ML19340E145

Control Room Habitability Evaluation,Brunswick Steam Electric Generating Plant

ML19340E145
Person / Time
Site:	Brunswick
Issue date:	12/31/1980
From:	William Arcieri, Broadhurst R, Slider J NUS CORP.
To:
Shared Package
ML19340E142	List: ML19340E141 ML19340E145
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.3.4, TASK-TM NUS-3697, NUDOCS 8101060498
Download: ML19340E145 (112)

Text

{{#Wiki_filter:! i l l NUS-3697 CONTROL ROOM HABITABILITY EVALUATION BRUNSWICK STEAM ELECTRIC PLANT INRC TMI ACTION PLAN ITEM llI.D.J.4) l l I l Prepared for CAROLINA POWER & LIGHT COMPANY By J. E. Slider E. R. Schmidt W. C. Arcieri R. W. Speidel R. H. Broadhurst D. A. Studley l R. W. Jubach G. D. Whittier l F. M. Quinn December 1980 Approved by: C O B.3.~ Naft. ManagN ' Licensing & Technology Consulting Division NUS CORPORATION 4 Research Place Rockville, Maryland 20850 01 C 'l {}f y- -.n- - - -ep. v ya-- y --e, --p n y-- --,g,--r--,y-y w ,-r ye, y 3 -g-9-

TABLE OF CONTENTS Section Title Page No. LIST OF TABLES 111 LIST OF FIGURES V 1.0 PREFACE AND

SUMMARY

l-1 2.0 SURVEY OF POTENTIALLY HAZARDOUS MATERIALS 2-1 3.0 ATMOSPHERIC DISPERSION ANALYSES 3-1 4.0

SUMMARY

OF HEATING, VENTILATING, AND AIR-CONDITIONING (HVAC) DESIGN REVIEW 4-1 5.0 RADIOLOGICAL ANALYSIS 5-1 6.0 TOXIC CHEMICAL ANALYSIS 6-1 APPENDICES APPENDIX A COMPARISON OF THE BRUNSWICK CONTROL ROOM TO THE CRITERIA OF THE STANDARD REVIEW PLANS 6.4, 9.4.1, AND 6.5.1 A-1 APPENDIX B ADDITIONAL INFORMATION REQUIRED BY THE NRC B-1 APPENDIX C JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED AND WIND DIRECTION BY ATMOSPHERIC STABILITY CLASS JANUARY 1, 1976 - DECEMBER 31, 1979 C-1 APPENDIX D BRUNSWICK ONSITE METEOROLOGICAL MEASURE-MENTS PROGRAM D-1 APPENDIX E METHODS USED IN RADIOLOGICAL ANALYSIS E-1 11 NUS COPPCAATICN

LIST OF TABLES Table No., Title Page No. 2-1 Hazardous Chemical Information Contacts 2-6 2-2 Hazardous Chemical Sources Identified 2-8 3-1 Adjustment Factors Used to Calculate Effective Relative Concentrations for Selected Time Intervals, Brunswick Unit 1 3-8 3-2 Adjustment Factors Used to Calculate Effective Relative Concentrations for Selected Time Intervals, Brunswick Unit 2 3-9 3-3 Calculated X/Q Values at the Control Room Intake for Radiological Releases From Brunswick Units 1 and 2 Containments 3-10 3-4 Calculated X/Q Values at the Control Room Intake for Radiological Releases From the 100-Meter Stack 3-11 3-5 One Hour X/Q Values for the Toxic Chemical Analysis at Brunswick 3-12 5-1 Assumptions in Radiological Analysis of the Brunswick Control Room 5-5 5-2 Results of Radiological Analysis of the Brunswick Control Room 5-6 6-1 Summary of Input Data 6-7 6-2 Results of Toxic Chemical Analysis 6-8 D-1 Operating Conditions D-5 l D-2 Major Components D-6 D-3 Operational Sensor Elevations D-7 D-4 Component Accuracy D-8 E-1 Nuclide Decay Constants and Fission Yields E-14 iii NUS COAPC AATICN

LIST OF TABLES (Continued) Table No. Title Page No. E-2 Average Bota and Gamma Energies and Iodine Inhalation Dose Conversion Factors E-15 E-3 Isotopic Gamma Energies and Decay Fractions E-16 E-4 Absorption Coefficients for Air E-18 l l [ l l iv NUS CC APC AATICN

4 1 i ) LIST OF FIGURES i Figure No. Title Page No. 2-1 Southport-Cape Fear River Area, North l Carolina 2-9 4-1 Schematic Diagrati of the Control Room Ventilation System, Brunswick--Air Flow Diagram for High Radiation Isolation 4-8 4-2 Schematic Diagram of the Control i.com Ventilation System, Brunswick--Air Flow Diagram for Chlorine Isolation 4-9 4-3 Partial Plot Plan, Brunswick Units 1 { and 2 4-10 4 5-1 Brunswick Control Room HVAC System j Flow Diagram 5-7 i 6-1 Simplified Brunswick Control Room Ventilation System 6-9 E-1 Dose Model Activity Flow Schematic E-19 i l l l l V NUS CC APC AATICN

4 1.0 PREFACE AND

SUMMARY

In the past year, the U.S. Nuclear Regulatory Comr.ission (NRC) developed a comprehensive list of new requirements based on the recommendations of the cany studies of the accident at Three Mile Island (TMI) Unit 2. This list was formally released in May 1980 as NRC's TMI Action Plan (NUREG-0660). By letter dated May 7, 1980, Darrell G. Eisenhut of the NRC directed all operat-ing reactor licensees to address five items identified by the NRC as being applicable to operating reactors. One of these was Item III.D.3.4, " Control Room Habitability." In requiring licensees to address Item III.D.3.4, the NRC sought "to assure that workers (plant operators) are adequately pro-tected from radioactivity, radiation, and other hazards, and that the control room can be used in the event of an emergency." The NRC required that all facilities that have not been reviewed for conformance to current NRC requirements be evaluated against these requirements by January 1, 1981. Most of these requirements have been promulgated since 1975 and any plants licensed after the promulgation of these requirements have generally had to conform to them or to justify nonconform-ance to them. Plants licensed before the promulgation of these requirements, such as Brunswick Units 1 and 2, have generally not had to address conformance or to justify nonconformance. " Current requirements" identified by the NRC in Action Plan Item III.D.3.4 include the following: e Standard Review Plan Sections 2.2.1 and 2.2.2, "Identi-fication of Potential Hazards in Site Vicinity" e Standard Review Plan Section 2.2.3, " Evaluation of Poten-tial Accidents" l-1 NUS CC A AC AAT!CN l l.,. - _..,. _ _

e Standard Review Plan Section 6.4, " Habitability Systems" The NRC also stated that the following guides could be used in performing this evaluation: o Regulatory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room Dur-ing a Postulated Hazardous Chemical Release" e Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Rcom Operators Against an Accidental Chlorine Release" e K. G. Murphy and K. M. Campe, " Nuclear Power Plant Control Room Ventilation System Design for Meeting General Design Criterion 19," 13th Atomic Energy Commission Air Cleaning Conference, August 1974 The NRC's position on this study has been clarified by NUREG-0737, issued October 31, 1980. These clarifications emphasize the NRC's interest in assuring control room habitability under accident conditions and in identifying and correcting potential weaknesses in the design of older control room habitability systems. Frcm the description of Action Plan Item III.D.3.4 and Eisenhut's letter, it was determined that this study should focus on two objectives: 1. Assessment of the present condition of the habitability equipment installed in the plant 2. Evaluation of the control room operator exposures under the present condition of the habitability systems l-2 NUS COPPCAATION

i To accomplish the first objective, the installed equipment was inspected and the plant design features and layout were examined. The mechanical equipment and plant design were compared with the j criteria specified by the NRC. The extent of the mechanical de-sign review is described in Section 4.0. The point-by-point com-parison of the current plant design with the NRC criteria is given in Appendix A of.this report. The second objective was accomplished by conducting radiological i and toxic chemical habitability analyses. In preparation for these analyses, a considerable amount of plant design, systems l operation, and maintenance information was reviewed. Sources of information useful to this study included the following: o Plant personnel 1 e Personal observations e Plant drawings i e Final Safety Analysis Report e Plant modification descriptions e Plant system descriptions e Operating procedures e Periodic test procedures e Preoperational test procedures e Technical specifications e Environmental Report e Environmental Impact Statement In addition, an extensive survey of the plant environs was con-ducted to identify potential sources of toxic chemical hazards within the prescribed 5-mile radius of the plant. The scope and results of the survey are described in Section 2.0 of this report. From these sources, the assumptions shown in Section 5.0 for the radiological analysis and in Section 6.0 for the toxic chemical analysis were developed. The site meteorological analysis for estimation of dispersion factors is presented in Section 3.0. 4 1-3 NUS CCAPCAATICN

The results obtained from the radiological analysis are presented in Section 5.0 of this report (the methods used in the radiologi-cal analysis are described in Appendix E) and show that the opera-tor doses are within NRC General Design Criterion 19 without con-sideration of main steam isolation valve leakage. The methods used in the toxic chemical analysis are described in Section 6.0 of this report and conform to Regulatory Guides 1.78 and 1.95. Appendix B presents specific information requested by the NRC in the clarification letter. l l l l l t 1-4 NUS CC A AC A AT:CN

/ 2.0 SURVEY OF POTENTIALLY HAZARDOUS MATERIALS In accordance with the directions in Eisenhut's letter of May 7, j 1980, a survey of the Brunswick site vicinity was conducted to identify locations of chemicals stored or transported within 5 miles of the plant which, if accidentally released, might present a hazard to control room cperators. The focus of the survey was a the determination of locations, quantities, transportation, stor-age, and use of the toxic chemicals listed in the Appendix of NUREG-0570 (Ref. 1). The survey was conducted for an area within approximately a 10-mile radius of the plant, to ensure identifica-1 tion of potential hazards adjacent to the 5-mile radius of the required study area. I A large, potential source of a hazardous chemical is found onsite at Brunswick. Liquefied compressed chlorine gas is used in the service water system and kept at the site near the service water intake :tructure approximately 450 feet from the control room air intake. As described in the Brunswick Final Safety Analysis Report (FSAR), the chlorine is obtained, stored, and used directly from a 55-ton rail tank car. The potential effects of the rupture of this tank car were analyzed in the FSAR (page M14.5-1) and were shown to be acceptable. General characteristics and significant features of the Brunswick site are described in the FSAR. The study area is a uniform coastal plain situated along the Atlantic Ocean and the Cape Fear River, about 25 miles south of Wilmington, North Carolina. As shown in Figure 2-1, the study area includes the city of South-port, North Carolina; several beach communities and adjoining built-up areas; and rural portions of Brunswick County. The principal highways serving the area are North Carolina Routes (NC) 211, 133, and 87. The area is also served by connections to the Seaboard Coast Line Railroad system via the federally owned and operated rail line to the Sunny Point Terminal. 2-1 NUS CC AAQAATiCN

The site study began by initial telephone and reconnaissance con-tacts with local business, industry, and governmental represen-tatives to identify potential chemical users and key contacts. These discussions were followed by a field survey and by personal interviews with the key contacts. Field observations and initial contacts led to secondary contacts and clarification of informa-tion found in maps and other published references. Federal and State governmental agencies were contacted to deter-l mine whether they had jurisdiction over or information on hazard-cus chemicals in the area; these agencies were expected to be the primary sources of information on the transportation of hazardous chemicals. The Family Lines Railroad (Seaboard Coast Line) was contacted directly. Table 2-1 shows the principal contacts that corroborated other i sources or provided information on nonstationary hazards in the Brunswick area. 2.1 Key Sources Identified The key sources surveyed and pertinent data on hazardous chemicals identified in this study are listed in Table 2-2, and these data are presented graphically in Figure 2-1. Important points about these sources are amplified below: e Standard Products. All of the chemical storage containers at Standard Products are confined within 3-to 4-foot cinderblock berms. Eight 47,000-pound loads of sulfuric l acid are delivered to the plant each year. Two 20,000-gallon shipments of caustic soda and two 500-gallon ship-ments of chlorine are also delivered to the plant each year. All shipments are delivered by truck, primarily from Wilmington, North Carolina. Some shipments may use NC 87/133, which, at its closest point, is 1.4 miles from the plant. 2-2 NUS CCAAC AATICN

1 i e Pfizer Chemical Company. Pfizer Chemical uses and stores "large amounts" of sulfuric acid for making citric acid. j Details on quantities and shipments could not be obtained due to proprietary protection. The chlorine on the site is used for " housekeeping" purposes. A rail spur from the U.S. Government line to Sunny Point i serves the Brunswick plant. The Pfizer Chemical Company uses this spur at a transfer point approximately 3.2 miles from the Brunswick station; as previously stated, no de-tails on their shipments are known at this time. e Sunny Scint Military Ocean Terminal. The Sunny Point Mili-tary Ocean Terminal is a major U.S. Department of Defense installation for the movement of conventional ammunition and weapons overseas. The Military Traffic Management Com-mand indicated, in a briefing October 2, 1980, that no chemical or biological weapons were handled at Sunny Point. The only potentially hazardous chemicals likely to be at the site are those used domestically at Sunny Point and the fuel of Lance missiles shipped through Sunny Point. Each Lance missile contains 375 pounds of liquid hydrazine and 1107 pounds of red fuming nitric acid. This fuel is contained within the missile during its shipment and tem-porary storage. Each missile is individually protected against rough handling; they have been drop-tested success-fully from 40 feet. Furthermore, the terminal is ringed by a 4600-acre buffer zone on the west side of the Cape Fear River. Inspection, storage, and holding areas are designed with blast-restricting earthen berms, and the nearest area to the Brunswick plant is a rail holding yard 2.0 miles from the plant. The bermed area is about 270,000 square feet with berms ranging from 10 to 15 feet in height. 2-3 NUS CC APOAATICN

The chemicals used domestically include sulfuric acid, trichloroethylene, and chlorine, as listed in Table 2-2. The chlorine is used in 150-pound cylinders attached to seven wells scattered around the post. The other chemi-cals are used in maintenance operations. o Brunswick County Department of Public Works. The Bruns-wick County Department of Public Works uses ten 1-ton chlorine cylinders at its waterworks. The waterworks, however, is over 6 miles from the Brunswick plant. e Intracoastal Waterway (ICW). Research to date suggests that significant quantities of chemicals are shipped on the Cape Fear River segment of the ICW below Wilmington. Information received to date from governmental and in-dustrial sources indicates, however, that little of this traffic consists of hazardous chemicals. One waterway user, W. R. Grace Company of Wilmington, ships approxi-mately 9400 tons of anhydrous ammonia in a four-tank barge every 3 weeks; occasionally this shipment may reach 10,000 tons in a five-tank barge. Approximately 10,000 tons of ammonia nitrate are shipped once in every 10-month period. The Chlorine Institute indicated that, to its knowledge, no chlorine was shipped over the Cape Fear segment of the ICW and no evidence contradicting this has been found to date. 2.2 Additional Information Being Sought Additional information has been requested from several sources to quantify the potential for truck accidents on NC 87/133 and NC 211 l and shipping accidents along the ICW involving hazardous chemicals. l Additional information on rail shipments of hazardous chemicals has been requested from Seaboard Coast Line to quantify the use of hazardous chemicals at Pfizer Chemical Company, 2-4 NUS CCAPCAATICN

1 The toxic chemical analysis in Section 6.0 of this report provides l a bounding analysis of toxic chemical release on the ICW. [ 2.3 Reference 1. U.S. Nuclear Regulatory Commission. 1979. NUREG-0570, " Toxic Vapor Concentrations in the Control Room Following a Postulated f Accidental Release." l l 4 1 F i I 1 h i 2-5 NUS CCAPCRAT!CN

