Text

Environ Rept for Facility,Vol 3
	ML17296A542
Person / Time
Site:	Palo Verde
Issue date:	12/05/1979
From:	; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
Shared Package
ML17296A539	List: ML17296A541; ML17296A542;
References
	ENVR-791205-02, ENVR-791205-2, NUDOCS 8001090295
	Download: ML17296A542 (195)
	v • d • e

PALG VERGE NUCLEAR GENERAL(MG SYATIGM KMW)%0>M5lKRUR,ll lRKP > IK O~HlK'i7llM% UXKR0% K'/MAL 0

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cX PVNGS ER-OL CHAPTER 3 THE STATION CONTENTS Pa<ac 3.1 EXTERNAL APPEARANCE 3.1-1 3.1.1 DESIGN OBJECTIVES 3 1 1

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3.1.2 SOURCES AND PUBLIC EXPOSURE 3 e 1~1 3.1.2.1 View From Wintersbur 3~1 2 3.1.2.2 View From Northeast 3.1-2 3.1.2.3 View From Ward Road 3~1 2 3.1.3 SPECIFIC FEATURES 3~1 2 3.1.3.1 Power Block Com lex 3~1 3 3.1.3.2 Other Structures 3.1-4 3.

1.4 CONCLUSION

3.1-4 3.2 REACTOR AND STEAM-ELECTRIC SYSTEM 3.2-1 3.3 PLANT WATER USE 3 ~3 1 3.3.1 INFLUENT WATER SOURCES 3. 3-1 3.3.2 PLANT WATER USES 3 ~3 2 3.3.2.1 Circulatin Water S stem 3 3 2

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3.3.2.2 Ess'ential S ra Pond S stem 3~3 2 3.3.2.3 Domestic and Demineralized Water S stems 3~3 3 3.3.3 PLANT WASTE WATER 3 3 3

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3.4 HEAT DISSIPATION SYSTEM 3.4-1 3.4.1 CIRCULATING WATER SYSTEM 3.4-1 3.'4.1.1 Main Condenser 3.4-1 3.4.1.2 Circulatin Water Pum s 3.4-2 3.4.1.3 Plant Coolin Water Pum s 3.4-2 3.4.1.4 Coolin Towers 3.4-2 3.4.1.5 Chemical In'ection S stem 3.4-4 3.4. 1. 6 Makeu Water S stem 3.4-4 3.4.1.7 Blowdown S stem 3.4-4

PVNGS ER-OL CONTENTS (cont)

PacCe 3.4.2 OTHER COOLING WATER SYSTEMS 3.4-11 3.4.2.1 Turbine Coolin Water S stem 3.4-11 3.4.2.2 Nuclear Coolin Water S stem 3.4-11 3.4.2.3 Essential S ra Pond S stem 3.4-11 3.4.2.4 Essential Coolin Water S stem 3.4-12 3.5 RADWASTE SYSTEM AND SOURCE TERM 3.5-1 3.5.1 SOURCE TERM 3.5-3 3.5.1.1 Tritium Source Terms and Releases 3.5-3 3.5.1.2 Secondar S stem Sources 3.5-5 3.5.1.3 Fuel Pool Source Terms 3.5-5 3.5.1.4 Leaka e Sources 3.5-6 3.5.2 LIQUID RADWASTE SYSTEM 3.5-11 3.5.3 GASEOUS RADWASTE SYSTEM 3.5-11 3.5.4 SOLID RADWASTE SYSTEM 3.5-30 3.5.5 PROCESS AND EFFLUENT MONITORING 3.5-30 3.5.5.1 Desi n Ob'ectives 3.5-41 3.5.5.2 S stem Descri tion 3.5-42 3.6 CHEMICAL AND BIOCIDE WASTES 3.6-1 3.6.1 PREOPERATIONAL AND PERIODIC CLEANING WASTES 3.6-1 3.6,.2 NONRADIOACTIVE OPERATIONAL WASTES 3.6-2 3.6.2.1 Water Reclamation Plant 3.6-5 3.6.2.2 Circulatin Water S stem 3.6-9 3.6.2.3 Domestic Water S stem 3.6-10 3.6.2.4 Demineralized Water S stem 3.6-11 3.6.2.5 Condensate Polishin Demineralizer S stem 3.6-11 3.6.2.6 Laboratories and Dr Cleanin Laundries 3.6-12 3..6.2.7 Floor Drains 3.6-12 3.6.3 NONRADIOACTIVE LIQUID WASTE DISPOSAL 3.6-13 3.6.3.1 Eva oration Ponds 3.6-13 3.7 SANITARY AND OTHER WASTE SYSTEMS 3~7 1 3.7.1 LIQUID WASTES 3 7 1

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3-3.3.

PVNGS ER-OL CONTENTS (cont)

PacCe 3.7.1.1 Sanitar Wastes 3.7-1 3.7.1.2 Other Li uid Wastes 3 ~ 7~2 3.7.2 SOLID WASTES 3~7 2 3.7.2.1 Sources of Solid Waste 3 ~ 7~2 3.7.2.2 Solid Waste Dis osal Area 3 7 3

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3.7.3 GASEOUS EFFLUENTS 3~7 3 3.7.3.1 Diesel Generators 3 ~7 3 3.7.3.2 Auxiliar Boilers 3~7 3 3.7.3.3 Water Reclamation Plant 3.7-4 3.8 REPORTING OF RADIOACTIVE MATERIAL MOVEMENT 3.8-1 3.9 TRANSMISSION FACILITIES 3.9-1 3.9.1 ELECTRIC TRANSMISSION FACILITIES 3.9-1 3.9.1.1 Transmission Route Descri tions 3.9-2 3.9.1.2 3.9-6 3.9.1.3 3.9-7 3.9.1.4 ~btructures 3.9-10 3.9.2 PVNGS WASTEWATER CONVEYANCE SYSTEM 3.9-13 3.

