses with respect to the annual design objectives of Appendix I and Docket RM 50-2 is presented in Section 5.3 which follows. 5-3 TERA CORPORATION
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Tat.ie 5.2-2 ! Dose to Nearest Resident from ' Calvert Cliffs Gase.':/V E)fp)iqat j Releasq. (:Prem/yr) M k Elevat.e_d Release Model (3) Source Total goA Thyroid Skin Plume (4) 2.0E-02 2.0E-02 8.8E-02 l Groend(5) 2.2E-03 ?.2E-03 2.6E-03 Inhalation 4.5E-03 2.1E-02 4.4E-03 Ground Levri Pelette Model (6) Source Total Body - Thyroid r Skin l 1 Plume (4) 3.7E-01 3.7E-01 1.7E+00 Ground (5) 1.1E-02 1.1E-02 1.3E-02 i Inhalation 1.4E-01 4.6E-01 1.3E-01 ; i e> I I (1) Sou ce term from Table 3.4-2; includes 340 Ci/yr/ unit tritium. j (2) Resident has no cow, goat or acrden.
/ i l
(3). Resident located at distance of 1.33 miles in southeast sector, i Noble gases only. I Iodine and ? articulates only. Resident located at distance of'0.93 miles in west northwest sector. , 1 I l i l l l i 5-4 i TERA CORPORATION I
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- l. 67.l. 9 9 11 13 3 1 1 91 2 1111 3 11 2 3
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, a e 34434 3 34434 3 }4434 3 3434 3 it M r 00000 0 00000 0 00000 0 0000 0 i
/ e - - - - - - - - - - - - - - - - - - - - - - - r w v EEEEE E EEEEE E EEEEE E EEEE E t o ) 4051 7 8 40743 3 40034 5 4047 5 C l iL - . t e 32717 5 3211 4 5 32224 6 3244 8 i k d n l o u i
M , / 4 M r
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s a i 5 e e C r l e a e 34544 3 34546 3 34536 3 3435 3 0 l e R e 00000 0 00000 0 00000 0 0000 0 4 b N n - - - - - - - - - - - - - - - - - - - - - - - 3 a d o EEEEE E EEEEE E EEEEE E EEEE E r T f e B 40348 5 0 40905 6 ;o o t 4012. l. 40.l. 4 7 dt a 321 26 4 321 46 4 3211 9 4 3221 5 ec n v me us io l a i s t F st a ( as c e o t c 34444 3 34444 3 nw L 34434 3 3434 3 oh a 00000 0 00000 0 00000 0 0000 0 i t t r - - - - - - - - - - - - - - - - - - - - - - - t u a T EEEEE E EEEEE E EEEEE E EEEE E ao _ - 40446 5 40672 1 40933 5 4095 0 rS _ s I . . e G t 32387 5 321 84 5 321 1 4 5 321 4 6 pn n oi r e ry u t sy/ l i e/s f nl sd f uid a E l ay mar s td 34444 3 00000 0 34434 00000 3 0 34434 3 00000 0 3434 3 o rm u oo - - - - - - - - - - - - - - - - - - 0000 0 w7 m
- - - - - t1 3 o TB EEEEE E EEEEE E EEEEE E EEEE E 20 e 40486 7 40993 s
a 406.l. 2 3 l. 0 0. l. 6 2 - 2
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- 4. o 4. 5 3 e2 o
r c = f en= l a e bt es e assa s n n n n Ti oE o y o o o o dD D a ki ki ki ki m r w l l t l t l t ot ri h d i t a d a d a iMl di a raiA t en Ml l en l en iMl l enMl l f A a mut e a mut a a mut a a mu a a d a meam P uoawh t uoawh t uoswh t uowh t l r eon o PGMCi T l reon o PGMCI T l reon o l ron o rtt m PGMCI T PGCI T eaea t cBG o elli c aa rsuu uwnn oonn
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5.3 EVALUATION OF CALCULATED ,00SCS Table 5.3-1 sunrnarizes the annual design objectives of 10CRF50, Appendix I, and the NRC staff's proposed Appendix I (Dccket RM 50-2, February 1974) snd compares these values to calculated values from Tables 3.4-1, 3. 4-2, 5.2-1, 5.2-2, 5.2-3 and 5.2-4. The following inportant items should be noted:
- 1. The cdiculated liquid effluent Jma gaseous iodine source terms are well below allowable limitsi.according to Docket RM 50-2. This source term was developed using' the methods and assumptions of Regulatory Guide 1.112 and NUREG 0017 including the 0.15 Ci/yr/
unit adjustment factor. As st.ch it is considered to be a conserva-tive representation of the operation of the Calvert Cliffs Plant, j 2. The calculated doses resulting from liquia effluents at the Calvert Cliffs site are well below the annual design objective values of Docket RM 50-2 (and Appenoix I). These doses have been calculated by methods consistent with Regulatory Guide assumptions, and as such are evaluated to be conservative, considering the liquid rad-waste system design and plant operating philosophy at Calvert Cliffs.
- 3. Gaseous effluent releases from the plant result in calculated doses well below the annual dose objectives of Docket RM 50-2 (and Appendix I). Since these doses were evaluated using the methods and assumptions of Regulatory Guides 1.,109 and 1.111, for both elevated and grouno level release models, they are considered to be conservative representations et the radiological impact of the plant on its environment.
57 TERA CORPORATION
r o a e t v
) v c 3 i a r e s ( l e o s fl e ( r t e f es / c h i va m m e e s a t l
eC e e CL e r m r i m ru d d a a m e m n m re/ n a td s r r r r r 1 h rna eue 7 C m m m m mC t vnl 4 0 2 7 1 s 0 0 6 3 7 2 0 l e e 2 9 s afi R C. 0 e C 0 0 0 1 4 1 T 0 l e b
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) r n n
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) ro 5 / e i / / a d 5bD 7 e M my ed r d d a a m
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B o ah gt ra d e i t t l OP D D l ) O P v m e a n r h t yH - r a. yl le e T o n A A i i o iSk AA nl s s p T ( (AA ( ( ( ( T ( (( e id b d y s n a 3 e n e t m s
) a u e 2 l i i 1* u t t s s s t t ic i i r t t r n t t n n e e r a e e u a g u u l l P n q l f f i f f f d d r f E E n u e E a l h s s c ig d u u e x o o n E H iuq e e i s s d ) )
i a a o 1 2 L C G I ( ( 1 2 A. B. B. C. I I II I I I UI I c c c c e e e e S S S S
i l 6,0 REFERENCES
- 1. Final Safety Analysis Report, Calvert Cliffs Nuclear Power Plant, f Units 1 and 2, BaltimBEe Sa5 and Electric Company, Docket Numbers J 50-317 and 50-318.
- 2. Environmental Report, Calvei t Cliffs Nuclear Power Plant, Units 1 arid f, Baltimore Gas and Electric Company, COCKet Numbers 50-317 f and 50-318. ]
- 3. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.112, l " Calculation of Releases of Radioactive Meterials in Gaseous I
and Liquid Effluents from Light-Water-Cooled Power Reactors," , April 1976, ! I
- 4. U.S. Atomic Energy Commission, " Final Environmental Statement, i Calvert Cliffs Nuclear Power Plant, Units 1 and 2," April 1973. I
- 5. U.S. Nuclear Regulatory Commission, " Calculation of Raleases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors," NUREG-0017, April 1976.
l
- 6. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, l
" Calculation of Annual Doses to Man from Routine Releases of l Effluents for the Puroose of Evaluating Compliance with 10CFR50, J Appendix I," March 1976.
l 7. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.111
" Methods for Estimating Atmospheric Transport and Dispergion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," March 1976.
- 8. U.S. Nuclear Regulatory Commission, Regulatory Gtfide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the Purpose of 1 implementing Appendix 1," May 1976.