TABI.E 2-1 !!AZARIXXIS CllEMICAL INFORMATION CONTACTS Contact Location Information Type National liighway Traffic Safety Washington, DC II4zardous shipments Administration Federal Highway Administration Washington, DC llazardous shipments, accident incidents Federal Railroad Administration Washington, DC Rail shipments U.S. Environmental Protection Agency Washington, DC 'Ibxic substance monitoring U.S. Army, Military Traffic Arlington, VA Sunny Point Terminal Operations Management Conunand U.S. Army, Redstone Arsenal iluntsville, AL lance Missile Program to i U.S. Maritime Administration Washington, DC Intracoastal Waterway (ICW) shipments m U.S. Coast Guard, 5th District Wilmington, NC ICW shipments North Carolina Department of Iluman Raleigh, NC llazardous materials monitoring Resources North Carolina Department of Commerce Raleigh, NC llazardous materials information North Carolina Department of Raleigh, NC llazardous shipments Transportation Southport Fire Department Southport, NC Incidents, emergency plans, general background Z h Southport Police Department Southport, NC Incidents, emergency plans, general g background O Il B O D d O2

TABLE 2-1 IIAZARDOUS CilEMICAL INF014MATION CONTACTS (continued) Contact Location Information Type Brunswick County Bolivia, NC liighway and rail information Seaboard Coast Line Railroad Jacksonville, FL Rail shipments Dupont Chemical Wilmington, NC llazardous chemical shipments on ICW liercofina Chemical Wilmington, NC Hazardous chemical shipments on ICW Brunswick Energy Company Southport, NC Hazardous chemical shipments on ICW Paktank Chemical Wilmington, NC Hazardous chemical shipments on ICW W. R. Grace Company Wilmington, NC liazardous chemical shipments on ICW u 3 The Chlorine Institute New York, NY llazardous chemical shipments on ICW 2 C Ul O O 11 110 11 d O2

4 TABI.E 2-2 IIAZARDOUS CllEMICAL SOURCES IDIMPIFIED 1 Storage Characteristics Numler of Quantity / Inside/ Distance from Company /Facili ty Chemical Tyie Units Unit Outside Plant (mi) Standard Products Sulfuric acid Tank 2 20 tons Outside 2.2 Caustic soda Tank 1 20 tons Outside 2.2 3' Chlorine Cylinder 3 1 ton Outside 2.2 Pfizer Chemical Chlorine Cylinder 1 220 ft3 1.4 Company Sulfuric acid ~ See text 1.4 Sunny Point Trichloroethylene Drum 1 55 gal. Indoors 2.0 (min) Military Ocean Sulfuric acid Carboy Numerous 5 gal. (200 Indoors 2.0 (min) Terminal gal. total) Chlorine Cylinder 7 150 lb Outdoors 2.0 (min) ra Nitric acid Lance 1,107 lb per Outdoors missiles missile Brunswick County Chlorine Cylinder 10 1 ton Outside 6.1 Deparcment of Public Works Intracoastal Several (see text) Barges / ships N/A 2.3 Waterway Z C ID O O Il 11 O i Il i ~ t 3O Z

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l 3.0 ATMOSPHERIC DISPERSION ANALYSES Atmospheric dispersion estimates were calculated for both the radiological release and toxic chemical release analyses for the control room habitability assessment. Calculations were made of relative concentrations (X/Q values) at the control room air intake based on appropriate conservative models and methodology selected for the particular release-point characteristics and dose assess-ment methodology. Values of X/Q were computed considering the fol-lowing NRC guidelines: e Regulatory Guide 1.145, " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants" e Regulatory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release" e Standard Review Plan 6.4, " Habitability Systems" o NUREG/CR-1152, " Recommended Methods for Estimating Atmos-pheric Concentrations of Hazardous Vapors After Accidental Release near Nuclear Reactor Sites" e NUREG-0 570, " Toxic Vapor Concentrations in the Control Room Following a Postulated Accidental Release" e NUREG/CR-1394, " Diffusion near Buildings as Determined from Atmospheric Tracer Experiments" " Nuclear Power Plant Control Room Ventilation System Design e for Meeting General Criterion 19," Murphy and Campe, 13th Atomic Energy Commission Air Cleaning Conference 3-1 NUS CCAPC AAT!CN ~

l Two types of releases were analyzed for Brunswick for the radio-logical assessment. The X/Q values were calculated at the intake for (1) releases from both the Unit 1 and Unit 2 containments and (2) releases from the 100-meter stack. Because of the location of the release points and intake relative tn surrounding buildings and because of the different release modes, the two releases were analyzed with different methods. Figure 4-3 shows the relative locations of the potential release points and the intake. The dispersion analyses for the toxic chemical assessment are based on offsite releases transported toward the plant. The X/Q values were calculated at various distances and equivalent wind speeds were calculated for a determination of effluent travel times. The methodology and meteorological data used to calculate the X/Q values are discussed in the following sections. 3.1 Calculations - Radiological Releases 3.1.1 Radiological Releases - Units 1 and 2 Containments 1 1 The X/Q values for radiological releases from the two containments were calculated based on procedures outlined in References 1, 2, and 3. These releases were assumed to be from a diffuse source (i.e., activity leaking from many points on the surface of the containment) with a point receptor (a single intake). Each con-l tainment was analyzed separately. The X/Q values were calculated for time periods of 0 to 8 hours, 8 to 24 hours, 1 to 4 days, and 4 to 30 days (Ref. 3). t cor the 0- to 8-hour calculation, results of recent analysis of diffusion tests near buildings were used (Ref. 2). The results of these tests have shown that for most meteorological combinations of atmospheric stability and wind speed, the model and methodology provided in Reference 1 overestimate the concentration, usually by 3-2 NUS CC A AC AAT:CN I L

one to two orders of magnitude. Because of this large overestima-tion of the NRC model, the 0- to 8-hour X/Q value was calculated j based on the recommendations of Reference 2. The studies provided in the reference were conducted at two dissimilar sites with con-tainment areas differing by nearly a factor of two. Consistency between the two data sets of measured concentrations was obtained by scaling the plume path length by the square root l of the minimum cross-sectional area of the containment, as long i l as this scaled distance was less than 1.0. Using this approach and Figure 9 of Reference 2, a 1-hour X/Q value (conservatively assumed to apply for 0 to 8 hours) for Brunswick can also be calculated. The assumptions for this determination are outlined below. Units 1 and 2 Containment cross-sectional area = 2095 m2 Minimum distance to intake = 38 m Scaled distance = 0.83 X/Q from Figure 9 = 1.7 x 10-3 sec/m3 l The X/Q values for the remaining time periods (8 to 24 hours, 1 to 4 days, and 4 to 30 days) were calculated using the method-ology in Reference 1. Analysis of the plant building configura-tion indicates that five wind sectors could affect the intake for releases from both Units 1 and 2. For releases from Unit 1, winds j from the northeast through southeast were used in the analysis. For Unit 2 releases, winds from the southeast through southwest were used. Data from these wind sectors were then used to obtain the necessary wind speed and direction factors. I l l I 3-3 NUS CC APCAATION

These factors are Unit 1 s/d ratio = 0.89 Wind sectors = NE, ENE, E, ESE, SE Wind speeds (10 m) 5 percent = 0.88 m/s 10 percent = 1.33 m/s 20 percent = 1.99 m/s 40 percent = 3.10 m/s Wind direction frequency = 21.84 percent Unit 2 s/d ratio = 0.89 Wind sectors = SE, SSE, S, SSW, SW Wind speeds (10 m) 5 percent = 1.20 m/s 10 percent = 1.77 m/s l 20 percent = 2.61 m/s 40 percent = 3.98 m/s Wind direction frequency = 34.73 percent Factors used to adjust the X/Q values are provided in Tables 3-1 and 3-2; the X/Q values are provided in Table 3-3. The meteoro-logical data used in the calculations are discusned in Section 3.3. 3.1.2 Radiological Releases - 100 Meter-Stack l Releases from the 100-meter stack necessitate a different type of analysis from those of the two containment structures. Because l the stack is freestanding, a 100 percent elevated release was as-t l sumed. The methodology of Regulatory Guide 1.145, then, was used to analyze these releases using only those meteorological condi-tions associated with wind directions that could affect the intake l i 3-4 l NUS CC APCAATION

if effluents were released from the stack (Ref. 4). These wind directions were determined to be southeast, south-southeast, and south. The 0.5 percent X/Q (assumed to be the O-to 2-hour value) and the fumigation X/Q were calculated in each of the three af-fected downwind sectors and the maximum values were chosen for the evaluation. Because the Brunswick plant is located greater than 3200 m inland, the fumigation X/Q is applied to the first one-half hour of the accident. For time periods greater than 2 hours, the values were determined by logarithmic interpolation between the 2-hour and the annual average values. The assumptions used in this analysis are outlined below. Stack Affected downwind sectors = NW, NNW, N Downwind distance = 190 m Release height = 100 m Receptor height = 25 m Building wake = None The X/Q values for the stack releases are provided in Table 3-4. Meteorological data used in the analysis are discussed in Sec-tion 3.3. 3.2 Calculations - Toxic Chemical Releases l 1 X/O values were calculated to support the toxic chemical analysic discussed in Section 6.0. These X/Q calculations produced con-tinuous release (1 hour), direction-independent X/Q values (shown in Table 3-5) at a series of distances out to 5 miles from the plant. The calculations used Equation 1 of Regulatory Guide 1.145 (Ref. 4), without the building wake credit or plume meander. From these calculated values of X/Q, the corresponding wind speed i was calculated (based on a representative atmospheric stability 3-5 NUS COAAQAATICN

i class of extremely stable, G) for use in the atmospheric disper-sian analysis discussed in Section 6.0, 3.3 Meteorological Data Meteorological data for the atmospheric dispersion analyses were collected at the site during the 4-year period January 1, 1976, through December 31, 1979. The data used for each analysis are listed below. 3 Atmospheric Wind Speed / Combined Data Analvsis Stability Wind Direction Recovery (%) Radiological N/A ll-m level (wind 98

releases, speeds converted containment to 10 m)

Radi0 logical T105-11 m 105-m level (wind 98

releases, speeds converted stack to 100m)

Toxic chemical T105-11 m ll-m level (wind 98 releases speeds converted to 10 m) t The joint frequency distributions of wind speed and wind direc-tion, by atmospheric stability class for both the 11-and 105-i meter levels, are provided in Appendix C. A brief description of the onsite meteorologic?.1 system is provided in Appendix D. 3.4 References 1. K. G. Murphy and K. M. Campe. 1974. " Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterien 19." 13th Atomic Energy Commission Air Cleaning Conference. 3-6 i NUS CCARCAATION

l l l l l 1 t l 2. J. F. Sagendorf, N. R. Ricks, G. E. Start, and C. R. Dickson. 1980. Diffusion near Buildings as Determined from Atmoscheric Tracer Exceriments. Technical Memorandum ERL ARL-84, National Oceanic and Atmospheric Administration. l 3. U.S. Nuclear Regulatory Commission. Standard Review Plan, NUREG-75/087, Section 6.4, " Habitability Systems." 4. U.S. Nuclear Regulatory Commission. Regulatory Guide 1.145, " Atmospheric Dispersion Models for Potential Accident Conse-quence Assessments at Nuclear Power Plants." l l l l l l 3-7 l NUS CCRACAATICN l 1 t

TABLE 3-1 ADJUSIMENT FACICRS USED IO CALCULATE EFFECTIVE RELATIVE CONCENTRATIONS 10R SELECTED TIME INTERVALS, BRUNSWICK UNIT 1 Adjust.nent Time Interval Factor 0-8 Hr 8-24 Er 1-4 Days 4-30 Days Wind speed 1.0 0.67 0.45 0.29 Wind direction 1.0 0.80 0.61 0.22 Occupanef 1.0 1.0 0.60 0.40 overall reductiona 1.0 0.54 0.16 0.026 aThe overall reduction factor is defined as the products of the wind speed factor times the wind direction factor ti:nes the occupanef factor. 3-8 NUS CC AAQAATION

TABLE 3-2 ADJUSTMENT FACTORS USED TO CALCULATE EFFECTIVE RELATIVE CONCENTRATIONS FOR SELECTED TIME INTERVALS, BRUNSWICK UNIT 2 ) Adjustment Time Interval Factor 0-8 Hr 8-24 Hr 1-4 Days 4-30 Days Wind speed 1.0 0.68 0.45 0.30 Wind direction 1.0 0.84 0.67 0.35 Occupancy 1.0 1.0 0.60 0.40 overall reductiona 1.0 0.57 0.18 0.042 aThe overall reduction factor is defined as the products of the wind speed factor times the wind direction factor times the occupancy factor. l l l 3-9 NUS CO APCAATION l ?

f } TABLE 3-3 i CALCUIATED X/Q VALUES AT THE CONTROL ROCM INTAKE FOR RADIOIDGICAL RELEASES FRCM BRUNSWICK CNITS 1 AND 2 CONTAINMENTS (includes occupancy factor) Unit 1 Unit 2 Time Period X/Q (sec/m3) X/Q (sec/m ) 3 0-8 hours 1.7 x 10-3 1.7 x 10-3 ~ 8-24 hours 9.2 x 10 9.7 x 10-4 1-4 days 2.7 x 10-4 3.1 x 10-4 1 4-30 days 4.4 x 10-5 7,1 x 10-5 t 3-10 NUS CCP ACAATION

TABLE 3-4 CALCUIATED X/Q VALUES AT THE BRUNSWICK CONTROL I ROOM INTARE EUR RADIOIOGICAL RELEASES FROM THE 100-METER STACKa (includes occupancy factor) 3 Time Period X/Q (sec/:n ) 0-1/2 hour (fumigation) 3.3 x 10-4 1/2-8 hours 1.8 x 10-6 8-24 hours 1.1 x 10-6 1-4 days 2.0 x 10-7 4-30 days 2.7 x 10-8 aThese X/Q values were calculated for use in the control room habitability analysis and are not intended for other applications. l l i l l 3-11 NUS CCAPC AATICN

TABLE 3-5 ONE HOUR X/Q VALUES FOR THE 'IDXIC CHEMICAL ANALYSIS A? BRUNSWICKa (1976-1979 onsite data, 11 m winds, aT104-11 m, no meander, no building wake, no initial plume volume, 5% direction-independent) 3 X/Q (sec/m ) Distance (m) Brunswick 100 5.2 x 10-2 500 3.4 x 10-3 1000 1.0 x 10-3 1500 5.4 x 10-4 2000 3.5 x 10-4 2500 2.6 x 10~4 3000 2.0 x 10~4 4000 1.4 x 10-4 5000 1.0 x 10~4 6000 8.1 x 10*; 7000 6.7 x 10-5 b.6 x 10-5 8045 (5 miles) 5 aThese X/Q values were calculated for use in the control room habitability analysis and are not intended for I other applications. b aximum sector-dependent X/Q value M greater (Regulatory Guide 1.145 0.5%) than indicated. r l ( l NUS CCAAQAATION l

4.0

SUMMARY

OF HEATING, VENTILATING, AND AIR-CONDITIONING (HVAC) DESIGN REVIEW

4.1 System Description

The Brunswick control building is of tornado-proof Class I con-struction and is located between the Unit 1 and the Unit 2 reactor buildings. The control room HVAC equipment is located in a pent-house on the roof of the control building at an elevation of 70 feet, 0 inch. Areas that are conditioned (room design, 75'F, 50 percent relative humidity) are the control room, the computer rooms, and the elec-tronic workrooms for Units 1 and 2. The remainder of the building, including the battery rooms, the mechanical equipment room, the cable spreading areas, spaces containing the motor control centers, and unit substations receive unconditioned ventilating air. Each computer room has an individual air-handling unit and condensing unit located within the electronic equipment room. Outside air is taken into the control building through supply dampers (tornado check valves, which are designed to prevent flow reversal due to a sudden drop in outside air pressure). The air passes through a roll filter and is used for pressurization of the control building, for makeup ventilation air to the conditioned spaces, and for ven-tilation of all other spaces. Air is exhausted from the building l

• hrough exhaust valves (tornado check valves).