9.3 REFERENCES

3'. 9-14 APPENDIX 3A RESPONSES TO NRC UESTIONS

PVNGS ER-OL TABIES Pacae 3.2-1 Station Gross Heat Rate vs Power Level 3 ~2 2 3.4-1 Design Characteristics of Round Mechanical Draft Cooling Tower System 3.4-3 3.4-2 Anticipated Monthly Evaporation Variation (Each Unit) 3.4-5 3.4-3 Daily Wet-Bulb Cumulative Distribution Chart 3.4-7 3.4-4 Essential Spray Pond System Water Quality Specification 3.4-13 3.5-1 Expected Primary Coolant Activities 3.5-4 3.5-2 Expected Annual Tritium Releases 3.5-6 3.5-3 Expected Secondary System Activities 3.5-7 3.5-4 Refueling Activities 3.5-9 3.5-5 Assumptions Used in Determining Airborne Radioactivity 3.5-12 3.5-6 Normal Airborne Radioactivity Concentrations 3.5-14 3.5-7 Waste Inputs to the LRS 3.5-16 3.5-8 Maximum Radioactivity Inventories of Equipment in the Radwaste Building 3.5-18 3.5-9 Liquid Radwaste System (LRS) Equipment Descriptions 3.5-22 3.5-10 Major Sources, Volumes, and Flowrates of Gases to the Gaseous Radwaste System 3.5-29 3.5-11 Gaseous Radwaste System Process Equipment Description 3.5-30 3.5-12 Normal Radiological Releases 3.5-31 3.5-13 SRS Input Activities 3.5-32 3.5-14 SRS Output Activities 3.5-36 3.5-15 SRS Equipment Descriptions 3.5-40 3.6-1 Estimated Maximum and Average Concentration of Chemicals in the Influent and Effluent Water Systems 3.6-3 3.9-1 Land Type Adjacent to Wastewater Conveyance Pipeline 3.9-14

PVNGS ER-OL FIGURES 3.1-1 Artist's Conception of V

PVNGS 301-2 Oblique Aerial View 3 1 3

~ Vicinity Map

3. 1-4 Site General Arrangement 3.1-5 Plan View Lines-of-Sight 3.1-6 Line-of-Sight Profiles 3.1-7 Typical Power Block 3.1-8 South Elevation of Typical Unit 3.1-9 West Elevation of Typical Unit 3.1-10 East Elevation of Typical Unit

.f 3.1-11 North Elevation of Typical Unit 3 3 1

~ Palo Verde Nuclear Generating Station Water Use 3.4-1 Generalized Heat Dissipation System Flow Diagram 3.4-2 Basic Flow Diagram Circulating Water System 3.4-3 Design Range Cooling Tower Performance Curve 100% Flow 3.4-4 Design Range Cooling Tower Performance Curve 90% Flow 3.4-5 Cooling Tower Evaporation Curve 100% Flow 3.4-6 Cooling Tower Evaporation Curve 90% Flow 3.4-7 Cooling Tower Discharge Air Temperature 3.4-8 Typical Cooling Tower 3.4-9 Basic Flow Diagram Essential Spray Pond System 3 ..5-1 Tritium Balance Flow Diagram 3.5-2 PSI Diagram Liquid Radwaste System 3.5-3 Basic Flow Diagram Liquid Radwaste System 3.5<<4 P&I Diagram Gaseous Radwaste System 3.5-5 Basic Flow Diagram Gaseous Radwaste System 3.5-6 PSI Diagram Solid Radwaste System 3.5-7 Basic Flow Diagram Solid Radwaste System 3.6-1 Water Reclamation Plant - Schematic Flow Diagram 3.6-2 Circulating Water and Plant Cooling Water Systems Schematic Flow Diagram 3-v

PVNGS ER-OL FIGURES (cont)

3. 6-3 Domestic Water System, Schematic Flow Diagram 3.6-4 Demineralized Water System Schematic Flow Diagram 3.6-5 Condensate Polishing Demineralizer System Schematic Flow Diagram 3.9-1 Transmission Line Routes Project 1 3.9-2 transmission Line Route Project 3 3.9-3 500 kV Steel Lattice Tower Project 1 3.9-4 345 kV Transmission Line Structure 3.9-5 PVNGS Water Conveyance Pipeline 3 vi

PVNGS ER>>OL

3. THE STATION 3.1 EXTERNAL APPEARANCE The external design of PVNGS has not changed significantly from that presented in ER-CP Section 3.1 and the FES. The external design is summarized in this section.

3.1.1 DESIGN OBJECTIVES Design objectives for PVNGS ensure that plant facilities and landscape are compatible with the existing environment. These objectives have been to:

o Organize buildings, exposed equipment; roads, parking, and railroad to create a pleasing visual image o Incorporate regional architecture, building materials, and colors into plant design o Allow the site to revegetate naturally, without.

extensive landscaping o Arrange the areas of water impoundments on the site in a manner to enhance the overall appearance of the terrain.

Figure 3.1-1 is an artist's conception of PVNGS.

3.1.2 SOURCES OF PUBLIC EXPOSURE A recent oblique aerial photograph of the site area is shown on figure 3.1-2 and the vicinity map is shown in figure 3.1-3..