5-1 TERA CORfCRATION
1 E I ll j l t I APPENDIX A j RESPONSES TO NRC LETTERS DATED FEBRUARY 19 and 25, 1976 REGARDING COMPLIANCE WITH REQUIREMENTS OF 10CFR50 APPENDIX I 4 1 1 TERA CORPORATION
I APPENDIX A / Introduction In response to the February 19 and 25, 1976 letters trom the Nuclear Regulatory ) Commission (NRC) to Baltimore Gas & Electric Cortpany (BG&E) regarding compli-ance with the requirements of 10CFR50, Appendix I and guidance for licensees required to file information with the Comission under the provisions of Section V.B of Appendix I, the following data is presented. This data incluties available information in the areas dtdined by Enclosures 1 and 2 of the NRC letters and is intended to fulfill the comitment made in flGSE's response to those letters, dated March 30, 1976. I i I l l l l I ! l ) A-1 TERACORPORATION
l 1 A.1 RESPONSES'TO' ENCLOSURE 1 b Guidance to Holders of Permits to Construct or Licenses to Operate Light-Water-cooled Reactors for which Application was Filed Prior to January 2,1971 to Meet the Requirements of Appendix ! to 10 CFR Part 50-Item 1 - Licensees should provide an evaluation showing .their facility's , capability to meet the requirements set forth in Section II of Appendix I to 10 CFR Part 50. Response - In response to the provision of Section V.B of 10 CFR 50,- > Apoendix I, BG&E has provided.in this report a coatprehensive and , conservative evaluation showing the capability of the'Calvert - Cliffs Nuclear Power Plant, Units 1 and 2. to meet the intent of j the requirements set forth in Section II of Appendix 1 and the guidelines of the NRC Regulatory Staff. set forth in Docket RM 50-2 (annexed to Apperedix I via the September 1975 amendment. Item 2 - Radioactive Source Terms used in the evaluation should be con - i sistent with the parameters and methodology set forth in Draft Regulatory Guides 1.BB or 1.CC (as appropriate). Note: For BW3s gaseous releases from the containment building and auxiliary building should be combined to form reactor building release for pre-BWR/6 Mark III Containment designs. l Resp _onse - Radioactive source terms used in the Calvert Cliffs Appendix I - evaluation are consistent with the parameters and methodology set forth in Draft Regulatory Guide 1.BB, " Calculation of Releases of Radioactive Materials in Liquid and Gaseous Effluents from - ! Pressurized Water Reactors (PWR's) (now Regulatory Guide 1.112)' See the text of this report and Section A.2 Of this Appendix for-details and specific references. i A-2 j TERA CORPORATION
l l l
)
l Item 3 - Meteorology / Hydrology information used in the calculation of doses should be consistent with Draft Regulatory Guides 1.DD 1 and I.EE. Response - The Calvert Cliffs site has a meteorological tower consistent l with the recommendations and intent of Regulatory Guide 1.23, and 12 months of data (1/75 - 12/75) were employed in the cal-ctilation of do:;es. The meteorological dispersion modal used l in the dose calculations was the " Straight-line Airtlow Model" l of Regulatory Guide 1.111 (formerly Draft P.egulatory Guide i.DD). I 1 They hydrological dispersion parameters are consistent with I the recommendations and intent of Regulatory Guide 1.109. I ten. 4 - Dose Calculations should be consistent with Draft Regulatory Guide 1.AA. j Response - Dose calculations performed in the evaluation of the Calvert Cliffs facility were consistent with Regulatory Guide 1.109 (formerly traft F.egulatory Guide 1.AA), See the text of this report and Section A.2 of this Appendia for details and specific references. Item 5 - Effluent Release Data from previous reactor operation should be provided, if available, for use in evaluating the source term calculations. Such data should include at least one full year of effluent release data tabulated by effluent relecse point, month, mode of cperation (e.c., full power oporation, refueling, shutdown), excluding the first year of reactor operation. A-3 TERA CORPORATION
i 1 Response - Calvert Cliffs Nuclear Unit I completed its first year of commer-
]
cial operation in May 1976. Calvert Cliffs Nuclear Unit 2 1 has yet to obtain its full-power operating license. On this basis, j it is concluded that item 5 does not apply to Calvert Cliffs Ruclear Units 1 and 2. I i Item 6 - The above evaluations should be accompanied by the information requested in Enclosure 2. Exceptions from the information ! requested will be considered on a case-by-case basis. , I i Response - The evaluation of the Calvert Cliffs facility with respect to i Appendit I employed the data provided in Enclosure 2. which l follows in Section A.2 of this Appendix. I Item 7 - The staff is prept., ring standard Technical Specifications and will ; issue further guidance to licensees regarding changes to Technical Specifications to impleinent the Appendix I objectives. Proposed revisions to Technical 3 specifications by licensees based on the iimit;ng conditions for operation set forth in Section IV of Appendix ! should be withheld pending further guidance from the staff. Response - The results of cur evaluations show that the existing Technical Specifications contained in Operating Licenses %. DPR-53 and DPR-69, for' Units No. 1 and 2 meet the "as low as practicable" cri te ria . Consequently, we are not proposing any additional changes to those Technical Specifications. A-4 ERA CORPC> RATION
)
i A.2 RESPONSES TO ENCLOSURE 2 l Aaditional Information Needed from Holders of Permits or Licenses to Construct or Operate Light-Water-Cooled Reactors for which Application was Filed Prior to January 2,1971 1 Item 1 - Provide the infonnation requested in Appendix D of Draft Regulatory Guide 1.BB or 1.CC, as appropriate. Response - The following data is provided consistent with the information requirements of Regulatory Guide 1.112, " Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from ' 1 Light-Water-Cooled Power Reactors," Appendix B, " Data Needed for ) Radioactive Source Term Calculations for Pressurized Water Reactors," (formerly Draft Regulatory Guide 1.BB, Appendix D). The information listed in this response constitutes the basic ' data used to calculate the release of radioactive material in liquid and gaseous effluents (source term) for the Calvert Cliffs facility. This data was taken from the contents of the Final Safety Analysis Report (SAR), Environmental Report (ER), and plant design documents as appropriate. All responses are for a single reactor unit.
- 1. General
- a. The maximum core thermal power (MWt) evaluated for safety considera-tions in the SAR. (Note: All of the following responses were adjusted to this power level.)
Data Iten ae 2700 MWt A-5 TERACORPORATION L
i
- b. The quantity of tritium released in liquid and gaseous effluents (Ci/yr per reactor). I Data Item b. The calculated total quantity of tritium released in liquid and gaseous effluent is 682 Ci/ year for the equilibrium cycle. (
Reference:
Environmental Report, Amendment 1, dated March 13, 1972.) l I The equivalent total tritium release calculated using NRC assumptions is 1070 curies (530 curies in liquid, 540 curies in gases). I
- 2. Primary System
- a. The total mass (lb) of coolant in the primary system, excluding the pressurizer and primary coolant purification system, at full power.
Data item a. 470,200 lb
- b. The average primary system letdown rate (gal / min) to the primary coolant purification system.
Data Item b. 40 gpm
- c. The average flow rate (gal / min) through the primary coolant purifica-tion system cation demineralizers. (Note: The letdown rate should j include the traction of time the cation demineralizers are in service.) {
Data Item c. The Calvert Cliffs facility does not employ cation 3 demineralizers.
- d. The average shim bleed flow (gal / min).
Data Item d. 0.28 gpm
- 3. Secondary System
- a. The number and type of steam generators, the type of chemistry used, and the carryover factor used in the evaluation for iodine and 1
nonvolatile. Data Item a. Two (2) recirculating U-tube steam generators; partition fa:. tor of 0.01 for iodine and 0.001 for nonvolatile.
- b. The total steam flow (lb/hr) in the secondary system.
6 Data Item b. 11.27 x 10 lb/hr A-6 TERA CORPORATION
i i
- c. The mass of liquid in each steam generator (lb) at full power.
Data item c. 217,600 lb ,
- d. The primary-to-secondary leakage rate (lb/ day) used in the evaluation. I Data Item d. 100 lb/ day
- e. Description of the steam generator blowdown and blowdown purification l systems. The average steam generator blowdown rate (1b/hr) used in the evaluation.
Data Item e. The plant has two (2) recirculating U-tube steam generators using volatile chemistry. The average blowdown rate is 0.2% of main steae flow (2.25 x 10 3 y l lb/hr). Blowdown tank vents are returned to the j / \ condenser. Liquids are currently discharged water or processed by the misce'llaneous radwaste system, as necessary. A blowdown filter and demin-eralizer system is currently being installed, with return flow to the feedwater heater (shell-side).
- f. The fraction of the steam generator feedwater processed through the condensate demineralizers and the decontamination factors used in l the evaluation for the condensate demineralized system.
l Data Item f. Fraction of steam generator feedwater processed through condensate demineralizers is 0.0. l (Condensate demineralizers not used to clean-up radio-active products.)
- g. Condensate demineralizers:
(1) Average flow rate (lb/hr). (2) Demineralized type (deep bed or powdered resin). 3 (3) Number and size (ft ) of demineralizers. (4) Regeneration or replacement frequency. (5) Indicate whether ultrasonic resin cleaning is used and the l waste liquid volume associated with its use. l (6) Regenerant (backwash) volume (gal / event) and activity. Data Item g. Not arplicable. Condensate demineralization not used. j 9 A-7 TERA CORPORATION ! l i
- 4. Liquid Waste Processing Systems
- a. For each liquid waste processing system (including the shim bleed, steam generator blowdown, and detergent waste processing systems),
provide the following information in tabular form: (1) Sources, flow rates (gal / day), and expected activities (fraction of primary coolant activity (PCA) for all inputs to each system).
]
(2) Holdup times associated with the collection, processing, and l discharge of all liquid streams., (3) Capacities of all tanks (gal) and processing equipment (gal / day) { considered in calculating holdup times. (4) Decontamination factors for each processing step. j (5) The fraction of each processing stream expected to be discharged ] over the life of the plant. (6) for demineralized regeneration, the time between regeneration, . regenerant volumes and activities, treatment of regenerants, and the fraction of regenerant discharged. Include parameters used in making these determinations. (7) Liquid source term by radionuclides (in C1/yr) for normal opera-tion, including anticipated operational occurrences. DataItema.(1) Flow Fraction Source (gpd) of PCA . 1
- a. Shim 400 1.0 Bleed
- b. Equip. 2600 0.6 l Drains I
- c. Clean 0.0 0.0 Waste
- d. Dirty 7000 0.01 5 Waste
- e. Blowdown (calculated)
- f. Regener- 0.0 0.0 ant A-8 TERA CORPORATION
DataItema.'(2)~and(5) Shim'-
& Dirty.
Equip. Waste Blowdown
- 1. 24_ .46 (Reti rculated
- 2. 9.7 7.2 to condensate system)
- 3. 1.0 1.0 Line 1 = waste collection time (days)
.Line 2 = waste. processing and discharge time (days)
Lf ne 3 = average fraction discharged Data Item a.(3) Collection Tank (gal.) 90,000 4,000 Holdup Tank (gal.) 90,000 90,000 DischargeTank(gal.) 90,000 '90,000 of' Equip. flow limiting capacity (gpd) 2.88x10 process 4 (1)'1.73x 10 5 (2) (1)basedon20gpm.wasteevaporator (2) based on 120 gpm radwaste demineralized DataItema.(4) Decontamination factors for each step are shown in Figures 3.2-1, 3.2-2, 3.2-3 of the report. Total' system DF's are as follows: Source Halogens Cs,Rb Utner
- a. Shim 1E07 4E05 1E08 Bleed
- b. Equi p. 1E07 4E05 1E08 Drains
- c. Dirty 1E05 4E01 1E05 Waste
- d. Blowdown 1E02 1E01 1E02 DataItema.(6)
No regeneration operations are anticipated for the radioactive liquid waste processing systems at the Calvert Cliffs facility. A-9
. TERA CORPORATION
i i i Data Item a.(7) Calculated liquid source terms by radionuclides (in Ci/yr) for normal plant operation are provided in the following Table A-1, and in Section 3.5 of the report.
- b. Provide piping and instrumentation diagram; and process flow diagrams for the liquid radwaste systems and for all other systems influencing the source term calculations.
Data Item b. The Reactor Coolant Waste Processing System piping and instrumentation diagram (P&lD) are Figures 11-1 & 11-1A in the Calvert Cliffs FSAR. Additional systems influencing the source term calculations are the Containment, Turbine,
]
Control Room & Penetration Room Ventilation System, the ! Auxiliary Building Ventilation System, the Condenser Air Removal and Priming System, and the Waste Gas and Misc. Waste Processing systems, the P&ID's for which are j Figures 9-21 (21A), 9-22, and 11-2, respectively, in the Calvert Cliffs FSAR. The P&ID's also fulfill the pro- i cess flow diagram requirement.