1 I There are three separate air-conditioning systems located in the mechanical equipment room: one serves Unit 1, one serves Unit 2, and the 'ch'.cd one is a common spare that can serve either unit. Each system contains a supply air fan, cooling coil, 15-kW heat-ing element, and compressor-condenser unit. l l Two out of the three systems are normally operating. The two operating air-conditioning systems circulate conditioned air to their respective areas in the control room. The systems introduce 4-1 NUS CCAPCAATICN

2000 cubic feet per minute (cfm) of outside air to the control room as makeup to pressurize this space. There is a roll filter in the return air plenum; this filter and the outside air filter have an Air Filter Institute weight method efficiency of 80 to 85 percent. Two radiation monitors located in the control building air inlet plenum are provided to protect against the intake of contaminated outside air. Figure 4-1 illustrates the state of the control room HVAC system following isolation on a high radiation signal. Should either monitor detect high radiation, the control room an-nunciator will be actuated and the following control actions will occur automatically: a. The normal fresh air intake and exhaust dampers of the ventilation system in the control and electronic equip-ment rooms are closed. b. The emergency bypass ventilation system is placed in service to filter 1000 cfm of recirculated air and 1000 cfm of outside air to cleanup and to pressurize the control room air and to provide fresh breathing air. c. Carbon filters are automatically placed in service with the filters in the recirculation duct. d. The cable spreading room ventilation systems are shut down to protect these areas from the intake of poten-tially contaminated outside air, e. The mechanical equipment room ventilator fan is shut down to reduce the intake of potentially contaminated outside air into the mechanical equipment room. 4-2 NUS CCAPCAATICN

f. The control building exhaust fan is shut down and the 1000 cfm return air from the washroom is shunted through the emergency filters. Should smoke-filled air be drawn into the control room, smoke detectors within the control room will alarm. Controls are avail-able to reduce the volume of normal makeup air, and/or to place the bypass ventilation system filter trains in service. l Chlorine protection is provided by six chlorine detectors: two detectors are mounted at the control room air intakes; two detec-I tors are attached to the wall of the service water intake struc-ture immediately adjacent to the rail siding where the chlorine tank car is located; two detectors are located inside the chlor-ination building. The first two locations are inside or on the outer wall of Class I structures and are seismically protected. The detectors have a sensitivity of 1 part per million or better and a response time of less than 3 seconds. Detection of high chlorine concentration in the chlorination building alarms in the control room and at the sensor location. Detection of high chlorine concentration at the tank car siding ( or in the control room air intake will alarm in'and automati-cally isolate the control room. Figure 4-2 illustrates the state of the control room HVAC system following isolation on a high chlorine signal. Isolation consists of closing the out-side air makeup damper, termination of ventilation air to both the mechanical equipment room and cable spreading rooms, and stopping the control building exhaust fan. The emergency re-circulation system fans do not operate during chlorine isola-tion, to prevent degradation of the charcoal filters by chlorine contamination. Each cable spreading room and battery room and the mechanical equipment room have an individual supply and exhaust fan. The battery rooms are held at a negative pressure with respect to 4-3 NUS CC APC AATICN

the control building to ensure that hydrogen fumes do not enter other areas of the building. The ventilation systems for the mechanical equipment room and the cable spreading rooms are auto-matica11y shut down on either the high radiation or the chlorine signal. The ventilation systems for the battery rooms continue [ to operate during an emergency. ~ Figure 4-3 shows the location of the control room air intake, the plant stack, the reactor buildings, and the service water intake structure. l l 4.2 Design Review t I The control room ventilation system and areas adjacent to the con-trol room were reviewed to assess the level of protection provided l for the control room occupants during a postulated design basis l l radiological release or a toxic chemical release. This assessment l was performed by comparing the plant design with the guidance pro-vided in NRC Standard Review Plan 6.4. The results are summarized i below. a. The zone serviced by the control room ventilation system includes all critical areas, such as the control room, kitchen, sanitary facility, the computer rooms, and the electronics rooms. Areas not requiring access are ex-cluded from the zone by closed doors, b. The capacity of the control room in terms of the number of people it can accommodate for.any extended period of time was reviewed. Makeup air (1000 cfm) is provided to ensure that carbon dioxide levels do not become excessive. Though the control room for Unit 1 and Unit 2 is very large, there is-little open floor area for storage of emergency food, cots, and blankets. .The emergency food stockpile is currently stored in a locked cabinet in the 4-4 NUS CO APC AATION - ., -. ~...

Unit 1 cable access way. Breathing apparatuses are cur-rently stored in the Unit 2 cable access way with the other emergency supplies. Both areas are outside the control room ventilation zone. c. The control room ventilation system layout and functional design were reviewed to determine flow rates and filter efficiencies. The control room system design air flow is 20,000 cfm recirculation by each of two supply fans and 2000 cfm makeup and pressurization flow. Preopera-tional testing confirmed that this flow was sufficient to maintain a positive pressure in the control room during normal operation. d. The design of the emergency filter system was reviewed. The system design differs from some of the criteria of Standard Review Plan 6.5.1, as indicated in Appendix A of this report. For example, the emergency filter design does not include a HEPA downstream of the charcoal, and does not include instrumentation in the control room to signal, alarm, and record pressure drop and flow rate. e. The layout of the control room and adjacent areas was reviewed. There are several routes by which potentially contaminated outside air could enter the control room, including the following: e Direct infiltration through penetrations from the cable and battery rooms below the control room Leakage through the normal outside air makeup damper e (closed on radiation and chlorine isolation signals) e Leakage into the control room air ducts in the mech-anical equipment room 4-5 NUS CC AACAATION

e Leakage into the control building elevator shaft, into the control building stairwells, and through the control room doors e Leakage into the Unit 2 cable access way via openings in the cable penetration cutout to the rattlespace between the control and reactor buildings A summary of key leakage calculations (based on ASHRAE Equipment specifications and Fundamentals) is given below. The normal control room system airflow rate is 40,000 cfm with 2000 cfm of fresh air. During high radiation isola-tion, the calculated infiltration rate to the control room is 170 cfm. In addition, 106 cfm of air from the mechanical equipment room is calculated to leak into the suction side of the control room ventilation system. This duct inleakage comes from the mechanical equipment room, which is calculated to exchange air with the out-side at the rate of 2640 cfm. During chlorine detection, the infiltration rate to the control room is calculated to be 1250 cfm. The duct in-leakage during chlorine detection remains the same as during high radiation detection. The relatively low infiltration rate during high radia-tion is attributable to the filtered makeup air system that provides 1000 cfm for pressurization. As indicated above, the mechanical equipment room has an inleakage rate of 2640 cfm. A large portion of the infiltration will come through the elevator machine room which has an opening of approximately 1 square foot be-tween both the mechanical equipment room and the outside 4-6 NUS CORPC AATICN

air. Infiltration through these openings will be as-sisted by the " pumping action" resulting from elevator travel. f. Radiation shielding of the control room has been ana-lyzed in the FSAR and in Carolina Power & Light (CP&L) Company's December 1979 submittal in response to NUREG-0578 Item 2.1.6.b. Additional analyses described in Section 5.0 of this report confirmed the adequacy of previous calculations. 4.3 Results Differences between the design of Brunswick's control room venti-lation system and current NRC criteria set forth in Standard Review Plan 6.4 are detailed in Appendix A. In addition, the fol-lowing areas were identified as concerns: a. One door of the mechanical equipment room was found ajar and one was found off its hinges. b. Because the cable access ways potentially communicate with the outside, these areas may not be suitable for storage of emergency food supplies or breathing gear. c. Two unsealed penetrations were found in the control build-ing floor. One was located in the Unit 2 cable access way and consisted of an open, 2-inch diameter pipe. The i other was located in the washroom and consisted of an annular gap between a 4-inch diameter cutout and a 2-inch diameter pipe passing through the cutout. This condition should be checked against fire protection requirements, i d. Several Engineering Work Requests pertaining to the con-trol room ventilation system were identified as being unresolved. 4-7 i NUS CC A AC AATICN

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f 5.0 RADIOLOGICAL ANALYSIS This section summarizes the methods and results of the analysis of control room habitability during postulated radiological accidents at the Brunswick plant. j 5.1 Methods The methods used to calculate the beta and gamma whole body doses and the thyroid dose to the control room operators are standard calculational techniques for modeling the generation, release, transport, buildup, and removal of radionuclides. The equations used to model these phenomena are well known, and the specific equations incorporated into the computer program used in this study to calculate the control room,perator doses are presented in Appendix E of this report. The methods used to compute the whole body dose contributed by sources of direct radiation out-side the control room are based on the work of Jaeger, Chapter 6 i (Ref. 1). The shine dose from liquid source terms was presented in CP&L's response to NUREG-0578 Item 2.1.6.b. 5.2 Assumptions The assumptions used in this analysis of control room radiation l exposures are described below and in Table 5-1: l Radionuclides released from the reactor core are uniformly e distributed throughout the primary containment. Radionu-clides released to the secondary containment are assumed to be uniformly distributed throughout the secondary containment. kk l e The primary containment leaks at a con'stant rate of 0.5 percent per day for the duration of the accident. 1 s 5-1 NUS CC APCAAT!CN l L

The primary containment is assumed to consist of a single e volume with no washout of radionuclides by containment spray. e The secondary containment exhaust rate is assumed to be one secondary containment volume per day. e There is no direct leakage from the primary containment to the environment. All exhaust from the secondary con-I tainment is filtered by the standby gas treatment system. The dose calculation does not include consideration of MSIV leakage, e The accident duration is assumed to be 30 days. e Radionuclides in the control room are assumed to be uni-formly distributed throughout that volume. e The breathing rate of the control room operators is as-sumed to be 3.47 x 10-4 cubic meters per second for the duration of the accident. e The control room X/Q values are adjusted for the occu-pancy factors given in NRC Standard Review Plan 6.4. 5.3 Results The radiation dose to individualc within the control room during a postulated design basis accident at the Brunswick station is computed using the assumptions above and those presented in Table 5-1 and Appendix E. The meteorological data and HVAC design parameters are based on the information presented in Sections l 3.0 and 4.0, respectively. ? As described in the Brunswick FSAR, the maximum calculated dose to individuals within the control room occurs during a postulated 5-2 1 NUS CCAPC AATICN

i l l loss of coolant accident (LOCA). This is because the magnitude and duration of the radionuclide release during a LOCA is much greater.than that for any other accident. This is discussed further in References 2 and 3. The dose to control room personnel from radioactivity buildup l within the control room is calculated using the HVAC system mode'. and the data shown in Figure 5-1. This figure shows the possible inleakage paths into the ductwork and into the control room it-self. The 30-day integrated dose due to airborne radioactivity within the control room is summarized in Table 5-2. The dose due to various sources of radioactivity outside the control room I is also listed in Table 5-2. These results are based on data given in the Brunswick FSAR (Ref. 2, Ref. 3) and the Brunswick shield design review (Ref. 4) and on the work of Egap (Ref. 5). i The dose due to reactor building shine was calculated using the QAD computer code (described in Appendix E). The features of the reactor and control building essential to the control room shielding analysis were input in the QAD code. The sources used in the CAD code were based on the method described in Appendix E. These results are based on a reactor building concrete wall thickness of 2.0 feet and control building wall and roof con-crete thicknesses of 2.0 feet each. As shown in Table 5-2, the calculated control room doses are well within the current NRC criteria of 5 rem whole body and l 30 rem thyroid given in Standard Review Plan 6.4 (Ref. 6). 5.4 References j 1. R. G. Jaeger et al. 1968. Engineering Compendium on Radi-ation Shielding. Volume 1, Springer-Verlag New York, Inc., l 1968. l l 5-3 NUS CC APCAATICN t

i ) 1 2. Carolina Power & Light Company. 1972. BSEP-1 & 2 FSAR. Amendment 13, p. M14.1-1. f l 3. Carolina Power & Light Company. 1972. BSEP-1 & 2 FSAR. Amendment 15, p. M14.4-1. ~ l i 4. Brunswick Shield Design Review. Submitted December 31, 1979 l to U.S. Nuclear Regulatory Commission in response to NUREG-l 0578 Item 2.1.6.b. 1 l 5. M. A. Egap. 1980. Dose Rates and Integrated Dose at the Main Control Room from Various Sources Resulting from a TID-l 14844 Source Term Accident. 6. U.S. Nuclear Regulatory Commission. NUREG-75/001, Section i 6.4. l l l [ 5-4 NUS CC AAC AATICN

l l TABLE 5-1 ASSUMPTIONS IN RADIOLOGICAL ANALYSIS OF ME BRUNSWICK CONTROL ROCM i ~ Power level = 2,550 MWt Operating time = 1,000 days Fraction of core radionuclide inventory released to drywell l l Noble gases = 100 percent Halogens = 25 percent i Drywell free volume = 164,000 ft3 Maximum / minimum wetwell free volume = 134,600/124,000 cfm Reactor building free volume = 2,000,000 ft3 Standby gas treatment system flow rate = 3,000 cfm Standby gas treatment system filter efficiencies for iodine Elemental = 95 percent organic = 95 percent Particulate = 99 percent Primary containment leak rate = 0.5 percent / day l Secondary containment air exchange rate = 100 percent / day l Control room volume = 298,650 ft3 Control room ventilation system filter efficiencies for iodine Elemental = 95 percent organic = 90 percent Particulate = 95 percent Stack height = 100 meters Atnospheric diffusion factors for stack release 3 Time X/Q value (sec/m ) 0-1/2 hr 3.3 x 10-4 1/2-8 hr 1.8 x 10-6 8-24 hr 1.1 x 10-6 l-4 days 2.0 x 10-7 4-30 days 2.7 x 10-8 5-5 NUS CCAPCAADON ., _ _.._-.. _ __ _ __ _. ___ _., _~

/ TABLE 5-2 RESUL'IS OF RADIOIOGICAL ANALYSIS OF THE BRUNSWICK CONTROL ROOM Dose (rem) Source of Radiation Whole Body Thyroid Beta Skin Airborne radioactivity released from the SGTSa through the plant stack 0.002 0.41 0.039 Reactor building--shielded portion 0.004 s Reactor building--refueling area <0.109 SGTS charcoal filters <0.001 Control roce charcoal f11ter 0.054 Cic ' outside the control roca <0.160 Core spray line within the reactor building 0.085 Stack structure shine Negligible Total 0.415 0.41 0.039 aStandby Gas Treat:nent System. i 1 i I s-6 NUS COA AQAATION .,__,.. _.. ~.,. _ _. ~.,.. _.

e 100 cfm o 998cfm 37.878 cfm 4 I y 5E o-o" Control Rc m 4cfm 3 i Un:ts 1 and 2 .2 l = w V <0 t o o 40,000 u-998 cfm i! = = 1 r <i e efm 898 dm ii ,3 -c US 14 cfm Total Volume 83 cfm 3 = 298.650 ft o NOTES: y Total inteakage that bypasses charcoal filter 1374cfm 150cfm = 4 + 14 + 20 + 5 + 83 + 150 = 276 cfm Total inleakage that 20es through charcoal filters = 100 cfm i l l l l l l 1 l Figure 5-1. Brunswick Control Room HVAC System Flow Diagram 1 5-7 l