The general arrangement of the site is shown in figure 3.1-4.

Najor areas from which the plant is normally visible to the public are Buckeye-Salome Road, north of the station; and Ward (Elliot) Road, south of the station. The plant is also visible from segments'of Interstate 10, in the vicinity of the station.

PVNGS ER-OL EXTERNAL APPEARANCE There are no major roads west of the station. The flat land between the station site and the rugged Palo Verde Hills is partly used for agriculture. The Phoenix Valley West develop-ment noted in the ER-CP is no longer planned. Figure 3.1-5 shows the lines-of-sight from which the profiles of fig-ure 3.1-6 were derived.

3.1.2.1 View From Wintersbur Wintersburg is located at the intersection of Buckeye-Salome and Wintersburg Roads, approximately 2 miles north of the station. The station is only partially visible from this line-of-site because the hills at the north boundary of the station site interrupt the sight lines (see figure 3.1-6, profile 1).

3.1.2.2 View From Northeast PVNGS is visible to the public travelling on Buckeye-Salome Road along a 2-mile stretch northeast of the station, looking southwest through the gap between hills north and east of the site. Distance to the station is 2 to 3 miles, and the highest structures of the station appear much lower than the Palo Verde Hills in the background (see figure 3.1-6, profile 2).

3.1.2.3 View From Ward Road Ward Road is a rural road south of the station site and serves the agricultural area west of the site. The station is visible from Ward Road at a distance of 3 miles and looking north (see figure 3.1-6, profile 3).

3.1.3 SPECIFIC FEATURES PVNGS consists of three identical power blocks arranged in a c'rcular arc near the northwest portion of the site as

PVNGS ER-OL EXTERNAL APPEARANCE shown on the site general arrangement plan. in figure 3.1-4.

Figure 3.1-7 shows a typical power block in isometric form.

Figures 3.1-8 through 3.1-11 illustrate the four main eleva-tions of the power block.

3.1.3.1 Power Block Com lex Each power block complex consists of the following major structures:

o Containment building

~ Auxiliary building o Fuel building o Control building o Turbine building o Diesel generator building o Radwaste building o A laundry and decontamination facility at Unit, 1 only The containment is a cylindrical concrete structure with a hemispherical dome and is the highest part of the power block.

The containment is surrounded by lower power block structures.

With the exception of the turbine building, all other structures of the power block are constructed of concrete. The turbine building consists of a structural steel frame enclosed with con-crete base and metal siding walls of a color to complement the other structures within the complex.

3 1 3

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PVNGS ER-OL EXTERNAL APPEARANCE The locations of the release points for gaseous wastes are illustrated on figure 3.1-9.

3.1.3.2 Other Structures Each power block is served by cooling towers located west or northwest of the power block. Other structures in the plant area include the administration building, the guardhouse, service warehouse building, water reclamation plant, switch-yard structures, and miscellaneous ancillary buildings. These structures have low silhouettes.

3.1".4 CONCLUSION Because of the distances of the vantage points from the station and the high Palo Verde Hills backdrop, the visual impact to the public is negligible.

No properties listed in the National Register of Historic Places exist near the vicinity of the site, therefore there is no visual or aesthetic plant impact upon these properties.

3.1-4

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ER-OL LINE-OF-SIGHT PROFILES Figure 3.1-6

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EL 290 FT -7 IN EL 240 FT - 0 IN CONTAINMENT BUILDING TURBINE BUILDING EL 194 FT4 IN.~

EL 180 FT-0 IN Il FUEL BUILDING EL 166 FT -0 IN~

CONTROL BUILDING CORRIDOR STRUCTURE EL 140 FT -0 IN RAOWASTE BUILDING EL 130 FT-0 IN DIESEL GENERATOR BUILDING EL 120 FT -0 IN SWITCH GEAR EL117 FT-0 IN BUILDING HOLD.UP REFUELING TANK WATER TANK LRS TANKS INSTRUMENT REPAIR FACILITY GRADE SOUTH ELEVATION EL 100 FT - 0 IN SCALE 1/32" = 1'0" Palo Verde Nuclear Generating Station ER-OL SOUTH ELEVATION OF TYPICAL UNIT Figure 3.1-8

EL 290 FT-7 IN CONTAINMENT BUILDING EL 194 FT-4 IN EL 180 FT -4 IN FUEL BUILDING FT-4 IN CONTROL BUILDING EL 156 EL 166 FT-0 IN STAIRS EL 146 FT - 0 IN AUXILIARY REACTOR MAKE.UP EL 160 FT -0 IN BUILDING WATER TANK DIESEL GENERATOR RADWASTE BUILDING BUILDING CONDENSATE HOLD.UP TANK TANK LRS TANKS GRADE EL 100 FT - 0 IN WEST ELEVATION Palo Verde Nuclear Generating Station ER-OL WEST ELEVATION OF TYPICAL UNIT Figure 3.1-9

EL 290FT-7IM CONTAINMENT BUILDING EL 240 FT - 0 IN TURBINE BUILDING CONTROL BUILDING EL 180 FT-0 IN EL186 FT-0 IN EL 156 FT -0 IN EL 146 FT - 0 IN CORRIDOR BUILDING AUXILIARY BUILDING EL 130 FT-0 IN EL117 FT-0 IN DIESEL GENERATOR BUILDING SWITCH GE AR CONDENSATE BUILDING INSTRUMENT TANK REPAIR FACILITY GRADE EL 100 FT-0 IN Palo Verde Nuclear Generating Station ER-OL EAST ELEVATION OF TYPICAL UNIT Figure 3.1-10

EL 290 FT-7 IN EL 240 FT - 0 IN CONTAINMENTBUILDING STAIR 5 ELEVATOR EL 194 FT -4 IN EL 159 FT ~ 0 IN FUEL BUILDING MAIN STEAM SUPPORT STRUCTURE REACTOR CONDENSATE MAKE-UP WATER TANK TANK GRADE EL 100 FT. 0 IN Palo Verde Nuclear Generating Station ER-OL NORTH ELEVATION OF TYPICAL UNIT Figure 3.1-11

PVNGS ER-OL 3.2 REACTOR AND STEAM-ELECTRIC SYSTEM Design parameters of the reactor and steam-electric system have not changed significantly since the ER-CP. This section t

summarizes design details.