- 5. Gaseous Waste Processing System
- a. The volume (ft3 /yr) of gases stripped from the primary coolant.
3 Da,ta Item a. Total design basis volume - 23,620 ft at 14.7 psia, 80 F (per unit basis),
- b. A description of the process used to hold up gases stripped from the primary systems during normal operations and reactor shutdown. If pressurized storage tanks are used, include a process flow diagram of the system indicating the capacities (ft ),3 number, and design and operating storage pressures of the storage tanks.
3 Data Item b. Three (3) pressurized storage tanks (610 ft each) are used. Design pressure is 150 psig. Figure 11-2 of the Calvert Cliffs FSAR includes the Waste Gas Processing System P&ID. A-10 TERA CORPORATION
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- c. A descri.ntion of the normal operatior, of the system, e.g., the number ,
of tanks held in reserve for back-tv-back s'nutdown, fill time for { tanks. Indicate the minimum holdup time used in the evaluation and the basis for this number. l Data Item c. Nermal operation of the system is described in the Calvert Clif fs FSAR. Section 11.1.2.3. The calculated minimum holdup time used in the evaluation iG 45 days, based on the tank volumes and average yearly gas pro- 3 duction rates. )
- d. If HEPA filters are used downstream of the pressurized storage tanks, the decontamination tactor used in the evaluation.
Data Item d. HEPA filters are used downstream of the storage tanks. ) l The particulate DF used in the evaluation was 100,
- e. If a charcoal delay system is used, a description of this system j indicating the v.inimum holdup times for each radionuclides considered in the evaluation. List all parameters including mass of charcoal 3
(lb). flow rate (ft / min), operating and dew point temperatures, a'id dyn;mic ad:orption coefficNts for Xe and Kr used in calculating holdup times. Data Item e. No charcoal delay is used in the Calvert Cliffs system. l f. Piping and instrumentation diagrams and process flow di? grams for the gaseous radwaste systems and for other systems influencing the source term caltcletionto. usta Item f. (See Data Item b.)
- 6. Ventilation and Exhaust Systems _
For each building that houses a steam generator blowdown system vent l exhaust. a passcus waste proce: sing system vent, a n.ain condenser air i 1 removal system, or a system that contains radioactive materials, provide j the following: I
- a. Provisions incorporated to reduce radioactivity releases through .
the ventilation or exhaust systems. ! t A-12 TERA CORPORATION j
Data Item a. Provisions incorporated to reduce radioactivity releases through ventilation or exhaust systems for the containment and auxiliary buildings include auxiliary building HEPA filters and containment HEPA and recirculating charcoal filters.
- b. I Decontamination factors assumed and the bases (include charcoal adso/bers, HEPA filters, and mechanical devices).
Data Item b. For all charcoal filters and HEPA filters in ventila-l tion and exhaust systems, decontamination factors of j l 10 and 100, respectively, were assumed.
- c. Release rates for radiofodine, noble gases, and radioactive j particulate and their bases.
Data Items. Calculated release rates for radiciodine, noble gases, and radioactive particulate are presented in Table A-1 and in Section 3.5 of the report. ! d. Description of the release points, including height above grade, ! l height above and location relative to adjacent structures, expected average temperature difference between gaseous effluents and ambient air, flow rate, exit velocity, and size and shape of flow orifice. Data Item d. Release Point Description Unit 1 Plant Vent Unit 2 Plant Vent a) Size and shape of flow Circular pipe 6 ft. orifice Same as Unit - 1 internal diameter b) Height above grade 158.5 ft. Same as Unit - 1 c) Height above adjacent 10 ft. above con-structure Same as Unit - 1 I tainment dome d) location relative to SE with approxi- NE with approximately adjacent structure mately 3 ft. I 3 ft. clearance clearance e) Flow rate 131,000 cfm 11?,000 cfm f) Exit velocity 4600 ft/ min 4000 f t/ min g) Expected average tempera- 0 0 ture difference between l gaseous effluents and ambient air The distance between the above described release points is about 210 feet. , A-13 TERACORPORATION
- e. For the containment building, the building free volume (ft 3) and a thorough description of the internal recirculation system (if pro-vided), including the recirculation rate, charcoal bed depth, operating time assumed, and mixing efficiency. Indicate the expected purge and ventirig frequencies and duration and the continuous purge rate (if used).
Data Item e. Containment building volume - 2.0 x 106 ft 3 Recirculation rate - 60,000 cfm Charcoal bed depth - 2 inches Operating time - 16 hours Mixing efficiency - 70% Purge frequency - 20 times per year, plus 4 shutdown purges. Venting frequency - Continuous venting is not used Item ? - Provide, in tabular form, the distances from the centerline of the first nuclear unit to the following for each of the 22 degree radial sectors centered on the 16 cardinal compass directions. a) nearest milk cow (to a distance of 5 miles) { b) nearest meat animal (to a distance of 5 miles) c) nearest milk goat (to a distance of 5 miles) d) nearest residence (to a distance of 5 miles) e) nearest vegetable garden greater than 500 ft 2 l (to a distance of 5 miles) f) nearest site boundary For radioactivity releases from stacks which qualify as elevated releases as defined in Draft Regulatory Guide 1.DD, identify the locations of all milk cows, milk goats, meat animals, residences, and vegetable gardens, in a similar manner, out to a distance of 3 miles for each radial sector. Response - Table A-2 provides the distances of the nearest receptors within a distance of 5 miles for items a-f. A-14 TERA CORPORATION
TABLE A-2 ACTUAL SITE B0UNDARY NEAREST DISTANCF WITHIN 5 MILES
- l l
Affected Site Boundary Nearest Cow (1) Nearest Nearest i Sectors Meters and Meat Animal Residence Garden { Meters . Meters Meters. l SE 1281' - 2134 - SSE 1297 - 2499' '2621 i i S 1500' - 2682' 2865 l SSW 1578 - 2621 '2682 SW 1438 6706' 2012, 2377 WSW 1328 - 1829 1920 W 1656 - 1951 ,2225 WNW 1150 - 1494 1524' NW 1265' - 3292 3322
*No Milk Goats (1) Potential Location A-15 TERA CORPORATION
Tables A-3, A-4 and A-5 identify all locations out to a distance of 3 miles where such recepters exist (to be applied to elevated release calculations). Note that no milk coats exist within 5 miles of the plant and that meat animals / potential milk cows exist at only one location, in the southwest sector at 6,700 meters. For the locations 2 miles and larger, some of the numerous loca-tions have been combined and represented by an average location.- This combining process occurred for distances within about 500 feet of each other (i.e., receptor locations at 10,900, 11,100, and 11,600 in the NW affected sector were represented by a distance of 11,200 feet in the calculations (Table A-3)). This combination of locations is included on Table A-4 by the brackets to the right of the location. The residences located within 3 miles of the plant (Table A-3) N have been represented by calculations performed every 0.125 miles from 1.125 miles to 3 miles. This method was used because the specific locations were not given. The appropriate distance calculation representing the specific receptor location can be determined from the 0.125 mile increments. Item 3 - Based on considerations in Draft Regulatory Guide 1.DD, provide estimates of relative concentration (X/Q) and deposition (D/Q) at locations specified in response to Item 2 above for each release release point specified in response to Item 1 above. Response - The following Tables A-7 through A-15 provide estimates of X/Q and D/Q for a single release point from the Calvert Cliffs plant . having characteristics described in Table A-6. The X/Q and D/Q \' estimates are based on data for the period January 1,1975 - December 31, 1975 from a meteorology tower which meets the , requirements of Regulatory Guide 1.23. A-16 ' TERA CORPORATION i!
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3 2 4 6 ed ri 01 '00 '08 '01 '01 '02 '09 '03 as 8, 92 09 4 05 9 02 8 01 02 08 09 03 ee 03 9,1 4,1 0,1 6, 02 6, 62 8, 62 2, 42 0,1 NR 1( 4( 6( 6( 6( 8( 2 wia 8( 8( 7( on ca kt l a i e
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l TABLE A-4 1 IDENTIFICATION BY SECTORS OF VEGETABLE GARDENS 500 FT.2 OR LARGER WITHIN 3 MILES OF CALVERT CLIFFS NUCLEAR UNITS 1 & 2 FEET I i l l Nearest
- No. of Loca ted* Located
- Located
- 1.ocated*
Vegetable Vegetable Between Between Between Between i Sectoro
- Garden __ Gardens 0 & 1.5 mi. 1.5 & 2.0 mi. 2.0 & 2.5 mi. 2.5 & 3.0 mi. }
NW 10,900 18 0 0 1- 10,906 1- 14,106 2- 11,100 2- 14,200 3- 11,600 3- 14,600_ 4- 11,700~ 4- 14,906 5 .12,000 5- 15,000 ,
.{
6- 12,100_ 6- 15,20Q , 7- 12,700~ 7- 15,600' 8- 12,800_ 8- 15,700 9- 15,700 10- 15,700 ; WNW 5,000 3 1- 5,000 1- 9.200 0 0 , 2- 9,700 i l W 7,300 4 1- 7,300 1- 8,800 1- 12,800 0 2- 7,600 WSW 6,300 1 1- 6,300 0 0 0 l SW 7,800 4 1- 7,800 1- 8,700 1- 11,000 ! ' 0 2- 9,100 SSW 8,800 10 0 1- 8,800 1- 10,506, 1- 14,106 2- 9,900 2- 10,80Q 2- 14,20E 3- 11,206 3- 14,600 4- 11,500
'5- 13,000 l
S 9,400 5 0 1- 9,400 1- 10,700 0 ! 2- 9,600 2- 11,20Q 3- 11,700 ] i SSE 8,600 1 0 1- 8,600 - 0 0 ! SE ------------------No Gardens--------------- I co Sectors not shown are in the Chesapeake Bay Area. I o Distance from center of plant in feet. ' i A-18 1 TERA CORPORA 710N l
3 2 1 8 3 5 4 - 4
- - - / - - - - /
0 - 7 8 4 6 8 2 2 6 2 8 6 6 5 S S. 9 3 2 2 2 3 SR 3 3 4 8 0 EE - - / / - - - - / LT 6 2 8 3 4 I E 6 MM 1 0 / / / 2 4 7 5 0 O 7 0 3L 2 2 2 3 0 I NK 2 2 I / HS 3 0 2 1 2 TE 1 6 5 0 8 IL 4 4 3 9 8 WI . . . M 3 3 3 3 3 S T - - / / / - / - / E S S 1 0 3 4 5 C R 5 ES 2 5 8 2 RN 1 N O EE 1 1 0 4 4 E T S A . . . D C R TD 2 2 2 2 2 I E E 6 S NR S S T E IA 1 1 L G E E 8 0 B F R E M A OE 2 6 3 3 6 7 R O 2 3 3 6 4 7 8 5 3 F O L / / / T L 2 2 7 6 9 6 O H I SB 0 5 0 TA
. . . . . S K 5 7 3 3 2 2 2 3 S N / 7 8 NT - - / / / - / / / E O S .