6.0 TOXIC CHEMICAL ANALYSIS 6.1 Introduction This section presents an evaluation of offsite toxic chemicals and determines the effect on control room habitability of postu-l lated toxic chemical releases. The buildup of toxic chemical concentrations at the control room air intake and within the control room volume are evaluated. The results are compared to Regulatory Guide 1.78 requirements (Ref. 1) to identify the acceptability or unacceptability of control room habitability with respect to postulated toxic chemical releases. Table 6-1 summarizes the general input data used in the analysis. Table 6-2 presents the identified offsite chemicals which were the subject of this analysis. The only significant onsite toxic chemical is a 55-ton tank car of liquefied chlorine gas, located approximately 450 feet from the control room air intake. Other onsite toxic chemicals are l limited to quantities that are sufficiently small to be excluded from this analysis. The rupture of the chlorine tank car was shown in the FSAR not to impair control room habitability. In addition, scoping calculations were performed for postulated spills involving shipments of 1200 tons of anhydrous ammonia and chlorine on the Intracoastal Wa,terway near the plant. 6.2 Methods of Analysis The procedures used first apply the toxic chemical screening methods described in Regulatory Guide 1.78. Table C-2 of this j guide determines maximum quantities of toxic chemicals at dis-tances from control room air intake with adjustments for control l room ventilation system design. Toxic chemicals that satisfied i l 6-1 NUS CCPPC AATlCN

the criteria of Regulatory Guide 1.78 Table C-2 were not further analyzed. The remaining chemicals were next analyzed by evaluating the con-centration of each toxic chemical at the control room air intake. The concentration was calculated using the X/Q values shown in 5 Table 3-5 of thic report. Consideration was given to the contin-uous release or a puff release as appropriate for the storage method and chemical being analyzed. Overall assumptions are as follows: The wind direction is always from the postulated spill e toward the plant air intake. Atmospheric stability and wind speed selected are repre-e sentative of the worst 5 percentile dispersion conditions based on onsite data. i e For chemicals that are liquids at normal conditions, the spill spreads out over an area such that the average depth is 1 centimeter, unless there is a berm around the tank. In this case the spill fills the entire berm. e The temperature of the spilled chemical is assumed to be 100*F. e Toxic chemical repors and toxic gases are assumed to have the same density as air, e No credit for diffusion is taken for topographical fea-tures along the drift path, i If multiple-sized containers are employed, the largest is e assumed to fail. l l l l 6-2 l NUS CO APC AATION

e The tank is assumed filled to nominal capacity at the time of the spill and the total contents are released. / Puff release includes the isenthalpic flash fraction of e stored material. Evaporation rates of spilled chemicals with vapor pressures less than atmospheric were evaluated using the general methodology for mass transfer between liquid and vapor phases given by Bird, Stewart, and Lightfoot (Ref. 2). This evaporation model is dependent on the spill area, the wind speed, the mass transfer coefficient, and the effect of Sherwood, Reynolds, and Schmidt numbers using the analogy between heat and mass transfer. Concentrations of liquefied compressed gases at the control room air intake were analyzed using procedures in Appendix B of Regu-latory Guide 1.78. The quantity of the puff release (flash frac-tion) is evaluated assuming an isenthalpic expansion. Based on this analysis, chemicals with concentrations at the control room air intake less than the toxic limit were eliminated from further study. Hypothetical large releases were evaluated using a flash frac-tion release, a drifting cloud dispersion model, and a simple dif ferential equation for control room concentration as a func-tion of time. A Gaussian dispersion model is used to calculate the concentration dilution as the vapors drift from the spill site to the air intake. For purposes of this analysis, normal and isolated operational modes of the Brunswick plant ventila-tion system are represented by the simplified schematic shown in Figure 6-1. 6-3 NUS CCAPCAATICN )

The control room concentration as a function of time is repre-r sented by the following differential equation: dX ~ CR bSS*S)XOA-9X5 CR; j = 1 or 6 V dt j where V = volume of space served by control room ventilation system XCR = toxic chemical concentration of control room air, mg/m3 xOA = toxic chemical concentration of control room air in-take, mg/m3 (based on Gaussian dispersion model) 08 = total system infiltration 03 = fresh air input during normal or isolated mode QS = total system outleakage 6.3 Analysis of Hypothetical Barge and Truck Accidents The Intracoastal Waterway (ICW) passes the Brunswick plant at a distance of closest approach of 2.3 miles. In order to deter-mine the importance of toxic chemicals that may be aboard barges on the ICW, two hypothetical accidents have been postulated for this study of control room habitability. The accidents assume worst-case conditions based on the following extremely conserva-tive assumptions for accidents releasing chlorine and ammonia: o Complete release of the largest tank normally carried aboard barges Wind direction is towards the plant e e Wind stability is Pasquill Class G 6-4 NUS CCAPCAATICN

Release occurs at the closest point of waterway approach e i e Average wind speed is 1.5 meters per second State Highways 87/133 pass 1.4 mfles from the plant. Accidents involving hypothetical sni?ments of ammonia and chlorine were also avaluated for this transportation route. ~ The concentration in the control room was evaluated using the control room model and the toxic chemical concentration differ-ential equation described in Section 6.2. For both chlorine and l ammonia, the calculated concentrations resulting from these very conservative analyses of hypothetical accidents are greater than the toxic limits. Because actual shipments of the magnitudes assumed in these calculations have not been verified, further in-vestigation is deemed necessary before CP&L determines if these postulated accidents are real concerns. 6.4 Summary of Results Table 6-2 summarizes the numerical results of this toxic chemi-cal habitability analysis for the Brunswick plant and shows com-pliance with the appropriate limits. The Regulatory Guide 1.78 screening procedures eliminated all toxic chemicals stored in the vicinity except sulfuric acid. Sulfuric acid was eliminated because of its low vapor pressure resulting in a concentration at the air intake much less than the toxic limit. 6.5 References 1. U.S. Nuclear Regulatory Commission. Regulatory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemi-cal Release." 6-5 NUS CCAACAATICN

2. R. B. Bird, W. E. Stewart, and E. N. Lightfoot. 1942. Transport Phenomena. New York: John Wiley and Sons. l I i 6-6 NUS CC A AC AATICN

l TABLE 6-1 SU1 WARY CF INPUT DATA Parameter Data Units Meteorological: Pasquill stability G None j Average wind speed 1.0 m/sec Atmospheric dispersion, X/Q See Table 3-3 sec/m3 HVAC System l Normal operation: 3 Fresh air makeup 2,000 ft / min 3 Inleakage 272 ft / min 3 Outleakage and exhaust 2,272 ft / min Filter removal, toxic chemical None None I Loop flow 40,000 3 ft /mir. Air exchange rate, outside air 0.46 Per hour j Emergency operation (chlorine isolation) : 3 Fresh air flow (damper leakage) 1,100 ft / min 3 Inleakage (duct and adjacent areas) 272 ft / min 3 Outleakage and exhaust 1,372 ft / min Filter removal, toxic chemical None None 3 Loop flow 40,000 ft / min Air exchange rate, outside air 0.28 Per hour volume of control room 298,650 ft3 6 i 6-7 NUS CC APCAATION

TABIk; 6-2 HESUI/IS OF '10XIC CHEMICAI, ANAI,YSIS Concentratism Caantity Allowed in Control kuum t gar e Regulatory Tonic Concentsation at 2 Ninutes Distance Storage Quantity Stored Guade 1.78 Limit at Intake After Numan I I 3 I Incatson (ei) Chemica1 Condition (l to) (lb) (mg/m ) (ag/m ) Detection (mg/m ) Standasd Psoducts 4.0 Sulfuric acid Tank ambient 40,000 2,500 2.0 0.01 N/Cd temperatute arw! pressute i Standard Psoducts 4.0 Chlosine Liquetied gas 2,000 10,000 45 N/C N/C undes psessure (464)b Piizer Chemical 1.7 Chlorine 1iquefied gas 45 2,100 45 N/C N/C f under pressute i Pfizer Clweical 1.7 Sulf ur ic acid (c) (c) (d) 2.0 Sunny Point 4.2 Trichloroethylene 55 gal, drum 660 670,000 515 N/C N/C f Sunny Point 4.2 Hed fuming nitric l.ance missale 1,107 6,2t,0 5 N/C N/C O) acid fuel tank Sammy Point 4.2 Hydrazine I.ance missile 175 d,100 6.5 N/C N/C fuel tank Sunny Point 4.2 Chiosine Wellhead tanks 150 10,000 45 h/C N/C aNot sequised to 1;e calculated. !*It.enthalpic flash traction. (h C !ntornation on Pfizer not available due to Pfizer psoprietary rest riction'.. dConservatively assuming a stor age tenteratur e of 145"F, a release qseates than 2,000,000 lb woulet te necessary to cause a concentsation equal to the toxic limit at the als intake, if analyzed according to seg al.atory Guiale 1.78. (< 9 cc i Eso + IF=='

s 05 I k Control Room and interconnecting Space i Volume = 298650 ft3 T y = c3 / 1 Filter 4N I Oj During Normal Operation 06 During isolated Operation "I "9 Ventilation Flow, [ Qi Normal isolated l (chlorine) i 3 3 Flow ft / min Flow ft / min 01 2,000 2,000 02 40,000 40,000 03 40.000 40,000 i l 04 37,728 37,728 05 2.272 1,372 06 0 1,100 08 272 272 l l Figure 6-1. Simplified Brunswick Control Room Ventilation System ( 6-9

APPENDIX A COMPARISON OF THE BRUNSWICK CONTROL ROOM TO THE CRITERIA OF THE STANDARD REVIEW PLANS 6. 4, 9.4.1, and 6.5.1 A.1 COMPARISON WITH STANDARD REVIEW PLAN 6.4 A.l.1 Control Room Emergency Zone The zone serviced by the control room ventilation system contains all critical areas requiring access such as the control room, kitchen, sanitary facility, computer rooms, and electronics rooms. The electronic equipment rooms for Units 1 and 2 are open to the control room and therefore increase the surface area of the con-trol room ventilation zone and the potential for inleakage from adjacent potentially contaminated areas. The cable and battery rooms are not directly accessible from the control room and have their own ventilation systems. A.l.2 Control Room Personnel Capacity The Brunswick control room is common to Units 1 and 2; therefore, two operating crews will normally occupy the control room. Con-trol room manning requirements are as given in technical specifi-cations. The emergency food stockpile has not been inventoried to determine how many persons it will support for 5 days. At present, the northwest and southwest corners of the control room floor are open and available for occupancy in an emergency. A.l.3 Ventilation System Layout and Functional Design The ventilation system design provides two distinct modes of emer-gency operation. In the first, the system automatically isolates the control zone and recirculates a small amount of air through the charcoal filter. In this mode, a small amount of outside air A-1 NUS CC APCAATION

. _ _ =.. 1 is introduced through the charcoal filter to pressurize the con-trol room zone. This mode is used in radiological releases. The second emergency mode of operation is used in chlorine releases. In this mode, the system automatically isolates the control zone and does not start the charcoal filters or introduce pressuriza-tion air. This minimizes the intake of chlorine-contaminated outside air. a. The emergency filter isolation valves are heavy-duty, low-leakage, single-blade dampers. b. The fresh air makeup (2L-D-CB), emergency recirculation (2J-D-CB), and bathroom exhaust (2H-D-CB) dampers are not redundant. Likewise, one solenoid valve (SV-916) controls both the emergency recirculation and the fresh air makeup dampers. Failure of any one of these active components could impair emergency mode operation of the control room ventilation system. c. Pressurization of the control room during high radia-tion isolation uses 1000 cfm of filtered makeup, which is equivalent to an air change rate per hour of 0.22. Stand:cd Review Plan 6.4 states that a control room with i a make-up rete of less than 0.25 air changes per hour requiree geriodic testing to verify that 1/8-inch water j positive pressure is maintained. A.l.4 Toxic Gas Protection l As indicated in Section 4.0 of this report and in the FSAR, the Brunswick plant design includes chlorine detectors and provisions for an automatic isolation of the control room on detection of chlorine. Section 6.0 of this report and Section M14.5 of the FSAR present analyses of toxic chemical protection. A-2 1 NUS CC APCAATION

A.l.5 Emergency Standby Filters See 3ection A.3 below. A.l.6 Relative Location of Source and Control Room The control room air intake is approximately 25 meters above grade, on the roof of the control building. The plant stack is approxi-mately 180 meters away; the Unit 1 and the Unit 2 reactor buildings are approximately 40 meters away. The chlorine tank car is approx-imately 140 meters away. The potential for contamination of the control room air from re-leases to adjacent areas is discussed in Sections 4.0 and 5.0 of this report. A.l.7 Radiation Shielding Control room shielding is discussed in the Brunswick FSAR and in CP&L's submittal to the NRC in December 1979 in response to NUREG-0 578 Item 2.1. 6.b. A.l.8 Radioactive and Toxic Gas Hazards l These are discussed in Sections 5.0 and 6.0, respectively, of l this report. I A.2 COMPARISON WITH STANDARD REVIEW PLAN 9.4.1. I A.2.1 Single Failure Analysis The main supply fans have a common spare and the emergency filters are redundant, but there are several active components that are l l A-3 r NUS CCAPCAATICN

not redundant. Should one of these fail, the ventilation system could not operate as designed. These components are listed below: o Fresh Air Make-up Damper 2L-D-CB. Failure to close on a control room isolation signal or failing open could per-mit 2000 cfm of unfiltered outside air to enter the control room. e Emergency Recirculation Damper 2J-D-CB. Failure to open on a high radiation control room isolation signal or smoke alarm would not permit the recirculation of 1000 cfm of control room air, which would hamper cleanup of the control room air, e Bathroom Exhaust Damper '9-D-CB. Failure to close would not permit the recirculation of 1000 cfm of control room air, which would hamper cleanup of the control room air if it were contaminated. e Solenoid valve SV-916. Failure of this valve would hffect both the fresh air make-up damper and the emergency recir-J culation damper, causing them to fail "as is." The result would be the same as failure of the dampers themselves, e Outside Air Intake. Though not an active component, this is a critical component of the design. Should the lone outside air intake become obstructed, all intake of out-side air could be impaired. l A.2.2 Separation Analysis The emergency E!1ters are enclosed in a concrete block housing, separated from each other by a block wall. The filter fane, the supply fans, and the instrument air ccmpressors are not separated from each other by physical barriers. j A-4 NUS COAACAATICN