Each PVNGS unit contains a nuclear steam supply system (NSSS) powered by a light-water moderated and cooled, pressurized water reactor (PWR). Each reactor is fueled with 102,780 kg of slightly enriched uranium in the form of sintered uranium dioxide (UO2) pellets clad in 56,876 zircalloy-4 fuel rods.

Four-fingered and 12-fingered control element assemblies (CEAs) are used in the core. The CEAs provide short-term reactivity control under normal and anticipated transient conditions.

Each NSSS has a rated core thermal power of 3800 MWt. The reactor coolant pumps add 17 MWt of heat for an NSSS power level of 3817 MWt. The turbine-generator gross generator out-put corresponding to 3817 MW is 1304 MWe at, design condenser back pressure of 3.5 in. Hg absolute. The nominal net output of each PVNGS unit is 1270 MWe. Each turbine-generator consists of a tandem compound type, six flow exhaust, 1800 r/min, steam turbine with 43-inch last stage buckets (blades). The turbine-generator is hydrogen cooled with a 0.9 power factor and operates at 24 kV, 3-phase and 60 Hz.

The relationship between the station gross heat rate and unit load is summarized in table 3.2-1.

The condenser is a three shell, single pass, multipressure, reheat condenser. The circulating water is divided into two parallel paths for a total design flow of 560,000 gal/min.

9 The heat rejection rate is 8.9 x 10 Btu/h with a temperature rise of 32.1F. The titanium tubes (25,426 per 2 shell) provide a total effective surface area of 1,123,000 ft .

The design lifetime of each PVNGS unit is 40 years.

3I2-1

PVNGS ER-OL REACTOR AND STEAM-ELECTRIC SYSTEM Table 3.2-1 STATION GROSS HEAT RATE VS..POWER LEVEL Station Gross Heat Rate Power (Btu/kWh) 60% ll,014 10,320 80'00%