I E 7 7 OG 3 7 7 0 C E 1 1 2 1 2 6 3 6 N L L PE 0 0 7 V 6 8 2 A L I F
. . . . T A M OF 2 2 1 1 1 2 S O I N N D I OS 6 8 2 6 3 3 IE 2 5 TC 1 1 0 1 AN 9 0 6 3 8 4 CA 2 3 2 2 2 3 OT 1 2 LS - - / / / - / / / 1 1 I
8 5 8 9 2 1 8 0 2 D 1 7 4 3 4 2 8 8 6 4 7 1 1 2 1 1
/ / /
1 1 1 2 5 0 5 2 5 7 1 2 2 5 3 7 0 6 4 2 1 1 2 6 8 7 2 2 2 2 6 8 6 3 9 2 5 3
- 2 2 2 2 1 2 1 3
/ / / / / / / /
9 0 7 7 3 3 7 4 2 8 6 7 9 8 4 6 6 7 6 4 1 3 9 0 1 1 l 1 l l 0 2 d e t r ~ co E W W W et E S S W S N W f c S S S S S W W l r N f e AS
> (;
)
$> c[}
r l Data was evaluated by two methods, one taking credit for plant vent elevated release when wind speed conditions permit (based on the criterion provided in Regulatory Guide 1.111, Section C.2.b), the other assuming a continuous ground level release. A straight line trajectory model was assumed for both elevated and ground level releases. Titbles A-7 and A-8 provide X/Q and D/Q values J for elevated releases at receptor locations consistent with Table A-2. Fumigation factors consistent with evaluated sea breeze effects are also provided and should be included in " realistic" s calculations of site dispersion. (See Response to Item 7 below for details of analysis.) i Tables A-9 and A-10 provide X/Q and D/Q values for the conser-fative case of continuous ground level release at receptor !
', locations consistent with Table A-2. Open terrain factors are i
< also providod for the various locations of interest. This ground level release model with terrain factor is considered to be !
l overly conservative for the Calvert C11ffs site, but is included d for information and comparison purpuses to demonstrate that calculated doses are well within guideline values even using this model. Tables A-ll and A-12 provide the elevated release X/Q and D/Q values for all receptor residences within 3 miles of the plant. l Table A-13 provides the applicable fumigation factor. Tables A-14 I and A-15 provide elevated release X/Q, 9/Q and fumigation factors for all vegetable gardens within 3 miles of the plant. (Note that no milk goats, milk cows, or meat animals exist within 3 miles of the plant.) l TERA CORPORATION
TABLE A-6 PLANT CHARACTERISTICS ' .p , w1 Unit 1 Unit 2 Height of Release (MSL) 203.5 ft 203.5 ft , Height of Base of Stack (MSL)- 45 ft 45 ft-Dimension of Stack (Diameter of Circle) 6 ft. 6 fi-Height of Stack Above Base 158.5 ft 158.5 ft Exit Flow Rate (CFM) 130,750 112,497 Cross-sectional Area of Stack 28.27 ft 2 28.27 ft2 Exit Velocity of Effluents- 77.07 ft /sec. 66.31 ft /sec, Type of Plume Rise Momentum Momentum Height of Containment Structure Above Base 148.4 ft 148.4 ft HeightofWindSensor(MSL) 200 ft 200 ft Height of Wind Sensor Above Base 125 ft 125 ft 1 i s A-21
- TERA CORPORATION.
, r, ., <
). ' ,? .
' l- l 1 l
TABLE A-7 / lj l '
;- ELEVATED RELEASES
/
x/Q, D/Q, AND FilMIGATION IACTORS RECEPT 0R TABLE A ? , - 1 DATA PERIOD: 1 Jamary .11 Cd.e2W 7975 Distanc: Affected Meters Fumigation Sector (miles) y/Q D/Q Factors l
; Site Boundary i SE 1281 f.1E-7 5.3E-9 1.12 :
(0.796) j SSE 1297 2.6E-7 s 4.4E-9 1.11 (0.806) >[ ,c,- I S 1500 2.3E-7 4 . SE.-9 1.12 (0.932) , . ' // SSW 157r,i 6.5E-8 1.5E-9 1.07 ( (0.381) ll SW 1438 1.8E-7 2.6E-9 1.09 (0.894) WSW 1328 1.2E-7 1.9E-9 1.11 (0.8L5) . W 1656 5.4E-8 9. 5 E-10 1.08 (1.029) j WNW 1150 9. 5E. 3 ~ , 1. 2E-9 1.15
, (0.715) .
i
'1 i
'<NU 1265 1. 2E ' './ ' 1.7E-9 1.18 ;
(0.786) i
,1 {
Nearest Milk Cow and Meac Animal , SW 7 6706 3.4E-3 2.lE-10 1.07
/
(4.167) i e f s F
,. A-22 L I TERA CORPORAT:ON 4
,i
_ _ ___ L _.__ _ 1 -.
TABLE A-8 ELEVATED RELEASES x/Q, D/Q, AND FUMIGATION FACTORS RECEPT 0R TABLE A-2 DATA PERIOD: 1 January - 31 December 1975 l Distance ' Affected Meters Fumigation ( Sector (miles) y/Q D/Q Factors Nearest Residence l SE 2134 2.0E-7 2.3E-9 1.06 (1.326) SSE 2499 1.5E-7 1.4E-9 1.05 i (1.553) l 5 2682 1.lE-7 1.9E-9 1.05 I (1.667) ! SSW 2621 7.9E-8 9.lE-10 1.05 (1.629) ; SW 2012 1.5E-7 1.6E-9 1.06 (1.250) 1 i WSW 1829 1.1 E-7 1.2E-9 1.07 l l (1.136) W 1951 1.lE-7 9.7E-10 1.06 (1.212) WNW 1494 9.3E-8 8.6E-10 1.09 ! (0.928) J 3292 8.5E-8 I NW 5.0E-10 1.05 (2.046) l i Nearest Garden l SSE 2621 1.4E-7 1.3E-9 1.05 l (1.629) l S 2865 1.5E-7 1.7E-9
- 1.05 I (1.780)
SSW ~2682 7.7E-8 8.7E-10 1.05 (1.667) SW 2377 1.3E-7 1.2E-9 1.06 l (1.477) 1 WSW 1920 1.0E-7 1.lE-9 i 1.06 l (1.193) i W 2225 1.lE-7 8.2E-10 1.06 (1.382) , ; WNW 1524 9.3E-8 8.4E-10 ' 1.08 I (0.947) NW 3322 8.5E-8 5.0E-10 1 (2.064) ! .05-A-23 TERACORPORATION j j
TABLE A-9 X/Q, D/Q,and OPEN TERRAIN FACTORS GROUND LEVEL RELEASES WAKE TERM INCLUDED RECEPT 0R TABLE A '2 DATA PERIOD: 1 January - 31 Decertber 1975 Distance Open Affected Meters Terrain Sector (miles) y/Q D/Q Factor Site Boundary SE 1281 2.0C-6 1.2E-8 3.628 (0.796) l SSE 1297 1.6E-6 9.7E-9 3.591 (0.806) S 1500 2.lE-6 9.0E-9 3.100 (0.932) SSW 1578 7. 4E- 7 3.5E-9 2.952 (0.981) ( SW 1438 1.6E-6 5.4E-9 3.232 (0.894) WSW 1328 1.3E-6 4. 4 E-9 3.504 (0.825) W 1656 1.2E-6 3.lE-9 2.820 l (1.029) WNW 1150 1.5E-6 4.6E-9 4.000 ' (0.715) NW 1265 1.7E-6 6.0E-9 3.686 (0.786) Nearest Milk Cow and Meat Animal SW 6706 1.6E-7 3.3E-10 1.177 (4.167) e A-24 l TERA CORPORATION
I TABLE A-10 x/Q,D/Q, AND OPEN TERRAIN FACTORS GROUND LEVEL RELEASES WAKE TERM INCLUDED RECEPT 0R TABLE A-2 DATA PERIOD: 1 January - 31 December 1975 Distance ! Open Affected Meters { Sector Terrain q _(miles) y/Q D/Q Factor j l Hearest Residence ~
'J
~ ~~
SE 2134 9.4E-7 4.6E-9 3.510
~'
(1.326 I SSE 2499 6.2E-7 2.9E-9 2.998 (1.553) 1 J S 2682 9.0E-7 3.lE-9 . 2.803 (1.667)
'SSW 2621 3.4E-7 1.4E-9 2.864
) (1.629) ' SW 2012 9.3E-7 3.0E-9 3.733 (1.250) ' WSW 1829 8. 0E- 7 2. 5 E- 9 4.000 (1.136) W 1951 9.7E-7 l 2.3E-9 3.858 ; (1.212) WNW 1494 9.9E-7 2.9E-9 4.000 (0.928) NW 3292 4.2E-7 1.0E-9 2.338 (2.046) )' 1 Nearest Garden i SSE 2621 5.8E-7 2.7E-9 2.864 < (1.629) 1 5 2865 8.2E-7 2.8E-9 2.639 (1.780) SSW 2682 3.3E-7 ' 1.3E-9 2.803 (1.667) SW 2377 7.2E-7 2.2E-9 3.i48 (1.477) WSW 1920 7.5E-7 2.3E-9 3.924 (1.193) W 2225 8.0E-7 1.8E-9 3.365 (1.382) WNW 1524 9.6E-7 2.8E-9 4.000 (0.947) NW 3322 4.2E-7 1.0E-9 2.320 m (2.064) A-25 g TERA CORPORATION ' l-
E E E E E E E E
. 0 3 8 5 0 l 4 4 4 2 . . . . .