A.2.3 Analysis of Failure of Nonseismic Equipment This matter was recommended for further investigation. A.2.4 Adequacy To Maintain Suitable Environment The ventilation system is designed to maintain the control room at 75'F, 50 percent relative humidity with only two units in oper-ation. A 100 percent capacity spare is provided to assure con-tinued operation in the event of failure of the primary units. To maintain air quality within the control room, 2000-cfm of fil-tered fresh air is provided. A.2.5 Ability To Detect, Filter, and Discharge Airborne Contaminants in the Control Room Upon detection of radiation, the emergency filter system is auto-matically aligned to filter 1000 cfm to remove the airborne con-taminants in the control room. Filter operation is inhibited upon detection of chlorine in the control room air intake. Smoke de-tectors are located in the control room general area rather than in the intake plenum. A.2.6 Provisions To Detect and Isolate Portions of systems in the Event of Fires, Failures, and Malfunctions The independent ventilation of each compartment within the con-trol building serves to minimize the potential for the spreading of smoke. Fire dampers are provided for all penetrations through firewalls. A.2.7 Seismic Design Requirements An investigation of the original seismic design of the control room ventilation system is being conducted. A-5 NUS CCAACAATICN

t t l l A.3 COMPARISON WITH STANDARD REVIEW PLAN 6.5.1 A.3.1 Operation After a Desigr. Basis Accident The emergency standby filters and the supply system are designed to operate after an accident. The control room ventilation sys-tem enters the emergency mode when a high radiation level in the intake duct is detected. i A.3.2 Design Features of the Emergency Filter i a. Each emergency filter train contains a HEPA and a char-coal filter bank. The filter train does not contain a HEPA filter downstream of the charcoal filter to catch fine particles of charcoal. The filter trains do not require a moisture separator. The mixing of 50 percent outdoor air and recirculation air assures that the rela-tive humidity will be maintained below the critical conditions. b. The redundant emergency filter trains are separated by a barrier so the damage to one system will not cause damage to the other system. The separation of the redundant emergency filter fans does not assure this protection. l c. The emergency system flow rate is less than 30,000 cfm. d. The emergency filter system is not instrumented to sig-nal, alarm, and record pressure drop and flow rate in the control rocm. e. The emergency filter system will automatically be acti-vated by a high radiation level detector located in the s outside air intake. A-6 f NUS COAPC AATICN

( i A.3.3 Equipment Environment l The system will not encounter any severe environmental conditions. The equipment will be exposed to relatively low radiation levels, in addition to normal environmental conditions. A.3.4 Component Design and Qualification Testing The emergency filter system equipment meets the design and testing qualifications of ANSI-N-509-(1976). l A.3.5 In-Place Testing i DOP injection and detection ports are installed for the inlet and outlet of the HEPA filter bank. Freon 112 injection and detection j probes are provided for testing the efficiency of the charcoal l filters. 1 A-7 NUS CC AACAATICN t

APPENDIX B ADDITIONAL INFORMATION REQUIRED BY THE NRC i 1. Control Room Mode of Operation:

Response

Radiological accident: pressurization and filter recirculation Chlorine release: isolation 2. Control Room Characteristics: 1 i a. control room air volume: J

Response

298,650 cubic feet i b, control room emergency zone:

Response

The emergency zone includes the control room, electronics rooms, kitchen, washroom, computer i

rooms, i

c. control room ventilation system schematic with normal and emergency air flow rates:

Response

See Figures 4-1 and 4-2 in this report. d. infiltration leakage rate:

Response

The calculated infiltration leakage rate in the radiation isolation mode is'276 cfm. l e. HEPA filter and charcoal adsorber efficiencies:

Response

HEPA filter efficiency: 99 percent for partic-l l ulate iodine. I l B-1 l NUS CCAAC AATICN

4 l l r charcoal adsorber efficiency: 95 percent for i elemental iodine, 90 percent for organic iodine. f. closest distance between containment and air intake:

Response

The principal radiological release point is the plant stack, located approximately 180 meters from the control room air intake. g. layout of control room, air intakes, containment building, and chlorine or other chemical storage facility with dimensions:

Response

See Figure 4-3 in this report. h. control room shielding including radiation streaming from penetrations, doors, ducts, stairways, etc.:

Response

For analysis of the Brunswick plant shielding, refer to Section 12.4 of the Brunswick FSAR and the December 31, 1979, submittal by CP&L in response to NUREG-0578 Item 2.1.6.b. i. automatic isolation capability--damper closing time, damper leakage, and area:

Response

The closing time of the outside air isolation damper (2L-D-CB) is 7 seconds, f The damper is assumed to leak at the rate of 1 percent of flow in the open position, per ASHRAE for dampers with seals. Assumed damper leakage is 20 cfm. The area of butterfly damper (2L-D-CB) is 1.4 square feet. B-2 NUS CC AAC AATICN

3 I i j. chlorine detectors or toxic gas (local or remote): i

Response

The response to comment 14.5 in the Brunswick FSAR states that the plant is equipped with l six chlorine detectors: two on the service water intake structure, two in the chlorina-i tion building, and two on the control room air intake. l l k. self-contained breathing apparatus availability (number): l

Response

By procedure, seven Scott Air Paks (four 30 min, three 15 min) are maintained in the con-trol room emergency kit. 1. bottled air supply (hours supply) : l i i

Response

The self-contained breathing apparatuses are i refilled at the compressed air station from a bank of twelve 2000-cubic-foot capacity bottles. I m. emergency food and patable water supply (how many days and how many people):

Response

A stock of emergency food is maintained in a locked cabinet in the Unit I cable access way. See Section A.l.2, Appendix A. n. control room personnel capacity (normal and emergency) :

Response

The minimum shift complement in the control room is as defined by technical specifications. In an emergency, CP&L would limit the number of people in the control room to the minimum required. B-3 NUS CCAACPATICN .. _.. _. _ _, ~ _... _ _ _. _ -, -,.. _ _. _. _ _ ~. ~..

\\ / \\ 3 o. potassium iodide drug supply:

Response

CP&L intends to purchase pharmaceutical grade potassium iodide to be stored at the site for administration by a physician in a radiologi-cal accident. 3. Onsite Storage of Chlorine and Other Hazardous Chemicals: a. total amount and size of container:

Response

See CP&L response to comment 14.5 in the Bruns-wick FSAR for identification and analysis of chlorine and other hazardous chemicals stored at the site. This analysis indicates that the 55-ton chlorine tank car at the service water intake structure is the only hazatdous material stored at the site in a significant quantity. b. closest distance from control room air intake:

Response

See the response to comment 14.5 in the Bruns-wick FSAR. The tank car is located approxi-mately 450 feet from the control room air intake and the control room air intake is approximately 25 meters above the grade on which the tank car is stored. 4. Offsite Manufacturing, Storage, or Transportation Facilities of Hazardous Chemicals: a. identify facilities within a 5-mile radius b. distance from control room B-4 ovJS CCAPCAATICN

c. quantity of hazardous chemicals in one container d. frequency of hazardous chemical transportation traffic (truck, rail, and barge):

Response

See Section 2.0 of this report 5. Technical Specifications: a. chlorine detection system:

Response

See Brunswick Units 1 and 2, technical specifi-cation 3.3.5.5 for the LCO and surveillance requirements on the chlorine detection system. b. control room emergency filtration system, includng the capability to maintain the control room pressurization at 1/8-inch water gauge, verification of isolation by test signals, damper closure time, and filter testing requirements.

Response

Refer to Brunswick Units 1 and 2, 'echnical specification 3.4.7.2 for the lim..ing con-ditions for operation and the surveillance requirements on the control room emergency filtration system. Technical specification 4.7.2.d.4 requires veri-fication at least once per 18 months'that the system maintains the control room at a positive pressure relative to the outside atmosphere during system st/ cation. Specifice~ dM 7.2.d.2 and 4.7.2.d.3 address verificatsan of isolation by test signals. B-5 NUS CCAAQAATICN

Specifications 4.7.2.b, 4.7.2.c, 4.7.2.d.1, 4.7.2.e, and 4.7.2.f address filter testing requirements. I l B-6 l NUS CC APCAATION

APPENDIX C JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED AND WIND DIRECTION BY ATMOSPHERIC STABILITY CLASS January 1, 1976 - December 31, 1979 l l I C-1 NUS COAPCAATION

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0.40 1.24 2.29 1.43 0.10 5.S% 15.10 ne t Nt 0.0 0.04 0.4v 1.27

s. 19

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f. IF 1%.62 1

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m. i e.

e. .o. e, l l w t ie t i w e-e im mi e o m .= c Cl i .n !N e N .N o e h ed e ese se me

== e== == = m. es .= i l @c I I l I Z. I' ( l I 3 3 l i e i I. I l 1 i 4 4 It m M wn er* aN es= N e .c 4 a. lC. C. =a. IC.- O.

==. C. C. 4G. C. C. ec. C. C. iC. l .4 i 'c i p 4 4 s C C !C C C C C C. 0 l b= sc C C lC C C sc C* i I I 5 I C. I t i e l l a 1 Z c. 4 C C. O. C. C. C. sc. C. C. C. C. C. .IC., C. C. sC. j I 1 p C C C C C O C O C C C C O O C C f e I g e I W O* lC .= I .i l I W cP 4 j e w== W e i w sa N M 4 (* i e.= C + N. l i se s e

== i. l ' Z N.'. I N l4 Eb =

== O so C C

• =.s C.

IC. C. o. C. C. O. C. O. C. C. C. IC. C. C. C C. i12r w j b. i C o o C o b::, o L* i a t-e o C o C C o I., C l: ci i k N 2 im O >= 4 8

1. v. v e.

e A .e cL i g 'T ' s== w J e lC l i - at 1.

== ly C I le i I l ) 1 0 4.w-s. l l

• m t C==

1C j (2 si 10 i.= P= 4 c

• • C C

N -..= f4 N

==

• g

' e:l"

.,

iC. C. C. f. C. C. ,C. C. C. R. C. C. O. C. u.

r. -

i==< te ..e g er i i i 12 - ;. s ;: !s I N .J m le .cL s rc C o O O C C C O IC C C iu C C iL L 4C 11.= .h.J== M -. C i* >= t l '? !O l2 s th no e. i. Ie iA 6E % pri sw

• • C IT i4 N le i

e i.- L a et i i a== [ I lu lv T H na la 4.J i

2

,2 < is ?.>- l I C N m ser e e D'3 a. iC Je O 6'e L C = P. a cL Ir C to-w w iN o. C. C. .c. C. C. C. C. C. C. E.. C. C. C. C. + ! C' C 'e = w e.

== l i. l w ick i. .=N a 'e e. lC., C C C C C C C C C C4 iC C 6 10 !. 7 = i l l V 4 l I i.J e v. lC n,= ~ o. l l l i c.C er e-tw v 3 m i Iv 1 lw-i e I ( =x I l' I' l . Z 4, lF

O la

L

.= i ls

== ic 1: mj . z ui .J r i- -e .:l N ea -o o e

== IC

==, t lC. C. C. C. C. C. C. C. C. IC. C. G. C. C. 4,. =. 6 : 6 e. g-g C C iC C C .3 C O C C C C C C IG C, w N lO l l j != 2 .= i i

7 0 e

I j i I' i i ai t m l 6 l 1 t a. I i l O C f C

== lt C .=== Ce C. C. C. C. TS. C. C. C. C. C. la C. C. K. C. ; e. IC. ei 1 i i 6. 6 l g 2 01 O lo C C iC C O iC C O IC-f C p C' m IC + + I i 1 I I i m c. l = 1 J l ! b I l i o j i { e. i l I . jO t i C. C. iC. C. C. }O. C. ; 0 C. O. C. C. C. C. C. C IC 1 'O / :. f t t t. i. se f a P C C r C C le C C IC r C 1* r C ,3 C l I ! s f' e i l v a ed I l l ve i I aA l l l l l : C e j i z i r y .=, 4 1w j wf a. l o n z 2 iz <: - r .e-M. M e I 2 T '? =t i=.' 3 T E. ' 'l l 71Z J 2 m Z e e A v5 2 T 1 2 i Lt O' i . b=

2 2

.T ?F wl3 y ' = 1 ? l I { 1 l C 1 .i l I I i l l C-10 I 1 i i i i i i -.-,........s.- -... ~.- .e,_ ..e.4 -s - : e.:.. J s -f w w d w w e J s e 4 d 4 d e 4 e t 9 9, p

D** TN .n 'S W e m dJ

3

,=. =...... 1:.51: : c r!w:;:;.; d i:;*ita.: It: Ic c :: r r ;; ;; ;; g ? ; = 5 3 ;; ;.I: i ;;.yj; pg _;; ; g g ;fjo,g

.ge.,

I e \\ ? I l, 1 f o. N o. 4 i l c m a e p. e m e P. CP ci m e. o. m. e. e.l e. e. e.t 4 o. e. 4 =. z.e P P. c.6 t' o w e. N N w t .s a e c. a =.=. e.=i m. e.= - =. =., = =. =. ee l f> I r 42 I i t. I I i I l 1 ,i i

== 4 P.

== p P. es } C.P C t l C P* N 4 a. a

=

o. o. e

==. C.6 N. N. N. C. .a i o C o C C o C C o o C o o C C o N f i c i i e i l l w f I I O. e l e t l N 'l F i O. C. O. C. C. O C. C., C. C. C. C. C. C. C. C. C. l l 4 = t l l C C. O C C C O C O c C c C C C C C or 8 f C O >= u Cr I 4 4-l W

e. s x

O f t* e-6 a, != s N. 4 e s =* . 2 N. C C N C .= E 10 er' e a w

.e o..,

O. C. C.. C. C. C.. C. C. C.' C. F. C. O. C. = =., h3 C. c m. g. - x x . e o o . o C C o o o C o C o o C o C Ci 1 y w s u. N l I = e ? -e

== 4 6a j e. '.4 0 s s l m i Y T a a. 4 =. O C - t ,a 2 cw I'.= l 'c

w t

9 c ri e

• =='

N CP c

== C -. O C 2 lC.

== c. C. C. C. C. O. O. C.l C. C. O e i C. C. C. C. o. I.t. t =

== e. i:

=

. C C O O C C O C C C C C ' O C C. '2-C C t sw fx ' A.s.p N. J lu=. 1.t a = g= u - 0 'C .w ee N z.a

• A==

=T la .e. '.d N

• • C

.m.. lT .s o i u-1 ?4 2 m 'Q

• C

== >s

e w

e .' e 4 .= e es 4 e d 4 e r== P. Cl

• e

=. !C C. C. C. C. ! O. C'.

== e lC"".

==.! w C. O. t. vs.= II . O

• aa e. C.

C..: O. 4 i-s O O C C# C C C C C C L. o -* d aN C c) C 2 1. e e 'v j . =. O l i I a e u a. lv l A 2 .1 i .t er P I w 1 - u 13 i v w y l i.2 i i = .a ir w c e ' -2

== = = * =*

== - . 0 4 =* . C = = =. C ? 59 8 ' C. C. C. e I. 3 lC. C. l C G. G. C.. C. Q Q .C o. a: a. i J. i. C Cl 4 'C Oi o C Q O C C O 'C C C C C O j 1 i

• 1 f

Z* A l f g i { r U" ? ( E et + 1 l i f I C.

c. m O.

O. C.. { l i ,C. C. ; o. o. C., C. i. C. O. C.l. C. C e. C t a 'C 06 O C O C C Of Q C Cl O C Cl C O O' 1 6 N4 i I a i f } f g I I i s n i I C t-, I i C l s 1 6 a z l 4 I s 6 : C O. s c. c.

c. e o.

,o cf O. C. C. *l o.

c. '

C. c. O. ! O e o a g, r j. 6 4 t. s lC l t ' C 'C C6 C O ": C Gt s .C G1 C C -3 C 'O Cl O I ss 4 } + v l l VC e i -i l i I I th I 5 e i i r z! . C i l 1 i I ~ s i t l i s. - E 15 e il 2 =, o f i g 4 1za z; a z e. .s T 2 ..C.= l Ae ye a

• be A

Al E ,.T Et Z e r g'

c : :

.s es e ti a I Zl Z e ar e

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3.. 7 e

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%4 rrt /.I .o

• Me o

.t JL I

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-. 3 f g...

.q =..)- .. g ,7 7.,7., 3 1 l_. l l i 1 t i I t l l l l r i l 8 l I I l I l e O t a= N ee m e-im e N se 4 e ew e c ;4 ol I M.