(3817 MWt) 9,987 Stretch (Valves Wide Open) 9,998

a. At design condenser backpressure of 3.5 in. Hg absolute.
3 ~2 2
PVNGS ER-OL 3.3 PLANT WATER USE Parameters of plant water use have not changed substantially from those presented in ER-CP Section 3.3 and the FES. This section provides additional, information and summarizes PVNGS water use.
Figure 3.3-1 presents a schematic, flow diagram of the basic plant water use and lists 'the expected maximum, average, minimum, and shutdown'flow rates of those water systems that require makeup and/or generate waste.
3.3.1 INFLUENT WATER SOURCES There are two influent water sources to PVNGS. The primary plant water source is waste water effluent from the City of Phoenix 91st Avenue Sewage Treatment Plant. The processed effluent, is delivered to the onsite water reclamation plant via pipeline from the 91st Avenue Sewage Treatment Plant.
It is further .treated and then stored in the onsite reservoir.
No surface diversion occurs. The secondary plant water source is from on-site wells that. supply water to the domestic water system. The two onsite wells are shown in figure 3.1-4.
The wells are located wholly within the site boundary. No well water will be used offsite. The effect of well water withdrawal on the local groundwater hydrology is discussed in section 5.6. The domestic water system supplies potable water to each generating unit for domestic, utility, and air conditioning services.
The total annual makeup water requirement for PVNGS from the city of Phoenix is estimated at, 21,350 acre-feet per year per unit. The average well water requirement is'app'rox-imately 1300 acre-feet per year for all PVNGS units.
The water reclamation plant and the domestic water system are described in section 3.6.
3.3-1
PVNGS ER-OL PLANT WATER USE 3.3.2 PLANT WATER USES 3.3.2.1 Circulatin Water S stem Each unit,'s circulating water system removes waste heat resulting from normal operation of the unit and rejects it to'he atmosphere via the three cooling towers in each system.
Heat rejection is accomplished by the evaporation of a portion of the circulating water flow. To maintain the chemical concentration of circulating water at or below 15 .times that of makeup water (15 cycles of concentration), a quantity of water, called blowdown, must be discharged from the system.
In addition to evaporation and blowdown losses, a small amount of water in the form of entrained droplets (drift) is carried away in the'ooling tower air stream. Makeup water to replace these losses in each unit is drawn from the reservoir.
During the period when the reactor is shut down for refueling and maintenance, the circulating water system is not used and makeup water is not required.
3.3.2.2 Essential S ra Pond S stem Each generating unit has two spray ponds that provide the ultimate heat sink for cooling the auxiliary systems required for reactor shutdown. The domestic water system provides makeup water to the essential spray ponds. The spray ponds are normally in use only during a reactor shutdown. Hence, makeup from the domestic water system during normal operation is only required to replace water lost by natural surface evaporation and periodic blowdown to the circulating water system. During a reactor shutdown, makeup requirements to the spray ponds are increased because of the increased evaporation to dissipate the imposed heat load and the drift associated with the operation of the ultimate heat sink sprays.
3 3 2
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PVNGS ER-OL PLANT WATER USE 3.3.2.3 Domestic and Demineralized Water S stems The onsite wells provide makeup to the domestic water system where it is processed in a reverse osmosis system to produce
. potable water. The product of the reverse osmosis system is used as makeup to the demineralized water system. Demineral-ized water is supplied to each unit.
3.3.3 PLANT WASTE WATER The major source of waste water is blowdown from the circu-lating water system of each unit,. Additional waste water is produced from sources such as: Nonradioactive demineralizer regenerants, demineralized water wastes, domestic water wastes and miscellaneous (e.g., floor drains) nonradioactive wastes. This wastewater is directed to the onsite evaporation ponds without requiring any offsite discharges.
Sanitary waste from each unit is kept separate from other plant wastes and is directed to the shared, onsite sanitary waste treatment facility. Liquid effluent from the sanitary waste treatment facility is returned to the water reclamation plant for reuse.
Treatment processes for the circulating water, domestic water, demineralized water, and condensate polishing systems, includ-ing chemical consumption, are discussed in section 3.6.
3 ~3 3
COMMON TO TYPICAL PVNGS UNIT 3 UNITS UNIT 3 UNIT 2 EVAPORATION 8
DOMESTIC UNIT 1 DRIFT DOMESTIC 9 ONSITE WATER WATER WELLS 16 18 SYSTEM OTHER CIRCULATING 17 SERVICES WATER SYSTEM MAKEUP MISC LOSSES EVAPORATION 10 AND SEEPAGE UNIT 3 12 MISC 19 UNIT 2 LOSSES z
O 0
INFLUENT UNIT 1 0O EVAPORATION FROM THE WATER 0 CO 4 91ST AVE MAKEUP WATER la SEWAGE TREATMENT RECLAMATION PLANT RESERVOIR O. (5 bh PLANT DRIFT TYPICAL ESSENTIAL PVNGS SPRAY POND 23 UNIT SYSTEM UNIT 3 15 UNIT 2 UNIT 1