1 8 9 4 7 5 6 4 6 5 7 8 7 8 8 8 8 8 8 2 - - - - - - - - - 6 E E E E E E E E E l 2 0 8 3 4 7 l 7 2 . . . . . 1 8 1 4 7 5 6 4 6 0 7 8 7 8 8 8 8 8 8 0 - - - - - - - - - 5 E E E E E E E E E
. l 7 l 0 7 7 0 9 0 2 . . . . . . .
1 8 1 5 7 5 7 4 7 5 7 8 7 8 8 8 8 8 8 7 - - - - - - - - '- 3 E E E E E E E E E 5 2 3 l 3 l 0 3 l 4 7 2 . . . . . . 9 1 9 1 5 8 6 7 5 7 1 0 7 8 7 8 8 8 8 8 8 r 5 - - - - - - - - - e 2 E E E E E E E E E b . 3 9 2 6 6 3 7 4 8 _ S m 2 . . E e 1 9 1 5 8 6 7 5 7 NL c . OI e 5 7 7 7 8 8 8 8 8 8 SIM3D ET S2 - - - - - - - - - _ - E1 E E E E E E E E E l SA3 A1 AR 3 L I2 4 l 3 0 l 6 0 7 2 l ETNE M 1 1 1 6 9 6 8 5 8
- LNI L -
_ A EEH B E0 7 7 7 8 8 8 8 8 8 _ RCTAy C0 - - - - - - - - - E NI Tr N0 E E E E E E E E E _ L DOH a A 3 l 3 4 7 0 4 0 7 _ B EC R u T2 . . . _ A T S O r. S 1 1 1 6 9 7 8 6 _ T AEE T a I 8 _ VVCPJ D5 7 7 7 8 7 8 8 8 8 _ EINE 7 - - - - - - - - - LTE C1 8 E E E E E E E E E EADE 4 2 4 8 0 4 9 4 2 _ LI R 1 . . , . _ ES : 1 1 1 6 1 7 8 6 9 _ RE D R O 5 7 7 7 8 7 8 8 I ~ - - 8 8 R . E E E E E E E E E E 1 6 3 5 3 l 9 3 6 P . . . 8 _ 1 1 1 7 7 1 9 6 9 _ A _ T 5 7 7 7 8 7 8 8 _ A 2 - - - 8 7 _ D 6 E E E E E E E E E . . 7 7 9 2 4 8 0 1 . d. . 1 . . . 0 _ 1 1 7 8 1 1 9 7 1 0 7 7 7 8 7 8 7 8 7 0 - - - - - - - - - 5 E E E E E E E E E 8 5 8 5 3 9 0 4 0 1 . . . . 8 1 1 1 1 8 1 7 1 5 7 7 7 8 7 8 7 8 7 7 - - - - - - - - - 3 E E E E E E E E E 0 7 7 3 3 5 l 9 0 _ 1 . . . . . . . . _ 2 1 1 9 1 9 1 7 1 0 7 7 7 7 7 7 7 8 7 _ 5 - - - - - - - - - 2 E E E E E E E E E
. 2 8 8 0 5 0 l 3 l 1 . . . , . . . .
2 1 ' 1 1 1 1 8 1 5 7 7 7 7 7 7 7 8 2 - - - 7 1 E 't E E E E E E E 4 0 0 l 6 l 2 8 l 1 . . . . . . . . . 2 2 2 l l l l 8 l d e t r co et f c E W W W f e E S S W S N W AS S S S S S W W W N 1S R l!
~ _
l 1 1 TABLE A-12 ELEVATED RELEASES DEPOSITION VALUES RESIDENCES WITHIN 3 MILES RECEPT 0R TABLE A-3 OATA PERIOD: 1 JANUARY - 31 DECEMBER 1975 Distance Affected Sector SW ,JSW W WNW NW (miles) SE SSE S SSW
- 3. 4E-09 1. 7E-09 1.9E-09 't .2E-09 1.1E-09 6.8E-10 1.1E-09 j 1.12 3.1E-09 2.5E-09 1.25 2.5E-09 2.1E 09 2.9E-09 1.4E-09 1.6E-09 1.1E-09 9.3E-10 5.9E-10 9.7E-10 1.37 2.1E-09 1. 8E-09 .?. 5E-09 1.2E-09 1.4E-09 9. 3E-10 8.3E-10 5.2E-10 8.6E-10 1.50 1. 8E-09 1.5E-09 2.3E-09 1. lE-09 1.2l:-03 8.2E-10 7.4E-10 4.6E-10 7.9E-10 1.62 1.6E-09 1.3E-09 2.0E-09 9.2E-10 1. lE-09 7.2E-10 6.7E-10 4.lE-10 7.0E-10 .
1.75 1.4E-09 1.2E-09 1,7E-09 8.1E-10 9.4E-10 6.5E-10 6.0E-10 3.7E-10 6.3E-10 ] l 1.87 1.2E-09 1.0E-09 1.5E-09 7.lE-10 8.4E-10 5.8E-10 5.5E-10 3.4E-10 5.7E-10 1 2.00 1.lE-09 9.lE-10 1.4E-09 6.4E-10 7.6E.-10 6.3E-10 5.0E-10 3.1E-10 5.2E-10 l 2.12 9.9E 10 8.2E-10 1.2E-09 5.7E-10 6.95-10 4.8E-10 4.5E-10 2.8E-10 4.7E-10 2.25 8.9E-10 7.4E-10 1.lE-09 5.2E-10 6.?E-10 4.3E-10 4.2E-10 2.5E-10 4.3E-10 2.37 8. 0 E- 10 6.7E-10 1.0E-09 4. 7E-10 5. 7E-10 4.0E -10 3.8E-10 2.3E-10 4.GE-10 2.50 7.3E-10 6.1E-10 9.2E-10 4.3E-10 5.2E-10 3.7E-10 3.5E-10 2.2E-10 3.7E-10 2.62 6.6E-10 5.6E-10 8.4E-10 4.0E-10 4.8E-10 3.4E-10 3.3E-10 2.0E-10 3.4E-10 2.75 6.1E-10 5.lE-10 7. 7E-10 3.6E-10 4.5E-10 3.1E-10 3.1E-10 1.9E-10 3.2E-10 2.87 5.6E-10 4.7E-10 7,. lE-10 3.4E-10 4. lE-10 2.9E-10 2.8E-10 1.7E-10 2.9E-10 3.00 5.1E-10 4.3E-10 6. 6E-10 3.1E 10 3.8E-10 2.7E-10 2.7E-10 1.6E-10 2.8E-10 l A-27 TERACORPORATION
7 0 0 0 0 0 0 0 2 1 1 1 1 1 1 1 1 1 5 2 6 5 5 5 5 5 5 5 5 6 0 0 0 0 0 0 0 0 0 2 1 1 1 1 1 1 1 1 1 0 0 6 5 5 5 5 5 5 5 5 6 0 0 0 0 0 0 0 0 0 2 1 1 7 1 1 1 1 1 1 5 7 6 5 5 5 5 5 5 5 5 3 0 0 0 0 0 0 0 0 0 2 1 1 1 1 1 1 1 1 1 0 5 5 5 5 5 5 5 5 5 5 2 0 0 0 0 0 0 0 0 0 S R 2 1 1 1 1 1 1 1 1 1 OS TE .
- CL ) 5 .
AI s2 5 5 5 5 5 5 5 5 5 y SFM e1 0 0 0 0 0 0 0 0 0 l E l . . n ST3 i 2 1 1 1 1 1 1 1 1 1 o 3 AN m 0 1 EEN (
- LMI 0 7 A ETH e0 5 5 5 5 5 5 5 5 5 RST c0 0 0 0 0 0 0 0 0 0 d E UI n n L DJW a2 1 1 s 1 1 1 1 1 1 a B ED t A TAS s C T A E i 5 7 VNC D7 5 5 5 5 5 5 5 5 5 EON 8 0 0 0 0 0 0 0 0 0 s LI E . e ETD 1 1 1 1 1 1 1 1 1 1 l AI b GS a I E 0 T MR 5 5 5 5 5 5 5 5 5 5 U 7 0 0 0 0 0 0 0 0 0 f F o 1 1 1 1 1 1 1 1 1 1 s
e 5 u 2 5 5 5 5 5 5 5 5 5 l 6 0 0 0 0 0 0 0 0 0 a v 1 1 1 1 1 1 1 1 1 1 Q
/
0 D 0 5 5 5 5 5 5 5 5 5 5 0 0 0 0 0 0 0 0 0 d
. n 1 1 1 1 1 1 1 1 1 1 a Q
5 / 7 6 6 7 5 6 6 6 6 7 x 3 0 0 0 0 0 0 0 0 0
. e 1 1 1 1 1 1 1 1 1 1 s a
e 0 l 5 6 6 7 6 6 6 6 6 7 e 2 0 0 0 0 0 0 0 0 0 r 1 1 1 1 1 1 1 1 1 1 d e t 5 a 2 7 7 9 6 6 7 7 7 9 v 1 0 0 0 0 0 0 0 0 0 e
. . . . l 1 1 1 1 1 l l l l 1 e r
o d F e t r
- co et f c E W W W f e E S S W S N W AS S S S S S W W W N Ob, p
. TABLE : A-14 ELEVATED RFLEASES .