4. l l

im. c. 4 4

1. O.

C. 4f.' @ l. am

== P= e4 ap j us i i. w

• a i== e e

<c .= 'C i 5 I.C. .C. .N. C. .N im. c} .N. e.s l i ie w ~. l l l' s I + i MO I? I i 6 l i j -2 i g I i s I l l i .= C N Lt.*. 7 O te m c N e er e -. e NI =.J N. en. ed. N. J m. et.,, N. N. 4 m. g e m m aw .= . i. te o O C O tC C O. C C C O C c l i. ,C = ? = l > l 4 l l 3 i i i l l o. f to i 2' N e i C o. C C. o. IC C. C. 6 C. C. C. C o. ,iC. C. C C, e J. e. i e .== C C C IC C O hC C O

• C' C

O e C C C O i I E l w l 'C 3 =. Iw 7 w l

== e u. a= us l he. la s a 8 W* =* I,9 l ~ ,i a it s i rm =. 6 e== e l.= C es== c N .4 e m N l e. C. .C. O. C. IC. C. O. C. C. O. sc. N. O. IC C. O. lC. 4 i= lF r .y la l 80 C a

== e C C C IC C O C C C IC C C IC C C .c C I 0-4 6 l l v N i i g '= Z

= C w

• JC w

e. l 4

• lg i

6 IT e= ui a an l f f IC j (L 4

== l iv i i r iv l l ( > 0 IVw

• =,

.c i i i I +> m dL N d h6

== n:: C ! .O. .e -1 l '? M . O. im tra le c .= m.=- 4 6 .C. =. C. m e. C. O. N. c. C. w ic i W =

== == se '-4 e. .a

• =

l. l. . i. l. ' 7== iar w IO

== sl a o C o p C e w. o C C. e o ,C o C v x.e =a s ieu a s ,w . r Ca lC 17. a c = i jZ Ib

o=

e in b I 4 + = = .e= r u e e l .+ .a= C I'I W== 3

• • N I

t A er . ru i.r r== s iu. M l v iw l2 i2 e d' i== l l l I IC i N -4 O tC + v'a= f 4 m O .C CI p: C N C 7 le t.f. F

> w ha.

l>

== N. N. e.s t. ta .'C S .r4 N. e. r. N. c.i c, a ns4 p= =e r. e =.= i n. = i

a.

e N. o e e c o o C e o c c o e c C c e c. lr aN ) I I 'e= s a== = i6 l i ar 6 l e I i i IO l. C .A 1 .v e. 4 i

t. v

.c : ! v f7 at = l i 1 se i '. =7 4 iv j I t >- !? s s a 5 e l i l I l 'V a.e er <r.

== tz c N .c 4 e e e m W== .=. m as er l' a we .e. C. C.

1. G.

C. Q C. C. C. 4 i % I th. C. C. o. iC. G. C. C l 3 t j. 1 s, I e C., C C C C C IC C O 60 O O "C O C ,C C l i . = - 2 m-i .O 1 A i l l f I l - ~ c. l 1 m i l i .I j i l' .L 4 i C e su i i .C C c. N. 1 I g I C C O. C. 7 C. C. aC C. C. Ir-6e k2 O. C. I l c. O. 'I C. C C IC C C C O C C C C er? e., !C t. 6 i. i. 'C 04 C C i m 1 { l i 1 .e 9 g o I i. . l J I 4 1 i o f. 1 6 l i I I

• y l

(= C C IC C " c4 4 0 h* ? r. C O. C. ,C. C. C. lC r. C. G. c. c.

l C

O. C. h C i l r i. A =, ee 6 i. lC Cl I .J 'C C C C '.3 C iC C C K O O k' C 6 j l l l t. i i v e i2 i f I OC l e r j i i l 1 0 I, se== l i t r' i } s u u et 2 j 3 17 s;

r..

.31 i l 2.z v r* w z 2 r i r r-i 2, ,-, x z r

== .vi ir. a w

w.:

z, z -l ze l i j .z a i 1 i i i - t I I C i I i i I 1 i C-12 i I i i i . r g.; t 7, .e

.;.e e. +.

4 s. J .gl M J J J ) J %=*

• Y W

%I

== W W W q 4. .:.= m

'.t 'W V s. w 1 L' n c c o ....-.... = = = u u n. _ = = - u = n n. _ f I 4i O + N+ e. e r~ m 4 e, N O e e. i t O m N. e.l 4 e. e. c.e e. C.e N. e.l 1 W @l { 6 e ,as e c e M e O .N. mt

• Q Q

C. l e& S @+ .C. .e .e

== I 0 wt 40 i i. .t 1 = j e 2 4 4 e .= ei e 4 O e 4 C' ps A e N. 4\\ c. P.= 4 4 4 c. O. C. o. 4 Fw

== a e. ei N Ni ew N .a.6 q ce 4 ee .e s= a' C P I O e i e 1 N e I F C c d' M ,C 4 O C. C. C e. C. C. O. O. C. O. O. C. C. .c.

m. i' O.

j. 4 e C C C O O C O O C O O C O C C C O C er t e i ' N. 'C p. w ju @ w

w r-6 1%

E O e.* O 4 me a O% I 7e b es 4 4 ae >= J.= e 1 N P= = N N O d l .e.* I C .C C. O C C. C. C. C. O.. O. !C. e C N P* e e e e la e e e e

t e

a e C C O C C O G C C O C C C C 'C A i z - N ! 3 eJ Z ' hm O 4 9 e. e uC e A = - .x 1 .a. !e i r x-l l 2 e ! t u I s ,C J s.

n w

c V C 4 4 e 4 N. e .fm 4 N c N em N 3 t.2 le. N = O. G.

m. l#.

C. e. N. f. M =

== c. c. e.- 4 j

• e.

wt. a (C i is - u. .c t % ..e s 1 sL e C C O O O O O C O .= m O O C C Jm 4== U *e

O t

6-I O 'C I C.i. we e. E t N .h 4 se

• = T =

v5 ? w -c t jn N ?

• =

,az I .,e l4 4.J t g

v

=* r 7w e s l4 'O 0 w 40 = m-w e a ,e et + c== m C T P=. O 4 C m .= -t l 'I. C 1

1. =

I 4 me e. 4 4 O. .s r=. e. C. a a- + e

• w e.

4 m. a. e q a C O o C N o o s ,2 .a.. 3 e eN e J. 6 ' o y e I f e. s i O 'O .J .v

u..w.

} v is c. i a i v

• 7 e

l l 'E w T O g' n'

• 1 me

'J a j r Ne # + .c 2 e sa in d 2 e e Ni rs J A w l e. C.i e. 4 4. 9 e. 9 4 A. N. 4

4. 4

' Fm c i '*2 ' O C C O O C O O C O Cl O C ~l } f N C Ct [ t =. Z; e t j i C* l = l l i i m l l i j i 4 e J. e e e ' 4 4 y: i > c a e.* c 'e 'O t e. 1. C.. 0 C. C. O. O. C. J O. t'.. O. C. f O. ~ .4 m C C} O C Ci O C C O Cl C 0 Cl C O 3: I Jh l Of I I j e e (

==. 1 I a ee f C e I e ( <r l l ,C le I O. l ' O i O O O. l 'O e 0 t j O. ' C 'C. =. O. C. C. 3 C. t !C. C. e O. C. Ol c C 4 .6 i a. a-t e e Ie n :- C e =r r a C er O C ci o 'e C l I i a: i < ) l v i i i 3 u& 1 t I l t } i i -k A i l' j I t z 5 = i T_, i m' w as e si v -i i

-. n

,i e, a a e-

2.. 1 z -.

1 7.. 1 a e. ~n. s. s z 1,

3. z u.

z! z a. si t ..i ,e o t 12 i - z : si 42 2 l 5 C-13 j f 3 t r i t i I I I 1 ..,...............p-..;-

..p.

t. os l t t L v s e, t w s r

e,. ........... a -

• e

- e e a.... A ; g g - g.. g ( ; g g g,; 2,,;,. t :, y g y g,; g g - g.,; ;. 3.g g 3.j.p y. : 3g {f $ $k I D Ii ? U gglh j U l t 4 6 O N N 4 60 N e .N 4 e ans e O > c 4 e i w m C m em e e c N e.== se se N 4 O *= m. I w e e e ee e e se e e se e e to e e se

• a, 4

lp 4 4 >= e e n O e m 4 e ic = l e e g 8 40 Z t l 1 l i ~ m m a e e va e e== C 4 ca e m== > .J N

== f** N Q C 4 e IP=

== f C 4 N per

• =

e e o e 6e o e e le e q e e e o .e. em .== an em IN e m W em se N t-r% N se

== m C e= 6 t F C i e l N I l 2 w N N O = I 4 C O O C O O C C O #C C C C C C eC o. e e o e o e o e e o e e se e e e s= C C C C O o C C O C C O C O O C C eCw m c

== w (P W w i ll Pm a ,a % ar .C to *= 0 .as =a N CN

== 7 f%. O a=e O s%

== W85 d e ma e m e an - e a-C C C O C c O C C o== N O C O O C v.

== Io e e 4e e e ie e g Zr w a e o e e e e e e o e Ca 5 O C C O C O O C C O N: O O O C o IC C i 0 V N

== r

= c e-4 s

j 4 E e l,u C, 4 w- = e e. l

k..e. =.==

.e X wa e C j u lC T v l e ww 1 e e e ie ~ = w e 4 e = m - < i l0 - lia g

==: ,e C i==< so * -a

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== O s C O iC m I lu - U== 0 T =8 l I' = O u a-h' O O e= ten e .z .a -- -r w ie e w C I N 4 E s= JE

== i ? to vT

• • w 4

C I l I

• T iz 4 C

g l,e-w eC 8 l iC su .e w e N 4 e e 4 O p-e

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== N

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• • =
• e -.

v 7 le v im 1 t lO l t T = l 7.s a. P le t t 6 er.c =.=J lr 4 C P-em

== 0 N 62 4 s hr v = 4 l 4 J G A F e 4 e W 4 P'o* 64 A FN Ia. e e ee e

== e e e e o e e e e e e e ge g g 6 O C sc o O C C O

==

==

G C K. e .er. r i-.x 7 l:" : e 8 t e .=q. ?O j sa ' -t 1 m - u m. 4 O < - e s e. 'N N en tr% N N e-o N N ya es er% l e. N. m.e e e e i. e e ae e e .e e e

e m p C

C ac C C ic G O sc C O C C C F va ' I N r, n t d e 1 a" l. e N i O n ' i f zh I .==== c== e

== e

==

==

.= e s :( C C C O O C O C C O C C C. e

e e

e e e e 6e e e e o e ;: C C C 9 r .e e o e a c t' i E a lC C" C C C* C sc 0 C F. C C lC. C C C. C l e 46 v v =: 1 w 2' I l l '9 i, rC. =.i a a m. 1 1

a. a.

l .=- .: - r r_: z 6 .w e v 2 e r T 7 w i vi,z u ;z = z .e. -l 2 i .a .a e> 2 2 2 z ,e z e: 1 t .o;22 i C j i I 1 C-14 i ........e....e.e.pr.r._e,re.e e.-.~. , m.t pe.ta,:,:,:,re ,,:.e e r - :. :.,.. .,-.s. / w e. M-l ~ y ~ _-.. ]

L..... _ _ D 9 N-lTl)5Tdi'd a @lju. Mit A

a

o. o.

e o e e r n , =~.. ..=4... g;.

n. ; *:n M;;;;;;;; M g.:; it t.- 2:1I.1:: fl:;, T 2 !! O 3 L 0 3.1:"111:12 2

• L 1* 1G " g 1 G.;!:;t':? 0 :d*:2 i

o

• =

N N .= c N 4 m

• e=

m 4 c. m 4 O e= e. P= p

==i N. 4,. m 7 M. e. e=. N. N. W e es e e e e o . a. 4 m + m m n + + + 4 e 4 m e n m e 't3 en >4Cr .= 3 i C 4 4 7 4 e e m C m + =* N =e.- p. 6 .J 4 7 a. e. ar.t m. o. e.r 4 m. C. e. 7.6

1. et 4

C C C C O C C O C C

==

C

== Nt = C I p-I C e 3 e i N r C. C. C. C. C. O.. C. C.' O. C. c.' C. C. C.' O. C. C. d= e-O C C C C O-O C O C C C C C C C C i i' t W 4 C D-

== ae e ~ tu: em w , Om e f e g') - s.2 N. am e.4 C% IN =* 14 = e n- + 2 = n C O O. O. C., O. O. C.. O O. C. C. C. C. O. C. C. i==. C. C. C. i 2g w O O C O O C O O C .O C C C C C .I a O u N w 7

== C n-4 s e. 4 's=; C 4 u. fs s e. T 2 =. i w a O = * *, 3 4 =

• J iS l Z

.%3 ' O.O= l u= id 4w = 'Z en 'C C O N =. 4 C. C. C. C. O. C. C. O. .C. C. O. C. C.. C. C. C. -. 6 C -== 4 to. s

== c 4& C lT

• a e i O O

C O O C C C C C C C !3== .t e C C O C C 44 a 4

r. -

C .v - = O tw t O '&9 c. %.=E Iw 2 p- 's4 .4 e.= i

== c r 4N 2 =* sT . a.= I.w- 'lLA .O F = = * '2 4 C t' T C + 4C {a= 'O jeu e== N W N - N e c - WW c e N m J' 3 i O.? >= ' u lsa-w e. C. C. C. C. C. 'O.

== O. C,. C. C. U. C. C. = T ** iA.= t 4 m C C C C C C C C. C C C C C C G .D A N. 1N a 2 A.-, O 2-1 i w Y t c. wO 6 4 ,v ' e i== -c c t.J l3 f'= I 4 l4== l - s g t v

7 a. >

F !O

w. 2.

== t j

== 4 l t.e

== ** 4 a= 36 C ** 4 C 2 m P= os e e et ..z. J 'c A. C. 4 set. =. o. =.===.i e. c. 4 e. e. r. .s. = l i s.: -== I e i 1 3 f*

== c - O C C O C C C C C O C C C C 4l 8 .e-i

== x 2: a 8 ,"*A Q N t 89 I 4 l f e et O A - O e C m m 2 m e *= 4' O Je g M @l

1. . ?

N. N. N. N. t N. N. N. J. e f. O. t. .i e. g i s lC Ct O C C C C Q C C C C C ei ! cm e g I I 4 ~ 5 9 l I e f ( t .i i l 3 a P l C l

• z 3

. $3

=

=. .e N .n =9 N .M Pl ej m l i IC C.e C. l. C. O. C. C. C. C. C. C. f' '. C. C. .C. N. e o" , e je a C Of C c 0. O o C C C O C C 3 C C O! E .a [ 4 14 e W j . vo -l kh .I = j i i 1 . O I I TT 1 as .4 w. Ti

== .C n= e + u i, 3 2 T T sl ac c 4 t.

r u 7,

a 2

• .i. <

a i e r = z - rr 62 x l . 2.g .e d es e 3 3 3 2 3. O jee 2 gj Z w. an a i. O..= w

• O t

C-15 I

== l l t i l l l -i r--t .,y.. a;g.; 23; ; ..g.;.e.g.g,-

., ;-,; 3. ;. p,= 4 ;

.;p3 -...........=.....f.-.,

e

4. 5.*.s.-

7.- ..e l t

O D D T W; a W bU -.3,. 2is;;;;:.44.LI3 ;;4;f;j 3 ;;;;$3;,;.g

gag

............., - -. ^- r 4

• -.-(;

i i l, i .I I i j i 3 I i.= i e e. I l N.. C *. i e z o. a. m im + 'N.

c. !

e. .j cr..- e. ,e e. l u. $N. e..t N. se. N. e. w

• a im N1 N ce N

N IN N N 'm m m sN m N im N 'O e i i i s t> t e l I I. I '< C I' i i 7 i i a = i i I 3 l l l i 1 l l l l l l e e e w e o e.c 4 e e .e. C=. N 1 tC

• =

=. e,- e. N. .=. C. N. 4 i,st. e. C. ac. s. i .J i-= C o o O C C C C IC C C C O

== N I O l I' i l 6 e l i e i j l C. I 1 e N I F I C C C. C. C. C. C. C. O. C. O C C. C. C. C. 6 4 e to e 1 j = C C C C C O O C C #C C O 10 C O c o I I I l E I w I C. 10 i 1 %e i !u P= us g

1. w

• 4,L N C

l t.: 4

• a N

CL Ig N + e N a. 9 e in.= C C C C C O. C. pc. C. C C C a 7.J O. C. C. C. o. C. l 6.