'EVAPORATION DEMINERALIZED DEMINERALIZEDWATER WATER SYSTEM 24 MISC POND NONRADIOACTIVE WASTES CONDENSATE POLISHING UNIT 3 OEMINERALIZER WASTE WASTE UNIT 2 26 27 25 29 UNIT 1 28 OTHER UNIT 3 FAG I L IT I ES UNIT 2 21 SANITARY UNIT 1 SANITARY WASTE WASTE TREATMENT 22 Palo Verde Nuclear Generating Station FACILITY ER-OL PALO VERDE NUCLEAR GENERATING STATION WATER USE (Sheet 1 of 4)
Figure 3.3-1
1 tl I
A r I
I II III IV Shutdown Flow Plant Operating Maximum Flow Average Flow Minimum Flow Condi,ti,'ons Rate (gal/min)( Rate (gal/min)(b)( Rate (gal/min)(c)(f) ,'. Rate (gal/min)(d)(f)
Node II Point Description Influent from 'City of Phoenix 59,300 39,700 7,700 31,000 91st Avenue sewage treatment plant Miscellaneous !pipeline and 90 70 60 70 reclamation plant losses Water reclamation plant effluent 59,200 39i600 7g300 31,100 Reservoir evaporation and seepage 280 180 90 180 5 Reservoir discharge 59,000 39,500 7,600 30,800 Total per unit makeup water 19,700 13,200 2,500 0 (e)
Domestic water to power block 230 50 20 230 Circulating water system 18,300 12,300 2,400 evaporation I Circulating water system drift 26 24 26 10 Circulating water system blowdown 1,300 830 150 Circulating water system 587,000 587,000 587,000 circulating "flow 12 Essential spray pond system makeup 40 32 32 135 13 Essential spray pond system 40 108 evaporation 14 Essential spray pond system drift 27
a. Three units at valves wide open (VWO) and design ambient conditions, with one unit at maximum condensate polisher flow Three units at 95 percent output and annual average ambient conditions and a one month shutdown for each b.
unit for refueling.
c. Three units at auxiliary load and annual average ambient conditions.
d. Two units at VWO and annual~'verage ambient conditions with, one unit shutdown for refueling.
Shutdown unit only, refer to column II for average flows for the other units. Palo Verde Nuclear Generating Station I
e.
f. Flow rates may not balance due to round off. ER-OL PALO VERDE NUCLEAR GENERATING STATION WATER USE (Sheet 2 of 4)
Figure 3.3-1
I II III IV Plant Operating Maximum Flow Average Flow Minimum Flow Shutdown Flow Conditions Rate (gal/min) ( )(<) Rate (gal/min) (b)(f) Rate (gal/min) (c)(f) Rate (gal/min) (d)(f)
Node Point Description 15 Essential spray pond 'system 16,900 (e) circulating flow 16 Onsite wells output 1,700 790 500 li100 17 Domestic water to common 60 10 facilities 10 10 18 Per unit domestic water 270 85 52 365 (e) comsumption 19 Domestic water system waste 340 160 100 210 20 Per unit sanitary waste 2 (e) 21 Sanitary waste from common facilities 4 22 Total plant sanitary waste to 10 10 10 10 water reclamation plant II II 23 Influent to demineralized water 490 370 240 ~
300 system from domestic water system 24 Per unit demineralized water 230 120 77 50 (e) consumption 25 Demineralized water system waste 30 16 13 I
26 Condensate polishing demineralizer 160 40 0 system waste 27 Miscellaneous nonradioactive plant 22 12 12 17 wastes I 28 Total per unit wastewater flow 1,500 880 160 17 (e) without sanitary waste Palo Verde Nuclear Generating Station ER-OL PALO VERDE NUCLEAR GENERATING STATION WATER USE (Sheet 3 of 4)
Figure 3.3-1
~IM g Plant Operating I
Maximum Flow II Average Flow III Minimum Flow IV Shutdown Flow Conditions Rate (gal/min) (a)( ) Rate (gal/min) (b)(~) Rate (gal/min) ( )( ) Rate (gal/min) (d)(<)
Node Point Description 29 Total plant waste to evaporation 4,300 2i800 590 2,400 pond 30 Miscellaneous evaporative and 280 120 80 260 in-plant losses 31 Periodic essential spray pond intermittent 24 24 0 system blowdown Palo Verde Nuclear Generating Station
, ER-OL PALO VERDE NUCLEAR GENERATING STATION WATER USE (Sheet 4 of 4)
Figure 3.3"1
PVNGS ER-OL 3.4 HEAT DISSIPATION SYSTEM Information presented'in ER-CP Section 3.4 and the FES remains valid with minor changes except for the description of the cooling towers. This section summarizes and updates that information. In addition, information concerning the circular mechanical draft cooling towers utilized for PVNGS is piesented.
The system that removes and rejects waste heat from each unit during normal power generation is the circulating water system.
During a plant shutdown, waste heat is removed and rejected by one 'of two loops of the essential spray pond system. Each of the two redundant loops is capable of providing the cooling required for safe reactor shutdown, under normal or accident conditions.
A generalized flow diagram of the major heat dissipation systems is presented in figure 3.4-1 and the arrangement of the heat dissipation facilities on the site is shown in figure 3.1-4.'.4.1 CIRCUIATING WATER SYSTEM Of the total amount of thermal energy produced by each nuclear steam supply system, approximately one-third is converted into electrical energy. The unconverted thermal energy is trans-ferred via the main condenser to the circulating water system and then to the round, mechanical draft cooling towers where it is dissipated to the atmosphere. The circulating water consists of the main condenser, cooling towers, circu- 'ystem lating water pumps, a chemical injection system, and a makeup and blowdown system. The system diagram for the circulating water system is shown in figure 3.4-2.