VEGETABLE GARDENS WITHIN 3 MILES DATA PERIOD: 1 January - 31 December 1975 Distance Affected Meters . Fumigation . Sector (miles) _,,_y/0 _ D/0 Factors . . SSE 2622 . 1.4E-7 1.SE-9 - .1. 05 , (1.629)
~ .S 2865 1.5E-7 1.7E-9 1.05 '
(1.780) SSW 2683 7.7E-8 8,8E-10 1.05 (1.667) SW 2377 1.3E-7 1.2E-9. 1.05 (1.477) WSW 1920 . 1.0E-7 1.1E-9 1.06 (1.193) W 2226 1.1E-7 8.2E-10 1.06 ' (1.383) WNW 1524 9. 3E-8 8.4 E-10 1.08 , (0.947) NW 3322 8.4E-8 5.0E-10 1.05 (2.064) S 2926 1.5E-7 1.6E-9 1.05 (1.82) SSW 3018 6.8E-8 7.1E-10 1.05 (1.875) SW 2652 1.2E-7 1.0E-9 1.05 (1.648) W 2316 1.1E-7 7.8E-10 1.06 (1.439) WNW 2803 6.6E-8 3.7E-10 1.05 (1.742) i NW 3413 8.2E-8 4.8E-10 1.05-l (2.121) l S 3262 1. 3E-7 1.3E-9 1.05 l (2.027) ; SSW 3246 6.3E-8 6. 3E-10 1.05 i (2.017) , SW 2773 1.lE-7 9.6E-10 1.05 (1.723) W 2683 9.6E-8 6.4E-10 1.05 (1.667) WNW 2956 6.3E-8 3.5E-10 1.05 ! (1.837) ~j NW 3637 . 7.7E-8 4.3E-10 1.05 ' (2.260) ~ A-29~ TERACORPORATION
y i TABLE .A-15 I ELEVATED RELEASES VEGETABLE GARDENS WITHIN 3 MILES ' RECEPTOR TABLE A-3 DATA PERIOD: 1 January - 31 December.1975 Distance Affec ted Kilometers Fumigation SeQors (m iles) yf_Q D/0 Fac tors 1 3.413 1 S (2.1 21) 1.3E-7 1.2E-9 1.05 l 3.460 i S5W (2.150) 5.9E-8 5.6E-10 1.05 i ( 3.352 SW (2.083) 9.32-8 7.1E-10 1.05 1 3.901 - W (2.424) 7.2E-8 3.7E-10 1.05' ) 1 3.887 NW (2.415) 7.2E-8 3.9E-10 1.05 3.566 lJ S (2.21 6) 1.2E-7 1 lE-9 ' l.05 1 3.962- i SSW (2.462) 5.1 E-8 4.4E-10 1.05 1 4.358 i NW (~2. 708) 6.5E-8 3.2E-10 1.05 4.313 SSW' (2.680) 4.7E-8 3.8E-10 1.06 ! 4.582 - NW (2.847) 6.1E-8 3.0E-10 1.05' 4.450 SSW (2.765) 4.5E-8 3.6E-10 1.06 4.778 NW (2.969) 5.9E-8 2.8E-10 1.06 1 1
'l l >
l A-30 TERACORPORATION L__--- ___ - _ - - - _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - _ _ - _ - _ - _ _ - _ - _ - = - _ _ _ _ _ - _ _ _ _ _ _ _ _
Item 4 - Provide a detailed description of the meteorological data, models and parameters used to determine the X/Q and D/Q values. Include information concerning the validity and accuracy of the models and assumptions for your site and the representativeness of the meteorological data used. 1 Response - The meteorological data used to determine X/Q and D/Q values is discussed in the respcase to Items 5 and 7 below. Models arid parameters used to determine X/Q and D/Q values are dis-cussed in Section 4.2.2 of this report. These models and parameters are consistent with the recommendations provided in Regulatory Guide 1.111 (formerly Draft Regulatory Guide 1.DD) for the " Straight-Line Trajectory Model." The evaluation of X/Q and D/Q for the Calvert Cliffs site used the following meteorological parameters for the calendar year 1975: Parameter Measuring Level (feet) Wind Speed 125 Wind Direction lES Delta Temperature 30-200 Deita Temperature 30-125 The plant parameters are presented in Table A-6. Due to the close proximity of the two release locations when compared to the nearest receptor distance, only one release point was considered in the computer model . This release point had the characteristics of Unit 2 presented in Table A-6. The computer model, conforming to the Regulatory Guide 1.111 straight line trajectory model, was run for the receptor points given in Tables A-2 and A-3. The wind speeds were reduced by the standard power law to estimate winds at 10 meters above ground for use in ground level release calculations. A-31 TERA CORPORATION
i ine open terrain adjustment factors provided in 9,he X/Q and D/Q tables were developed from Figure 2 in Regulatory Guide 1.111 and should be applied to the X/Q and D/Q valuas derived as a result of the assumption that all plumes operate in a fully ground release mode. (However, the ground level release assumption is unnecessarily conservative.) The fumigation factors provided in the tables have been developed I by the analyses of sea breeze fumigation conditions which occur at Calvert Cliffs. They are described in Response 7 herein, and they should be applied to the X/Q and D/Q values derived from assumptions that the plume operates in elevated, mixed mode or ground release mode, as determined by concurrent wind speeds. The factors are distance and topography dependent, so each receptor has its own specific value. This approach is considered to be the correct and realistic one for the site. Open terrain adjustment and ' M2ation factors are used by multi-plying them times the appropriate X/Q or D/Q values. However, the open terrain adjustment factors and fumigation factors are never applied simultaneously to a X/Q or D/Q value at a receptor. In conjuncti)n with data collected by the meteorological tower (comrtc.surate w.th the recommendations and intent of Regulatory Guide 1.23), and as modified by the fumigation or terrain correction factor, deposition, and depletion models of Regulatory Guide 1.111, the " Straight-Line Airflow Model" provides a valid and conservative estimate of site meteorological dispersion characteristics for long-term releases such as those being evaluated here. No short term or intermittent releases were evaluated. The representativeness of the meteorological data is discussed in Item 5 below. A-32 TERA CORPORATION
Iten 5 - If an on-site program commensurate with the recommendations and intent of Regulatory G"ide 1.23 exists:
- a. Provide representative annual and monthly, if available, joint frequency distributions of wind speed and direction by atmospheric stability class covering at least the most recent one-year period of record, preferably two or more years of record. Wind speed and direction should be measured at levels applicable to release point elevations and stability should be determined from the vertical temperature gradient between measurement levels that represent conditions into which the l effluent is released.
- b. Describe the representativeness of the available data with respect to expected lor.g-term conditions at the site.
Response - a. An on-site meteorology program commensurate with the recommenda-tions and intent of Regulatory Guide 1.23 exists at the Calvert ; l Cliffs site. The data presented in Appendix B includes 12 months j of information, January 1975 through December 1975. The data includes the annual joint frequency distribution of wind speed and direction by stability class, as well as the monthly joint frequency distributions by stability class.
- b. The meteorological data presented for the period January 1975 through December 1975 is considered to be representative of long term conditions at the site. Comparisons with data presented in Section 2.3 of the Calvert Cliffs FSAR indicate that the gross wind frequency distributions are rather similar, as are the frequencies of occurrence of dispersion categories snd the annual average wind speed. In addition, the available data has been evaluated and applied in a conservative fashion such that annual fluctuations in site meteorological characteristics could not cause significant deviations from the estimated dispersion values.
A-33 TERACORPORATION
Item 6 - If recent on-site meteorological data are not available, or if ' the meteorological measurements program does not meet the recommenda-tions and intent of Regulatory Guide 1.23:
- a. Provide the best available meteorological data in the format described in Item Sa. above
- b. Describe the representativeness of the available data with respect to on-site and near site atmospheric transport and diffusion conditiors, and with respect to expected long term conditions at and near the site.
- c. Provide a description of the meteorological measurements used for collection of the data presented. This description l should include the location of the sensors with respect to i the power plant (s) and other prominent topographic features (including buildings) and accuracy of the instrumentation.
- d. Provide a commitment to establish a program to meet the i 1
recommendations and intent of Regulatory Guide 1.23, or pro- ' vide sufficient justification to allow the present ,.; ogram to remain unchanged. Response - The on-site meteorological program for the Calvert Cliffs facility meets the recommendations and intent of Regulatory . Guide 1.23, and recent data are available. j k Item 7 - Describe airflow trajectory regimes of importance in transporting l effluents to the locations for which dose calculations are made. Response - Atmospheric transport processes and airflow trajectory regimes are discussed in detail in the following paragraphs. i A-34 TERA CORPORATION
Atmospheric Transport processes At Calvert Cliffs A. Background In Regulatory Guide 1.111 0) it is pointed out that the straight-line trajectory models used to calculate annual average concentrations may underestimate these concentrations in the region near the source at some sites. The guide suggests specific factors for valley sites and for open terrain sites; and the magnitude of the factors is based upon the tendency of ground released plumes to meander in the vicinity of the source under light wird conditions at these sites. Because these occa-sional meandering, ground released plumes can have a signi.ficant influ-ence on close-in concentrations; factors up to 4 or 5 are recommended for use on open terrain and valley sites with ground release plumes. For coastal sites, the guide recommends that the proper recircula-tion factors be established on a case-by-case basis, and in the sections which follow the necessary recirculation factors for Calvert Cliffs are l developed. B. Recirculation at Calvert Cliffs Due To Plume Meander The Calvert Cliffs site is a coastal site on the shore of Chesa-peake Bay. About one-half of the wind directions are on-shore and one half off-shmre, where on-shore is the directions north-west through north-east to south-east. Using the plume evaluation methods of Guide 1.111, about one-half of the on-shore plumes at Calvert Cliffs are elevated releases. The other half of the winds are mixed mode; part elevated and part ground. Appendix B shows the wind direction, wind speed, stability frequencies of the 125-foot wind sensor which is at approximately the elevation of the plant stack vents. That portion of the plumes at Calvert Cliffs which are ground release constitutes far less than half of the plumes from the site because the Regulatory Guide 1.111 formula for prorating elevated and ground frequen-A-35 TERA CORPORATION
m cies begins at 9 mph, reachireg 100% ground release orly with winds ex-ceeding 45 mph. The recirculation factors, which have been identified as being appropriate for straight-line trajectory model calculations ap-plied to ground releases af the Braidwood Site (2) or the National Re-actor Testing Station (3) are due to plume meander during low wind speed, stable conditions. It is apparent that the ground release plumes at Calvert Cliffs cannot contribute significantly to such recirculation due to the high wind spi:eds needed for ground releases. ' The elevated release plumes at Calvert Cliffs site are " momentum" plumes resulting from stack exit velocities of about 45 mph. Their tem-peratures are essentially at ambient conditions. Using the conservative plume rise formulae of Sagendorf(4) for evaluation of elevated releases, the plume centerlines do not intersect the terrain within three miles of the source location. For these reasons, except for inversion breakup
)
conditions described in the following section, the highest ground concen-trations from these elevated plumes within three miles of the site occur during unstable conditions. i l During stable, low wind speed conditions when the elevated plume ! might meander, thereby contributing to plume recirculation, the result-ant ground concentrations near the site are lower than during unstable l 1 conditions. Such recirculation cannot have a significant effect on average ground concentrations calculated by the straight-line trajectory l model. l It is concluded that at, Calvert Cliffs, ground released plumes can-not contribute to recirculation because of their low frequency of occur-ence and their higher wind speeds when they do occur. It is further con-cluded that such recirculation as may occur during elevated release plumes !{ will not have a significantly adverse effect on average relative concen-trations calculated by the straight-line trajectory model. There is, how-ever, a set of meteorological conditions which can occur at Calvert Cliffs and which can affect the average relative concentrations calculated by the straight-line trajectory model. These conditions are those that accompany sea breezes at a coastal site. A-36 TERA CORPORATION
L 1
.C. Sea Breeze Recirculation' Factors At Calvert Cliffs !