• i*

l

• i.

r T w

s r x i-r C C C C C C C O C C C iC C C aC C i.O % l 3 is N j >r '.C 6d t g as s* C e la e. l ,1 I i ck

• =

g ! ,s a tr ..c= - l 'C - = = a se = lv i: r .c f 7 Cw = l f ,e l ~ ,e - {e - i

== C it .' O a al". C. C. O. C. C. C. C. C. C. C. C. C. C. C. i 'I ,z-4 M. IC 60 A.*. i l e l ? am !4 w Jw aY aE C C C iC C C C G C C C O aw C C o C i N. I tJ eI g a iv - 'O I I A -0 i e.s I l

t. r.

.N. . C ic '. =. te e. l> i n ,e +r I 4 .O fr + < *w W I. l T. 6=

4 x 1

u iw : -w '3

r et t

e-i l 4 Q ie

. e.-

1% ,e s O D ? N .mm .mn l b 'I C 6.* ngg jV .'e. O. ' m.- it-tw c. C. C. C. C. C. lC. C. O. C. C. C.

1. C.

C. C. ,' 7

; C.

l 1 4 i 1

D

= ' en N .C C O IC O O C C C K. C C tC C C C '. s P. -J i 3

== i ! *e -- v tv i ' l 6J 6 a IV o. l y

3 a=

e .O. I ar 6-icr T* i t v j l

1. 4 lv a-2 l

ir l i

r a l.>- tr j

l -a c6 1 e 'm =* IX .y i a N n. N m

== C C ir.

• =

e te c i l s, c. y2 a .4 r.d m. N. f. c. .c. C. C. c== ie. - o c. .r

== q. e e e z a-

C C

O C G C IC C C 10 O 10 C C IC t m .er. l i s-a i l '72 e 8 l i m-c i 40 I g t i a m j i i I I.

== ?- 1.* o e. 4

• • r to.

C. c. = N. C. O e. o. l7

c. l m

e e. p em g i i i. i j l 'O C C {0 C O iC O O C C C k.' r C C cl i i e ~ i s i 'a t 4 i i et l i O l i ~,. j l i. i i. l .c N n. - se e e at c. n.1 1 :: + l l ic. C. O. C. C. O. IC. C. O. C. C. C.

o. l e {.'

10 r'

• ==

I r l c o sc C O C C C n= r C i: C fr Cl r e cc t . =., t i v j k VL i I Mt i ) ) l i i i i , xe' I j =, 1 i T l l l w s' 12 7 e ? t2 r =:

1. o-w w

j 1s r r ->

2 1,z a..

x o - o e r

i

-

04 z 2' z W-e w 6e e Y 2 2 z + f =t 2 2' j i 421 j I i t O i i 8 f l c-16 I 77 e.-...t- .- 2,c, :. : : -,.

r.-:

s-g W .D %F map 4p 9 mr %r h 40.P g e-w d 8 m ~ w+

Df* }3.1 .=

g L _.

~ + c a-c a ... _.... -..... t :.=m :...,m u m m :.; =. e. u m : = ; m.. m.,e m. u.: u n.:.2. m e + l t f I I I e e m ~ ~ -, r e e c. f = o = c w e o a 4 ~ e o e u - o e i w e e o e e e e o e e4 e o e ei i

• A 4

m e h 4 ei p Ne e 4 M N 4 e i 6 2d W9 l 1 WC I 2 e 3 6 I i 4 P C e et N N se m e e P. N c .a G O O N t o 4 e o - e o C r 4 e= c 4 4 e 4 m m

1. 5 e

m et P= 4 e P. c 8 C

== 6 o I h t 1 1 0 1 l c N 2 =. a.' noe 4 7 + o .r I e C. C. O. o. C. O. C. C. O. C. o. o. C. o. o. e i = e i C C - o C C. O o C o C C o o C o o C I at I ana

== c , se e 4

w N W

az aN of C e me Q =s i A. t Q. c% ! , 2 N. 4 a.

=

N m n m o e .i

e P=

N 4 .'= C'. = C O C C =* mt =+ o

== c o. o

=

== c y: w a e e e o e e o e o e es e e e o e e

.c. 1 1

== + C C C C C O C G e C o o G o N O v N w 7 - a* l 4 yC W 4 e 1 X E .a:= as ge 9 a. e. 0 L lC T W %D 7 we .= te

7 IC.

--e 4 4 P=

== m m e es ? ? e o N e c *= 4 .t-8 4 m e ** ao se e p c C N v. e. 4 4 c.

e. i.

3 m. w ic = e e o e e m e e e e o >.a. s

a. m o

C -e. c C o o o . O es n e i .s. o C e o 4 s {c ir - lx-O ?: 4 O fW PO 2 g Y o= inn c I 4 . e== TZ

i. e

'4n * ' isJ f { a.- .=. K 'At 'd** X = q A a %b q 8 >E4 't I O t= C a

e s

'e w e

==

• 4 C

a* .a. e. e, e, s ?

. c oc o

~. ~ e e e ~ ~ r l-{ m Z. d 1 o e e e u

• J e

e e o e o e e O e of a 4.N. N N M

• • ='.

m 4 N se se en -. i e i ,s ' v v e s e m s c: ~ r-v 2 i ~ s .- 2 e i .z-r ss 4 l 'W "a .2u a mi a n. c -o e

e., o, s..

,r P. a e m ( n. e. ,r. <~ e. ~. ~. a

c. i

.w c. i n a. m me -. n, c. e, ce er e e e e l ..=g .= t*9 f i a e l E l l m ( 4 8 1 l 6 a l l tl r += o e ,cc ,,l ~ ,e C ce ,r e a, t c. 4 c.e

o.. e.

4

e.,

e.

s..i. lvs

.i e. 2

c..i 4

e e e l, e t, - m e o os o e er o o t c i. 4 8 i t + a a r. [ 6 i C t i i me i e t e i e x ,, o w c, -e e. i ao I. i i .a m .e i ,c ce c i. o.n o. o e o .c c.4i o

e.. o.

t 6 e lc. e se e J. i. $.c. e. .s : s C se c ci o o o ,ic c: o c c c -. r 6 - se r i i. j i v f i } 'J 9 i I i t c j i C Of l i I l h I . O i

r. wl

-o er .i e ei a ci l et is .!c - .-,1 T i 2. 2: 2 o a z: .z, o, z . 5g u

z I

t

z

.a a. ei a ,3. 2 m si : l .i r s } I j ,-7 I f i C t t a l l l I l l l i ~ ~ * ........g.:., e , :.;,.,.,.,.p.. 7 _m 4 t 6 0 9 e 9 4 e e 4 e e, 4 4 4 <a P.

APPENDIX D BRUNSWICK ONSITE METEOROLOGICAL MEASUREMENTS PROGRAM D.1 ONSITE OPERATIONAL PROGRAM A 360-foot, guyed, open-latticed tower supports the lower and upper levels of meteorological instrumentation. Wind direction, l wind speed, wind variance (sigma theta), and dew point tempera-tures are recorded at both levels. Ambient temperature is meas-ured at the lower level. The differential temperature between the upper and lower levels is measured by twin, redundant delta temperature systems operating simultaneously. Solar radiation and precipitation are collected near ground level. The wind sensors are mounted on 12-foot booms oriented perpendicular to the general northeast-southwest prevailing wind flow to mini-mize tower shadow effects. The temperature probes and lithium chloride dew point sensor are housed in Climet aspirated shields mounted on 8-foot booms. A complete specification of major sys-tem component operating conditions is presented in Table D-1; component manufacturer and manufacturer model numbers may be found in Table D-2. Operational sensor elevations are displayed in Table D-3 and component accuracies are shown in Table D-4. The meteorological tower is located 0.3 mile north-northeast of the reactor complex, with the base of the tower at 21 feet above mean sea level. An environmentally controlled shelter, which houses recording instruments, signal conditioning devices, and remote data access equipment, is located adjacent to the tower. The Westinghouse Environmental Monitoring System is the primary l data collection system. This system converts sensor outputs to a proportional number of discrete pulses that are electronically integrated and recorded on magnetic tape in 15-minute averaging periods. Also, a direct readout of any parameter is possible D-1 NUS CC APC AATICN i L

with this system. A test jack for each parameter is provided so that a pulse test counter may be plugged into it. The counter sums the pulses produced in a specific time interval, and the subsequent pulse total can then be converted to engineering units by use of a formula of the form y = mx + b. Esterline Angus Twin Strip Chart Recorders are used for providing an analog record of both the upper and lower level wind directions and speeds to back up the Westinghouse system. In addition, 15-minute averaged uppea and lower level wind speeds and directions, both differential temperatures, and ambient temperature parameters are telemetered to the CP&L general offices on an hourly basis via voice grade telephone lines to the site, giving CP&L the capabil-ity of detecting malfunctions of these parameters within 24 hours. D.2 DATA REDUCTION The Westinghouse system magnetic tape cassettes are changed and brought back to the general office approximately once per month l for translating. Computer programs convert all parameter pulse I totals into engineering units. The data is then reviewed and checked for consistency with the onsite strip charts and the Wil-mington, North Carolina, Weather Service data. The edited 15-minute averaged data is then compiled into hourly averages and stored on magnetic-history tapes. Routine computer outputs from the Westinghouse pulse data collec-tion system include the following: a. Monthly Data Summaries listing maximum temperature, minimum temperature, average temperature, barometric pressure, precipitation, solar radiation, and upper level and lower level dew point temperatures as a daily average and monthly average D-2 NUS CC APCAATICN

b, 'Iourly averages of precipitation, barometric pressure, ambient temperature, differential temperature, upper and lower level dew points, upper and lower level wind direc-tions and wind speeds, upper and lower level wind direc-tion variance (sigma theta), Pasquill stability classes (as outlined in Regulatory cuide 1.23) computed from the average of the two delta temperature systems, and accu-mulated solar radiation (langleys/ minute) c. The 15-minute averages of both upper and lower level wind directions, speeds, and sigma theta; barometric pressure; and accumulated solar radiation d. Joint w.nd frequency distributions by direction (as out-lined in Regulatory Guide 1.231 for both upper and lower levels, showing average wind speeds and number of unre-covered data hours The analog strip charts are changed twice per month. They are used as backup data to provide checks on the other systems and to provide consistency of data. D.3 MAINTENANCE AND CALIBRATION An onsite maintenance and calibration program was initiated in 1976. Regulatory Guide 1.23 data recovery requirements are met by performing scheduled calibrations carried out on a semiannual basis such that a. All wind systems are changed and replaced with National Bureau of Standards (NBS) traceable calibrated wind sensors, per Regulatory Guide 1.23 b. All ambient and dif ferential temperature systems are changed and replaced with NBS traceable calibrated sys-tems, per Regulatory Guide 1.23 l D-3 l NUS CCAACAATICN 1

The lithium chloride dew point sensor bobbin is changed c. d. The Cambridge dew point systems are changed e. Calibrations of the barometric pressure, solar radia-tion, and precipitation systems are verified (sensors are changed on an annual basis) f. All other onsite equipment is calibrated or its cali-bration is verified In addition to the scheduled calibrations, interim calibrations are perfomed at 6-week intervals. A further enhancement of data recovery is achieved by operating twin, redundant, delta tempera-ture systems simultaneously. Comparison of the two systems on a real-time basis through the hourly data (received at the CP&L general offices) gives CP&L the capability to detect discrepancies in either system, usually within 24 hours (except on weekends). l D-4 NUS CCAAQ AATION

TABLE D-1 OPERATING CONDITIONS Component Conditions Wind sensor -40 F to +120 F, up to 100 percent relative humidity, up to 125 mph wind speed l Temperature sensors -50 F to +130 F Aspirated temperature shields -60 F to +150 F Honeywell dew point sensor -40 F to +160 F, 11 percent relative humidity and above l l Cambridge dew point system l l Transmitter unit -80 F to +160 F Control unit -80 F to +120 F Total precipitation sensor No limitations l Solar radiation sensor No limitations Barometric pressure sensor -30 F to +170 F, 0 percent to 90 percent relative humidity i Magnetic tape recording packages -20 F to +140 F Strip chart recorder +20 F to +120 F Signal converter (transmuter) -40 F to +120 F, 5 percent to 95 percent i relative humidity TelecederR (encoder) 0 F to +120 F, 0 percent to 100 percent relative humidity at +77 F to +104 F without condensation i l l l I l D-5 l NUS CCAPCAATICN l

TABLE D-2 MAJOR COMPONENTS Camponent Manufacturer Model Ncmber Sensors Wind sensor Meteorology Research, Inc. 1074-22 l Single-element Rosemount 104ABG-1 temperature sensor Dual-element temperature Rosemount 104ABG-2 sensor Dew point sensor Baaeywell SSP 029D021 Total precipitation Weathetreasure Corp. P-511E sensor Solar radiation sensor Eppley Laboratory, Inc. 8-48 Barometric pressure Rosemount 1105A9Al sensor Cambridge dew point EG&G International, Inc. 110 sensor (transmitter unit) Sensor support equipment Cambridge dew point EG&G International, Inc. 110-C1 control unit l Strip chart recorders for Esterline Angus E1102R l wind speed and direction Aspirated temperature Climet 016-1 shield for single-element temperature l sensor Aspirated temperature Climet 016-2 shield for dual-element temperature sensor and Honeywell dew point sensor l l D-6 l l NUS CCP AC AATICN

? TABLE D-3 OPERATIONAL SENSCR ELEVATICNS Operational Elevations Sensor Above Tower Base (m) Wind 11.5 and 104.6 Honeywell dew point 10.2 Cambridge dew point 11.5 and 104.6 Solar radiation 1.5 Differential temperature 10.2 to 103.2 l Precipitation 1.5 Barometric pressure 1.5 l 1 I i D-7 NUS CC AACAATICN

l

l 1

TABLE D-4 00MPCNENT ACCURACY Component Accuracy Wind sensor 1 Wind speed 10.4 mph or 1 percent, whichever is greater = 1.0 mph Wind direction, O to 540 15.4 degrees Honeywell dew point sensor 12 F at or above 11 percent relative i humidity cambridge dew point system 10.5 F (error extreme) above a dew point of -20 F (excluding readout instrumentation). Error extreme increases in approximately linear fashion to 12 degrees at -80 F. Solar radiation sensor (pyranome ter) 10.04 calories / square centimeter / minute (langleys) Differential temperature system 10.186 F over ambient temperature range from -50 F to +130 F Ambient temperature system 10.498 F Magnetic tape recorder il pulse per interval Strip chart recorder il percent of full scale, direction = l 1 5.4 degrees, speed = 1 1.0 mph Total precipitation sensor 10.5 percent (calibrated at 0.5 inch per hour) Barometric pressure sensor 10.006 inch of :nercury (temperature effect: 10.1 inch of mercury per 100 l degrees of Fahrenheit operating tem-perature span) D-8 NUS CCAPCAATICN