3.4.1.1 Main Condenser The condenser removes approximately 8900 million Btu per hour at 100% power from the turbine exhaust steam. The circulating 3.4-1
PVNGS ER-OL HEAT DISSIPATION SYSTEM water flow through the main condenser is 560,000 gallons per minute at 87.3F design with a temperature rise of 32.1F; 3.4.1.2 Circulatin Water Pum s Circulating water is pumped through the main condenser enser b y four 25% capacity, vertical, wet-pit pumps with a capacity of approximately 140,000- gallons per minute each at approximately 103 feet total dynamic head (tdh).
3.4.1.3 Plant Coolin Water Pum s Plant cooling water is pumped through the turbine, the condenser vacuum pump seal coolers, and the nuclear cooling water system heat exchangers by two 100% capacity, vertical, wet-pit pumps with a capacity of approximately 29,000 gallons per minute each at approximately 110 feet total dynamic head. ,The plant cooling water system removes approximately 191 million Btu/h from the two closed-loop cooling water systems and about 4 million Btu/h from the condenser vacuum pump seal water cooler with a tempera-ture rise of approximately 15F.
3.4.1.4 Coolin Towers The primary heat dissipation system for PVNGS uses round mechani-cal draft cooling towers. Table 3.4-1 presents the design characteristics of the cooling tower system. The cooling towers dissipate the circulating water system and plant cooling water system heat loads, a design total of approximately 9250 million Btu per hour by cooling approximately 590,000 gal-lons per minute of water 32F. At the design wet bulb tempera-ture of 75F, the cooling towers cool the circulating water from 118.8F to 87.3F. Figures 3.4-3 and 3.4-4 present curves of design cooling tower performance, cold water temperature versus wet bulb temperature. Figures 3.4-5 and 3.4-6 present evapor-ation curves. Design cooling tower discharge air tempera-ture is presented in figure 3.4-7.
3.4-2
PVNGS ER-OL HEAT DISSIPATION SYSTEM Table 3.4-1 DESIGN CHARACTERISTICS OF ROUND MECHANICAL DRAFT COOLING TOWER SYSTEM PVNGS nominal net output, MWe 1270 Tower heat rejection rate, Btu/h 9.25 x 10 Circulating water flow rate, gal/min 587,000 Air flow rate, ft /min 64.4 x 10 Exit air temperature, F 104 Exit air relative humidity, percent 90 Dry bulb temperature, F 116 Wet bulb temperature, F 75 Circulating water,hot water temperature, F 118.8 Circulating water cold water temperature, F 87.3 Circulating water approach to wet bulb 12.3 temperature, F Cycles of concentration of circulating water 15 Drift loss, percent of circulating water flow 0.0044 rate Number of towers 3 Number of cells per tower 1 Base diameter of tower, ft 303 Exit air discharge height, ft 64 Number of fans, total 48 Horsepower per fan, hp 200 Exit diameter of fan, ft 36
a. All data on a per unit basis at design ambient conditions.
3.4-3
PVNGS ER-OL HEAT DISSIPATION SYSTEM There are three cooling towers per unit. Each tower is approxi-mately.303 feet in base diameter and 64 feet high with 16 fans as shown in figure 3.4-8.
3.4.1.5 Chemical In'ection S stem The chemical injection system adds chlorine, sulfuric acid, a foam control agent, and a dispersant to the circulating water system. Chlorine is added as sodium hypochlorite to control biological growth, sulfuric acid is added to reduce pH and control corrosion and scaling from calcium carbonate, and the dispersant is added to inhibit scaling of the heat exchanger surfaces. This system is described in more detail in sec-tion 3.6.
3.4.1.6 Makeu Water S stem Makeup water is treated in the onsite water reclamation plant prior to use. Refer to section 3.6 for a discussion of the water reclamation plant. Makeup to the circulating water system as shown in table 3.4-1 i's required as a result of three types of water losses: cooling tower evaporation, blowdo'wn, and drift.
Table 3.4-2 presents a summary of the expected average per unit monthly cooling tower evaporation, drift, and total consumptive loss. Table 3.4-3 shows the cumulative distribution of the daily wet bulb temperatures compiled on month-by-month basis.
3.4.1.7 Blowdown S stem Blowdown from the circulating water system is directed to the evaporation ponds. As noted in section 3.6, the water quality of cooling tower blowdown is significantly lower than that of makeup due to the 15 cycles of concentration in the circulating water.
3.4-4
PVNGS ER-OL" HEAT DISSIPATION SYSTEM Table 3.4-2 ANTICIPATED MONTHLY EVAPORATION VARIATION (1 of 2)
(EACH UNIT)
Circulating Water emp RH Evaporation Blowdown Makeup Temperature Month (F) (%) (GPM) (GPM) (GPM) (F)
January 50 51 3820 247 4090 55 February 53 35 4280 280 4590. 54 March 60 43 4540 298 4860 60 April 63 28 5050 335 5410 59 May 77 21 6130 412 6570 64 June 88 17 6700 474 7200 68 July 90 35 6350 427 6800 76 August 89 29 6540 441 7010. 73 Septembe 84 30 6230 419 6680 71 October 72 35 5400 360 5790 65 November 57 47 4290 280 4600 58 December 49 47 3820 247 4090 54 50 HEAT LOAD January 50 51 6590 445 7060 62 February 53 35 7010 475 7510 61 March 60 43 7370 501- 7900 66 April 63 28 7850 535 8410 65 May 77 21 9030 619 9680 70 June 88 17 9970 686 1068'0 73 July 90 35 9480 651 10160 79 August 89 29 9620 661 10310 77 September 84 30 9260 635 9920 75 October 72 35 8330 569 8930 70 November 57 47 7110 482 7620 65 December 49 47 6570 443 7040 61 3.4-5