~
J Evaluation of transport processes for the Calvert Cliffs site require- 8 consideration of the possible influences of sea breezes on the straight-line trajectory (SLT) model assumptions at coastal sites. Certain meteor- 1 ological events are not appropriately treated in the'SLT'model and they. I must be evaluated to determine.their significance. These events are des-cribed as follows:
- 1) The low level sea breeze air masses are often stable off-shore and up to the coast line because the air I
moves from warmer water off-shore across colder coastal water before moving inland. As the air moves inland' during the day, insolation may cause an unstable layer 'j
.1 to build upward from the ground. The top of this layer- 1 is the thermal inversion boundary layer (TIBL). This.
process continues until the " sea breeze front "is reach-ed when the entire sea breeze layer has become unstable, j If an elevated plume is emitted into the sea breezes ) at the coast line, it moves initially as a " coning" l plume in stable air, but when the TIBL. builds up to the plume elevation, the plume is mixed rapidly through the i unstable layer to the ground.
- 2) As shown by Lyons and 01sson(5) , when the plume emitted in the sea breeze reaches the sea breeze front, the inland boundary of- the sea breeze winds, the entire plume may go aloft, move seaward (above 700 meters ,
elevation), descend over the cold waters and move i inland again. -The sea breeze has thus established a closed circulation cell in a vertical plane gen-4 erally perpendicular to the shore line. The meteorological conditions and plume characteristics at the Calvert Cliffs site have been evaluated to determine the significance of these , events; and to determine the recirculation factors which should be applied to an SLT model to provide reasonable assurance that relative concentra-tions determined thereby are not significantly underestimated. The fre-t A-37 TERA CORPORATION.
1 1 i l : j i quency of sea breeze conditions is established first. Then the recircula-tion factors needed to account for its influence on relative concentrations are determined. D. Sea Breeze Significance At Calvert Cliffs An investigation has been performed to determine the extent to which sea breezes occur at Calvert Cliffs. The hours at which sea breezes and land breezes may be anticipated, l l if meteorological conditions are favorable, are defined as follows: Sea Breezes -- from three hours af ter sunrise to sunset Land Breezes - from three hours after sunset to one hour 1 after sunrise ' The annual data for calendar year 1975 from the Calvert Cliffs meteor-ological tower were divided into bi-monthly sets, and hours favorable to sea breeze and those favorable to land breeze were established, as follown: l Sea Breezes L cal Times - Land Breezes l Months Begin lid Begin End Jan - Feb 1000 1700 2000 0800 Mar - Apr 0900 1800 2100 0700 May - Jun 0800 1900 2200 0600 Jul - Aug 0800 1900 2200 0600 ; Sep - Oct 0900 1800 2100 0700 Nov - Dec 1000 1700 2000 0800 l Wind frequency distributions were examined for each bi-monthly data i set during sea breeze times and land breeze times to see if sea breeze and land breeze regimes were evident. Criteria for evidence of a signifi-cant land breeze or sea breeze influence on the frequency of wind direc-tions were established as follows: For each wind direction sector, the frequency of wind during sea breeze times (in accordance with the above table) is S, and the frequency during land breeze t'imes is L: A-38 TERA CORPORATION
1
- 1) Sea breeze influences are significant for a sector:
(a) if S s 5%, and S~l (b)if s 0.3
- 2) Land breeze influences are significant for a sector: )
(a) if L s 5%, and 1 b~l (b) if 2 -0.3 If only condition 1(b) or 2(b) is satisfied, sea breeze and land breeze I influences are considered possible, but the overall frequency of wind in the 50ctor is insufficient to establish the influence with confidence. l The following table (Table A-16) illustrates the result of these tests on the directional sectors for each bi-month period. The symbols C and A l indicate both criteria above are satisfied for sea and land breeze influ- I I ences, respectively. The symbols
- and for sea and land breeze, res-pectively, indicate that tests 1(b) and 2(b) only were satisfied. l Although random wind variations, not related to land and sea breeze influences are apparent, nevertheless winds from north through east to j south-southeast show frequency shifts which may be related to sea breeze conditions. These directions ray be compared with the on-shore directions which are north-northwest through east to southeast.
E. Inversion Breakup (Fumigation) Conditiors at Calvert Cliffs The Chesapeake Bay waters offshore of the Calvert Cliffs site are apparently of sufficient extent and temperature contrast to influence the frequency of on-shore and off-shore wind directions. These waters cannot, however, have the influence of the larger water bodies such as the sea or Great Lakes coastlines. It should be anticipated, for example, that the Chesapeake Bay waters lose their land-sea temperature contrasts later in the summer. The coastline at Calvert Cliffs has an orientation which is about northwest toward southeast. Many on-shore winds have a strong northerly component, and these winds may be producing advection of colder air which A-39 TERA CORPORATION
I I i i I l TABLE A-16 l SEA AND LAND BREEZE INFLUENCES l Wind Bi-Month Period , Direction Jan Mar May Jul Sep Nov All Sector Feb Apr Jun Aug. Oct Dec Months SW A A WSW C A W C A WNW A A A A NW A A NNW C C N C C C C C C C NNE C C C l NE C C C C C ENE *
- C C C E C C C C ESE C C SE C C C SSE C C C C C I S A A A A A A SSil A A A A A A l
l A-40 l TERA CORPORATION
I 1 would tend to limit the strength' of inversion conditions which could- I develop at the coast in sea breezes. A two-step process was developed to identify the times, in the 1975 calendar year data, when sea breeze inversion breakup was occurring at Calvert Cliffs. The first step was to identify all conditions when tower. ] data are appropriate for sea breeze inversion breakup (fumigation) inland of the site. The second step was to examine the weather conditions'and general circulation and eliminate those in which fumigation was not likely l to occur in spite of favorable indications in the onsite data, j Upon evaluation of the frequency of occurrence, the effects of fumi- j gation on the annual average x/Q and D/Q values were evaluated. l l The Frequency of Fumigation The first test for fumigation is performed on the onsite Calvert Cliffs meteorological data for 1975. The test includes the following criteria, which were applied to each hour of the data record as follows: ; (1) Time of day as defined in the Section D above (2) On-shore wind direction, northwest through northeast j to southeast (3) At least 2 hours persistence of on-shore wind during the day (4) Wind speed 5 1.0 mph (5) Upper tower,125 to 200 ft. stability, AT Pasquill class E, F, or G at the hour of test (6) Lower tower, 30 to 125 ft., AT Pasquill class A,-B, C, or D at the hour or during transport inland at initial wind speed to 50 km based on initial wind. speed. (7) Elevated plume status The significance and validity of the first four tests above do not need comment. The validity of the stability tests is based upon an eval-A-41 l TERACORPORATION. l I
uation of the plume characteristics at the site and the requirements for inversion breakup, as follows:
- The plume must be emitted into an initially stable layer so that it moves downwind toward the receptor aloft but with a slow rate of dilution.
Instabilit.y builds up from the ground to reach the ! poorly diluted plume and carries it to the ground rapidly at the downwind receptors. The effective plume heights were evaluated to determine the extent i to which tower measurements are representative of the stability conditions which affect the plume. The following table shows the plume elevations for the Calvert Cliffs releases, evaluated using the plume rise formulae recommended for use at j nuclear plants by Sagendorf(4) These heights are elevations above base I of the meteorological tower. Wind Speed, mps .5 1 2 4 6 8 10 13 Plume Elevation, m Neutral or Unstable Air 441 237 143 91 74 65 60 55 Pasquill E 104 90 80 72 67 65 60 55 F 97 85 75 68 64 62 60 55 G 94 82 73 66 63 61 60 55 ' The vents are 39 meters above the tower base, and the upper tempera-ture differences on the tower are measured between 38 and 61 meters. It is apparent that, except at low wind speeds in unstable air the tower mea-surements are a reasonable evaluation of the stability of the layer into which the plume is emitted. There were 413 hours in 1975 which satisfied the tower test criteria described above. Each day identified therein was examined in terms of weather conditions and general circulation. A-42 TERACORPORATION
1 There were several conditions which created positive tower. indica-tions, but during which cea-breeze inversion breakup was not likely to occur. The typical winter storm moving up the Atlantic _ Coast and giving
]
north to northeast winds and rain often gave on-shore flow at Calvert _- Cliffs with an upper layer Pasquill E and a lower layer Pasquill D. The tower tests would select these hours as potential fumigation. Cold fronts crossing the site would often have stable air behind them with onshore north to northwest winds at Calvert Cliffs. If warmer than the Post Cold fronteir,ChesapeakeBaywaterswould"destabilize"thelowerlayer,and! the tower data might show Pasquill E or F above a Pasquill A to D, there-by triggering selection of the hours for fumigation consideration. Similarly, a warm front developing south of Calvert Cliffs could pro-duce stable upper Pasquill classes, with the lowest layer "destabilized" by warmer Chesapeake Bay waters. After elimination of these conditions from the " tower" list, there were 211 hours of fumigation conditions at the site. The following Table A-17 identifies the days eliminated because 1 of weather and general circulation criteria. J i Fumigation Adjustment Factors for y/Q and D/Q Calculations ! The necessary adjustment factors to be applied to elevated release calculations of X/Q and D/Q values because of sea breeze inversion breakup l (fumigation)havebeendetermined,asfollows: Relative concentrations resulting from inversion breakup ) conditions were determined using)the procedures developed for the Southwest Energy Studyb. Ratios of inversion breakup concentrations to those obtain-ed with elevated releases not accompanied by inversion breakup were calculated for each receptor. j
- Based upon the ratio of concentration, above, and the 1 l frequency of occurrence of inversion breakup conditions, the necessary adjustment factors for the Calvert Cliffs 1
t
'J A-43 l- TERACORPORA110N )
i
.__.M_______ __U
TABLE A-17 ELIMINATED DAYS FRCM POSSIBLE FUMIGATION Month .Date January 4, 6, 12, 13, 22, 31 February 5, 12, 14, 17, 18, 19 March 1, 12, 13, 14, 17, 30 April 8, 10, 11, 14, 15, 25, 30 May 1, 16 l J ur,e 1, 7. 29 July 1 August 26 September 13, 16, 23, 24, 25, 26 October 9, 10, 16, 17, 19, 24, 25, 30 November None l Decenter 1, 9, 10, 16, 18, 24, 31 l l A-44 l TERA CORPORATION i
site to account for the influence of inversion breakup on the relative concentrations were developed. The details of these procedures are provided in the following para-graphs. The formula used in the Southwest Energy Study to calculate maximum fumigation concentrations is:
/2nu (a + Z/8) Z where u is the mean wind speed, y o is the horizontal dispersion coeffi-cient, and Z is the depth of the layer from the ground to the centerline j of the plume, equivalent to the effective stack height minus the terrain I height. The factor Z/8 allows for additional horizontal spreading of the plume as it is mixed to the ground.