APPENDIX E METHODS USED IN RADIOLOGICAL ANALYSIS The control room dose calculation computer program (AXIDENT) con-sists of a release pathway model and a dose evaluation model. The release model computes activity inventories and releases in the concainment and control room based on TID-14844 (Ref. 1) releases and prespecified flow rates, filter efficiencies, halogen non-l removal factors, and meteorological data. The program computes individual doses within the control room. E.1 RELEASE MODEL The activity release pathway model is shown in Figure E-1. Four activity nodes are represented: two primary containment volumes (sprayed and unsprayed), the secondary containment volume, and the control room. The equations for nodal activities, containment re-lease and integrated control room activity are derived from first order activity balances in the following paragraphs. The defini-tions of all variables used are presented in Section E.3. I E.1.1 Primary Activity The primary containment activity is the sun. vf the activity in i the sprayed and unsprayed regions. A = A7+A2 III p dA A A ~ ^1 ~ A A I) ~ ~ ~ dt sp l l l r 1 p l 2 dA A A A A2+ A (3) dt - 1 2 r 2 p 2 ~ ~ ~ 7 I E-1 NUS CO AACAATICN

The simultaneous solution of Equations 2 and 3 when combined with Equation 1 gives the primary containment activity as t -m2 - C e "I* (4) A =C e ~ p g A IA ~ *1) ~ A20 2 ~ "1) I 10 1 i C ($} 2 m2 ~ "1 A I ~*2)*A20 ( ~ "2 ) (6) C 10 1 = 1

• 2 ~*1 (A

'A } I7) m,m y 2 1 1 2 + f + f) _t (A +A + 3 1 2 ~t - 4 ($ Ai + f A; + Ai A;) A Ay+A*A

• A (8)

= 7 r p sp Ah = A1 + A, + A (9) p l -m2: _ C, e-m1= (10) 2 C, = e 1 l l t E-2 NUS CCAAQAATICN i

Ato ( 1 1+y ), A -m 20 C (ll) = 4 m2 ~*1 A10 ( 1 ~ *2 + V } V

1. 20 C

(12) = 3 m -m 2 1 3 ) eN (13) (C -C)e"2 ~ (C -C A = 2 2 4 7 Note that the above solution for Ap degenerates to a one-volume problem if.\\sp = 0. E.1.2 Secondary Activity The rate of change of secondary containment activity is the frac-tion of the primary activity that goes to the secondary contain-ment less the removal by decay, cleanup, and leakage (or exhaust) to the environment. dA dt s 1 p 3 A, -AA ( A ~ ~ r s s s I A A (15) ~ s 1 p 4 s A3+r (16) A + 4 s 's 's 1 g C 1 2 -m t ,m, + C5*zt ^ 1 e s A -m A ~ "I (17) 4 2 4 l [ f A C I C f s t 2 s 1 1 (18) A ~ 5 so A -m A ~ "1 4 2 4 E-3 1 NUS CC AAC AATICN

E.1.3 Containment Activity Release Rate The containment activity release rate has two components: the secondary containment release after filtration, and the fraction of the primary containment leakage that bypasses the secondary containment. FA A +( 1 ^p (19) R = ~ r 3 s s ~*2 e'*1 FA f A e R = r 3 s 1 A -m A 4 2 4 ~*1 (20) 4* ~ - FA C. e + 3 a I (1 - f ) A C e 2 -C e"*1 3 t 2 1 C. e"*2 -C e"*1 +C e 4 (21) ~ R = e o 7 3 FA f ~ 3 s +1-f A C (22) C. = l e A -m s 1 2 4 2 l FA f, (23) 3

• I~I C

C = 7 A -m s 1 g 4 1 L 8 3 5 (24) l t E-4 NUS CCAAC AATION L.

1 E.1.4 Integrated Release from Containment The integrated release from the containment is obtained by inte-grating the release rate, Equation 21, over the time period of interest. =[R dt R r (25) C g 1,,m2 t) _ C C 4 R 6 7 (t_,-mtj _9 {3,,-14t) (26) =

• 2
• 1 4

E.1.5 Control Room Activity The rate of change of activity in the control room is the dif-ference between the rate at which activity is drawn in from 4 the outside air and the rate at which it is removed by decay, cleanup, and leakage (or exhaust). 9 F2 "cc ( -A ^ dAc A ~*c^c (27) = ~ c r r c V c dt ec d A e- =C R-AA (28) g 7 et A =A + cc +x (29) 7 r e cc I I F G (30) C = g 2 ec c t ~mi

• C C 2 -C C e

=C C e 8* c g 6 g 7 g -xA (31) 7 c CC g 6 -m2t 9 7 -At 4 9 -AC4 ^c + 7 2 ^7 ~*1 x -m A 7 ^4 +C 10

• e E-5 NUS CC APC AATICN

I i CC CC CC g6 g 7 o g C =A + (33) 10 co x7 2

• 7 ~ *1 A

-m 7 ~*4 E.1.6 Integrated Activity in Control Room ~ The integrated activity in the control room is obtained by inte-grating Equation 32 over the time period of interest. R A dt (34) = i C C. CC t g7 o ~ *1)(1 3-m)f) (1. e-m2 ). R = c (1 - m }*2

• 1 IA

( } 7 2 7 ~ h *) (1 - e 4') + (1-e 7 + ) Implicit in the above derivations is the assumption of constant coefficients. In the actual transient simulation, solutions are I broken into a sequence of discrete time intervals over which the input parameters that make up the coefficients are prespecified constants. The input parameters consist of flow rates, X/Qs, de-cay and iodine removal constants, provided as stepwise constant: functions of time. Initial secondary containment and control room activity inventor-les are assumed to be zero. Initial primary activity may be based on the analysis of TID-14844 (Ref. 1) using the fractional iodine i release assumptions of Regulatory Guide 1.3 (Ref. 2) or 1.4 (Ref. 3). The source term equation is -AT A = 8.65 x 10 Pg fr1(1-e ) (curies) (36) o E-6 NUS CCAPCAATION

= - - I 1 i E.2 DOSE MODEL At the end of each time interval, control room individual thy-roid and whole body doses are determined using the containment a ] release rate, integrated control room activity, and input values of X/Q at the control room intake. Thyroid inhalation dose in the control room is given by the following equation: D (rem) (37) D = T T t i BR R DCF g i Cc 1 where i BR = breathing rate j = 3.47 x 10-4 m3 sec (Ref. 4) / l Beta dose in the control room is given by: j=[i D,1 (rem) (38) D Y*1 0.23 R V 1 (39) cc l where l l E3 = average beta energy (MeV/ dis) (See Table E-2. ) E-7 I t NUS CCPPCPATICN l

Gamma dose in the control room is given by = }] D (rem) (40) D y y i i O 25 f [R [E,1,j f 1 - e" #j 1

• u -8,j

_) r = j (41) cc 1 i j Gamma energies and fractions are presented in Table E-1. Absorp-tion coefficients divided by the density of air are listed in Table E-2. E.3 NOMENCLATURE Ap = Primary containment activity A1 = Activity in sprayed volume A2 = Activity in unsprayed volume .Al = Primary containment leak rate Ar = Radiological decay constant (Sec~1) (See Table E-1) Ap = Cleanup rate in primary containment fi = Fraction of activity released to sprayed volume f2 = Fraction of activity released to unsprayed volume Vi = Sprayed volume V2 = Unsprayed volume A3 = Secondary leak rate Spray removal rate Asp = Fraction of primary leakage fs= ich enters secondary F = Filter non-removal factor for secondary building exhaust system F2 = Filter non-removal factor for control room (center) intake system (X/Q)e = Atmospheric dispersion to control center qcc = Control center intake flow Vee = Control center volume Eyi = Average gamma energy (Me'V/d i s) (See Table E-2) Edi = Average beta energy (MeV/ dis) (See Table E-2) Ri = Integrated release from containment (Ci) Vcr = Control room free volume (m3) Eyi,j = Energy of jth gamma of ith isotope (MeV/A) (See Table E-3) f,j = Fraction of jth gamma of ith isotope (T/ dis) ia. = Energy absorption coefficient for air (m-1) (See 3 Table E-4) uj = Total absorption coefficient for air (m-1) (See Table E-4) r = Radius of hemisphere with same volume as control room (m) As = Cleanup rate in secondary containment E-8 NUS CCAPC AATICN

.\\c = Cleanup rate in control room Vee = Control center free volume (m3) Re = Integrated control room activity (Ci-sec) DCF[=Doseconversionfactor (rem / curie) (See Table E-2) Po = Base loaded core power (Mwt) Yi = Fission yield (percent) (See Table E-1) To = 1000 days (assumed) fr = Fraction of core inventory available for release = 0.25 (for iodines) (Ref. 2) = 1.0 (for noble gases) fi = 0.91 (for elemental iodine) (Ref. 2) = 0.05 (for particulate iodine) = 0.04 (for organic iodine) = 1.0 (for noble gases) Q = Mixing flow rate between sprayed and unsprayed volumes E.4 CALCULATION OF DOSE DUE TO DIRECT RADIATION FROM THE BRUNSWICK REACTOR BUILDING The QAD code (5) (Ref. 5) is used to compute the integrated dose to different points within the control building from direct radiation from the reactor building after a postulated loss-of-coolant accident. QAD is the generic designation for a series of point-kernal computer programs designed for estimating the effects of gamma rays and neutrons that originate in a volume-distributed source. Gamma ray dose rates, energy depositions, uncollided fluxes, and associated quantities; as well as inter-polated moments-method neutron fluxes, energy depositions, and dose rates, may be calculated. Surfaces, defined by quadratic equations, are used for a three-dimensional description of the physical situation. Speed, flexibility, and ease of use, as well as the ability to mock-up any direct-beam radiation problem, contribute to the utility of the program. l l E-9 l NUS CC APCAATICN l

The source used is based on the following equations: dA 1 " "A A ( dt 11 dA2 foi dt Y A -1A 1 22 jy where e 1\\ A =A +l l 1 r ( 3 1 1 A2"Ar+ l)2 A = radionuclide decay constant (br-1) r IIh = primary containment leakage rate (hr-1)

0) 1

= 0.5 percent / day = 2.1 x 10-4 hr-1 i l l = removal rate due to Standby Gas Treatment System (SGTS) operation (hr-1) = 9.0 x 10-2 hr-1 (based on an SGTS flowrate of 3000 cfm and a secondary containment volume of 2 x 106 3 ft), The solution to the above equations is: A (t)1 =A e (3) 1 10 l l E-10 NUS COAPC AATION

I A j A e ^1 1 1 ~ ~ ,e 2 (4) A,(t) = 7. 3 7. (^2' 1) [2 1) ~ ~ where i j A10 is the initial activity in the primary containment A2 (t) is the total secondary containment activity (Ci) A1(t) is the total primary containment activity (Ci) i I i i E-ll NUS CCAPCAATICN m -

E.5 REFERENCES 1. J. J. DiNunno et al. 1962. Calculation of Distance Factors for Power and Test Reactor Sites. TID-14844. 2. U.S. Atomic Energy Commission. 1973. Regulatory Guide 1.3, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors." Rev. 1, Directorate of Regulatory Standards. 3. U.S. Atomic Energy Commission. 1974. Regulatory Guide 1.4, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors." Rev. 2, Directorate of Regulatory Standards. 4. International Commission on Radiological Protection. 1959. Reoort of Committee II on Permissible Dose for Internal Radiation. Pergamon Pres. 5. CA-3573, QAD-Point-Kernal General Purpose Shielding Codes, l Oak Ridge National Laboratory. 6. M. E. Meek and 3. F. Rider. 1968. Summarv of Fission Product Yields for U235, Pu 39, and Pu 41 at Thermal, 2 2 Fission Spectrum and 14 MeV Neutron Enercies. APED-5398. l 7. C. M. Lederer et al. 1968. Table of Isotopes. 6th edition. New York: John Wiley and Sons. l l 8. " Final Environmental Statement Concerning Proposed Rule Making Action: Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low as Practicable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents," WASH-1258, Volume 2, Directorate of Regulatory Standards, U.S.A.E.C., July 1973. l E-12 NUS CCRPCRATION

9. J. H. Hubbell. 1969. " Photon Cross Sections, Attenuation Coefficients, and Energy Absorption Coefficients from 10 kev to 100 GeV," NSRDS-NBS 29. t l l i 1 l l 1 l l l l E-13 NUS CC APC AATION l

TABLE E-1 NUCLIDE DECAY CCNSTANTS AND FISSICN YIELDS (Ref. 6) Decay Constant Fission Yield Nuclide (sec~l) (percent) Il31 9.97 (-7) a 2.91 Il32 8.37 (-5) 4.33 Il33 9.17 ( 6) 6.69 Il34 2.22 (-4) 7.8 I135 2.87 (-5) 6.2 Kr83m 1.03 (-4) 0.52 Kr85m 4.38 (-5) 1.3 Kr85 2.04 (-9) 0.27 Kr87

1. 5 2 (-4 )

2.5 Kr88 6.88 (-5) 3.56 Xe 31m 6.79 (-7) 0.022 l Xel33m 3.55 (-6) 0.17 Xel33 1.52 (-6) 6.69 135m

7. 40 (-4) 1.8 Xe l35 2.11 (-5) 6.3 Xe Xel38 6.60 (-4) 5.9 aRead as 9.97 x 10~7 I

l E-14 NUS OCAAC AATICN

TABLE E-2 AVERAGE BETA AND GAMMA ENERGIES AND IODINE INHALATION DOSE CONVERSION FACTORS Nuclide Y(MeV/ dis) (Ref. 7) $(MeV/ dis) (Ref. 7) DCF (rem / curie) (Ref. 8) I131 0.371 0.197 1.48 (+6) 1132 2.40 0.448 5.35 (+4) Il33 0.477 0.423 4.00 (+5) 134 1.939 0.455 2.50 (+4) I Il35 1.779 0.308 1.24 (+5) Kr83m 0.005 0.034 Kr 5m 0.156 0.233 8 Kr85 0.0021 0.223 Kr37 1.375 1.050 Kr88 1,743 o,341 Xe 31m 0.022 0.135 l Xel33m 0.033 0.155 Xel33 0.030 0.146 Xe135m 0.422 0.097 Xel35 0.246 0.322 Xel38 2.870 0.800 l l l E-15 NUS CORACAATICN

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I TABLE E-4 ABSORPTION CCEFFICIENTS FOR AIR (Ref. 9) g g/, (a) Ma/o(b) 2 MeV cm /gm 0.01 4.99 4.61 0.015 1.55 1.27 0.02 0.752 0.511 0.03 0.349 0.148 0.04 0.248 0.0669 0.05 0.208 0.0406 O.06 0.188 0.0305 l 0.08 0.167 0.0243 0.1 0.154 0.0234 0.15 0.136 0.0250 0.2 0.123 0.0268 0.3 0.107 0.0288 0.4 0.0954 0.0295 0.5 0.0870 0.0297 O.6 0.0805 0.025' O.8 0.0707 0.0289 1.0 0.0636 0.0280 1.5 0.0518 0.0257 2.0 0.0445 0.0238 3.0 0.0358 0.0212 4.0 0.0308 0.0194 aFrom Table 3.-27, NSRDS-NBS 29. b From Table 1.-7, NSRDS-NBS 29. 1 E-18 NUS CCAACAATICN}}