Downwind distances at which the maximum fumigation concentration l should be applied were determined by adapting the method described by Pooler(7) . A distar,ce was calculated by multiplying the average wind speed for fumigation cases by a time, mt , defined by pcp 80/az t m *( R
) (AH + 2 k) (AH/2 + ok + H s ) '
j i where p = ambient air density ' C p = specific heat at constant pressure 30/3z = potential temperature lapse rate in stable air R = net rate of sensible heating of an air column i i by solar radiation AH = plume rise 1 k = vertical diffusion coefficient, az , at an l arbitrary distance of 10 km prior to which 3 i maximum fumigation for a non-buoyant plume j should occur. H = stack height. f s The distance obtained from this formulation is approximately 8 km. There-fore, the maximum fumigation concentration equation was applied from the l 1 A-45 TERA CORPORATION 1
l minimum distances of interest out to a distance of 5 miles. This is a conservative approach since fumigation concentrations resulting from a non-booyant plume released at only a moderately high stack height would most probably peak at distances less than 5 miles. I l Since dispersion coefficients are a function of stability class as t well as distance, the class associated with fumigation occurrence is ex-tremely important in calculating concentration. Therefore an analysis a I was made to determine the specific 125-200 ft stability class assor.iated I with each of the fumigation cases. Of the three classes which could occur, there were 177 occurrences of Class E (84 percent), 28 occurrences l of Class F (13 percent), and 6 occurrences of Class G (3 percent). Based on this finding, Class E stability was used for subsequent analysis. J An average effective stack height for all Class E fumigation occur-rences was determined using the momentum plume rise model described in Regulatory Guide 1.111. The height thus determined is 72 meters. Fumigation concentration computations were made 'for all distance- ) direction combinations of interest out to five miles. Terrain heights were included after the manner specified in Regulatory Guide 1.111. That is, the maximum terrain height between the release point and any given l receptor was subtracted from 72 m to determine the Z term. A unit wind speed was assumed for each calculation since this term cancels out when the fumigation and standard concentration formulas are in ratio. Having determined a fumigation concentration for each receptor, a l calculation was then made using the standard annual average relative con-centration equation: 2
= 1 -H X/Q nuoyz o **P (2ez 2)'
where H is effective stack height (other terms as previously defined). Again, a unit wind speed was used and the effective stack height ad-justed by the maximum terrain height between source and receptor. With . these calculations completed, a ratio value was obtained for each re-ceptor by dividing standard relative concentration into fumigation con-centration. A-46 TERA CORPORATION
?
l The final adjustment factors to be applied to the unadjusted on-shore x/Q and D/Q values were determined by scaling fumigation occurrence frequency. During 1975 there were 4,139 hourly occurrences of on-shore flow. Dividing this number of fumigation occurrences (211), a scaling i multiplier of 0.051 was obtained and applied to each ratio. Final fumigation adjustment factors were obtained by adding one minus the fre- ' quency of fumigation occurrences to the scaled ratios (for. direct multi- ) plication of unadjusted relative concentration and deposition values) ) and are shown in the first section of this repert. l There are obvious uncertainties and limitations in this approach to { the determination of adjustment factors to compensate for sea breeze in- j version breakup conditions. The expression used to calculate fumigation l concentrations, for example, is a rather simplified approach to a complex event. In addition, all on-shore fumigation occurrences were treated as a single category as there were insufficient data for a directional con-sideration. Individual sectors were included when accounting for terrain height variation. 1 Another problem involves the limitation imposed by meteorological l tower height. It is conceivable that both lower and upper delta-T measure- 4 j ments could indicate unstable or neutral conditions and yet the plume
)
could actually be imniersed in a stable layer at some height above the top of the tower. Plume rise calculations indicate that there are relatively l few on-shore cases when tower data are not representative of conditions ! J affecting initial plume transport and diffusion; therefore, this is a rela- ' tively miner limitation. F. A Plume In The Sea Breeze Vertical Plane Cell Lyons and Olsson b) show that under ideal sea (or lake) breeze con-ditions, a strong circulation cell in a vertical plane perpendicular to the coast may be established. A tetroon released at the coast designed to move at constant density altitude, moved inland at 300 meters to the sea breeze front, rose to 1000 metcrs, moved back across the shore over i TERACORPORATlON
i i the cold water, descended to 300 m2ters and moved back to the shore in about 2 hours from release. The circumstances of the Lyons study were ideal for establishment of the vertical plar.3 cell. Often the return flow at talvert Cliffs is over-ridden by a general circulation which prevents its existence. It is un-likely that a pluaie emitted at Calvert Cliffs into an ideal sea breeze vertical plane cell will create recirculation which has a significant in-fluence on relative concentrations. The Lyons study shows that when the vertical plane cell does develop, the descending return flow over the cold l water (which may include plume remnants) is met by a fresh, unpolluted flow moving frou water areas further off-shore. The gases and small par- l l ticulates (2 3 n\ic,rons) tend to re.nain in the upper one-third to one-half j portions of the on-shore flow as it crosses the coast. Only larger partic-ulates sef'de down into the lower half of the on-shore flow. I Vanderhoven IO) , quoting results obtained by Chamberlain, points out that "although liberated as a vapor, (iodine) is thought also to be ab-sorbed on condensation nuclei which are too small to have an appreciable I gravitational settling velocity". Thus, although processes other than gravitational settling result in deposition of iodine from lower level plumes, the possibility of the rem- l nant of the iodine plume in the return flow of a vertical plane recircula-l tion cell depositing iodine on the ground appears to be remote. l l Similarly, noble gas constituents of the initial plume, may return to the coast as a well dispersed plume in the vertical plane recirculation cell. Nevertheless, this dispersed plume will be limited to the upper one-half to one-third of the return flow layer. It is concluded that the recirculation of plume elements in the sea breeze vertical-plane cell will not affect significantly the values deter-mined by the SLT model. TERACORPORATION
REFERENCES
- 1. U. S. Nuclear Regulatory Commission, February 1976, Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.
- 2. Memorandum E. H. Start, Deputy Chief Environmental Research Labora- l tory, NOAA to Earl H. Markee, Jr. , Meteorology Section, Nuclear Regulatory Commission, May 3,1976 with enclosures. i
- 3. Start, G. E., Wendell, L. L., 1974. Regional Effluent Dispersion Calculations Considering Spatial and Temporal Meteorological Varia- l tions, Air Resources Laboratory, NOAA Technical Memorandum ERL ARL- J
- 44. I 1
- 4. Sagendorf, Jerrold F., A Program For Evaluating Atmospheric Disper- l sion From A Nuclear Power Station, NOAA Technical Memorandum ERL i ARL-42, May 1974.
- 5. Lyons, Walter A., Olsson Lt.rs E., 1972. Mesoscale Air Pollution Transport In The Chicago Lake Breeze, Journal of the Air Pollution l Control Association, Volume 22, No.11, November 1972. i I
- 6. Van der Hoven, I., Ferber, G. J., Humphrey, P. A., et al, 1972. 1 Southwest Energy Study, report of the meteorology work group.
Draft Report prepared by the National Oceanic and Atmospheric Administration for the U. S. Department of Interior.
- 7. Pooler, F. ,1965, Potential Dispersion of Plumes from Large Power Plants, prepared for U. S. Department of HEW, P.B.-168790. !
- 8. . Van der Hoven, Deposition of Particles and Gases, Section 5-3 l Meteorology and Atomic Energy, 1958 USAEC.
TERACORPORA110N
j Item 8 - Provide a map showing the detailed topograpaice' features (as modified by the plant) on a large scale, within 10-mile rac'{ur of the plant and a plot of the ma ncem topographic elevation
> versus' the distar.ce from the center of the plant in each of the
( sixtaer 22h degree cardinal compass point sectors (centered on s true storth), radiating from the center of the plant, to a distance l 6f 10 miles.
)
i Response - A map showing the detailed topographical features nn a large scale within a 10-mile radius of the plant is provided as Figure A-10, attached to this report. 1 1 Plots of the maximum topographic elevation versus distance from the center of the plant in each of tlw nirie 2L% degree j cardinal compass point sectors, radiating from the center of the plant in a landward direction, to a distance of 10 miles, e l are provided in the following Figures A-1 through A-9. 40te" !' the relatively small elevation changes indicating flat, rolling terrain. Item 9 - Provide the dates and times of radioactivity releases f rom inter-mittent sources by source location based on actual plant operation / and, if available, appropriate hoerly meteorological data (i.e., l wind direction and speed, and atl.iospheric stability) during each period of release. Response - Calvert Cliffs Nuclear Unit 1 completed its first full year of commercial operation in May 1976. Since item (5) of Enclosure 1,
" Effluent Release Data.," requires " excluding the first year of reactor operation" and because Calvert Cliffs tiuclear Urit 2 is currently in the process of obtaining its operating license, this paragraph doa not apply to Calvert Cliffs Nuclear Units 1 and E.
i
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l 1 I i 1 i a i d APPENDIX B j Wind Speed, Direction, and Stability Frequency Tables Calendar Year 1975 i
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