PVNGS ER-OL HEAT DISSIPATION SYSTEM Table 3.4-2 ANTICIPATED MONTHLY EVAPORATION VARIATION (2 of 2)
(EACH UNIT)
Circulating Water emp RH Evaporation Blowdown Makeup, Temperature Month (F) (%) (GPM) (GPM) (GPM) (F) 75 HEAT LOAD January 50 51 9420 647 10090 67 February 53 35 9820 676 10520 67 March 60 43 10260 707 10990 70 April 63 28 10710 739 11480 70 May 77 21 11960 828 12810 74 June 88 17 11950 899 12880 77 July 90 35 12580 873, 13480 82 August 89 29 12680 880 13590 80 Septembe 84 30 12280 852 13160 78 October 72 35 11280 780 12090 74 November 57 47 9990 687 10700 70 December 49 47 9380 644 10050 66 100'EAT LOAD January 50 51 12090 838 12950 71 February 53 35 12490 866 . 13380 70 March 60 43 12980 901 13910 74 April 63 28 13410 932 14370 73 May 77 21 1025 15760 77 14710'5730 June 88 17 1098 16850 79 July 90 35 15450 1078 16550 84 August 89 29 15510 1082 16620 82 September 84 30 15100 1053 16180 80 October 72 35 14050 978 15050 77 November 57 47 12700 881 13610 73 December 49 47 12040 835 12900 70
3. 4-6
Table 3.4-3 DAILY WET-BULB CUMULATIVE DISTRIBUTION CHART (1 OF 4)
CUKCKATZVB TOTALS 1948-1973 (BY IANYB)
Anblcut Wet Bulb Tenp (F Feb Apr Jul Aug Nov 1 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 "0 4 0 0 0 0 0 0 0 5 0 0 0 0 0 0 0 6 0 0 0 0 0 0 0 7 0 0 0 0 0 0 0 8 0 0 0 0 0 0 0 9 0 0 0 0 0 0 0 10 0 0 0 0 0 0 0 11 0 0 0 0 0 0 0 12 0 0 0 0 0 0 0 13 0 0 0 0 0 0 0 14 0 0 0 0 0 0 0 15 0 0 0 0 0 0 0 16 1 0 0 0 0 0 0 17 2 0 0 0 0 0 0 18 6 0 0 .0 0 0 0 19 10 0 0 0 0 0 0 20 37 0 0 0 0 0 0 21 36 1 0 0 0 0 0 22 35 6 0 0 0 0 3 23 60 5 0 0 0 0 13 24 65 16 0 0 0 3 21 25 80 41 3 0 0 6 35 U 26 93 42 9 0 0 8 49 H 27 128 79 2 0 0 8 63 28 167 82 14 0 0 ll 107 H H
0 R
Table 3.4-3 DAILY WET-BULB CUMULATIVE DISTRIBUTION CHART (2 OF 4)
C(BO(0(ATIVB TOTA18 1948-1973 (BY )((NTB)
Ambieut met Bulb Temp (8) Feb Apr Ju) Aug Sep Nov 29 257 111 2l 0 0 0 0 0 0 3 28 131 30 266 155 45 0 0 0 0 0 0 0 39 203 31 332 165 48 0 0 0 0 0 0 0 68 241 32 399 212 81 0 0 0 0 0 0 3 71 279 33 424 259 89 3 0 0 0 0 0 0 89 392 3l 506 321 160 1l 3 0 0 0 0 6 139 512 35 553 36l 202 32 6 0 0 0 0 11 204 584 36 659 451 220 46 3 0 0 0 0 14 280 636 37 692 446 3I2 72 8 0 0 0 0 16 241 789 38 789 545 384 111 9 0 0 0 0 30 353 904 39 842 617 473 152 27 0 0 0 0 50 l33 900 40 862 758 541 236, 25 0 0 0 0 69 555 952 41 924 851 709 265 75 2 0 0 0 76 594 896 (a) 42 891 8I9 767 366 81 2 0 0 0 130 715 983 sD 43 967 864 853 ~ 32 114 6 0 0 0 144 768 1039 I 44 980 909 977 566 146 10 0 0 0 227 821 10I9 CO 45 1017 886 100I 663 237 30 0 0 7 279 868 973 46 1003 881 1211 797 371 56 0 0 11 419 1001 956 47 1023 957 1171 843 416 87 0 0 2l 1071 937 48 922 931 1187 973 548 150 0 0 34 539 1033 908 49 847 896 1138 1159 684 132 0 1 57 590 1070 878 50 733 927 1090 1084 745 231 1 6 102 615 992 781 51 675 754 1079 1157 818 330 5 7 131 71$ 9I7 736 52 606 720 1048 106I 1051 377 8 8 150 837 880 647 53 487 664 1065 1232 1109 l76 29 8 213 876 913 512 Sl 880 3408 1278 7450 1135 12,868 540 16,830 39 19 '95 13 19 '90 282 17,991 957 13g248 866 4,511 376 1143 75t Circ U 381 968 491 1875 (23.9) 378 (23.1) 1039 (16.4) 831 (5.8) 311 (1.4) 'uater Temp H
55 200 (1.2) 447 (1 6) 763 (4.2) 1140 (9.6) 1196 (16.0) 631 (21.6) 59 (23.9) 33 56 131 348 S96 1074 1248 757 82 360 1000 772 191 H
P H
0
Table 3.4-3 DAILY WET-BULB CUMULATIVE DISTRIBUTION CHART (3 OF 4)
CUK OLATIVB TOTALS 1948 1973 {BY NONTN)
Anbient Wet Bulb Tenp {t) Jan peb Apu Jul Aug Sep Nov 57 89 211 411 1041 1237 860 108 62 495 1126 691 102 58 54 149 320 909 1340 882 122 100 550 1122 491 71 59 59 112 196 686 1262 1056 163 116 696 1245 325 52 60 38 61 110 529 1286 1052 194 184 765 1124 220 19 61 13 32 42 ioo 1088 1122 238 211 833 1057 133 16 62 3 21 28 218 971 1225 250 284 965 913 92 2 63 0 2 2 125 705 1238 381 291 1078 819 46 3 64 0 1 0 41 542 1293 474 460 1183 190 20 0 65 0 0 0 7 405 1171 559 549 1156 589 8 0 66 0 0 0 2 228 1219 754 658 1182 443 3 0 6'1 0 0 0 0 120 958 1034 867 1230 334 0 0 68 0 0 0 0 55 803 1197 1168 1334 288 1 0 69 0 0 0 0 38 661 1572 1399 1220 193 0 0 70 0 0 0 0 9 526 2090 1967 1185 96 0 0 11 0 0 0 0 2 313 2298 2272 1067 51 0 0 72 0 0 0 0 0 248 2569 2643 841 27 0 0 73 0 0 0 0 1 126 2063 2171 590 15 0 0 74 0 0 0 0 0 50 1647 1193 348 5 0 0 75 0 0 0 0 0 23 873 1155 185 8 0 0 76 0 0 0 0 0 12 371 577 61 1 0 0 77 0 0 0 0 0 1 126 197 7 0 0 0 78 0 0 0 0 0 0 20 58 0 0 0 0 79 0 0 0 0 0 1 5 15 0 0 0 0 80 0 0 0 0 0 0 2 1 0 0 0 0 81 0 0 0 0 0 1 3 0 0 0 0 0 U 82 0 0 0 0 0 1 2 1 0 0 0 0 H 0 0 0 0 0 0 1 0 0 0 0 Ol 83 0 Ul 84 0 0 0 0 0 0 0 0 0 0 0 0 H
H-0
Table 3.4-3 DAILY WET-BULB CUMULATIVE DISTRIBUTION CHART (4 OF 4)
CVNNVIATIVETOTALS 1948-1973 (BY MONTH)
A&blent 4(et SUlb Tertp (F) J&U Feb Apr JUl AUg Sep Nov 85 0 86 0 87 0 88 0 89 0 90 0 91 0 92 0 93 0 9l 0 95 0 96 0 97 0 98 0 99 0 100 0 Tet&1 19,3ll 17 ~ 640 19,344 18,717 19 ~ 344 18,719 19,338 19 ~ 320 18y720 19,3l4 .18,720 19,252 08/lC) 744 681.6 7ll 720 744 720 74l 7ll 720 74l 720 744 U
H H
0
PVNGS ER-OL HEAT DISSIPATION SYSTEM 3.4.2 OTHER COOLING WATER SYSTEMS Other major cooling water systems in PVNgS include
~ Turbine cooling water system e Nuclear cooling water system e Essential spray pond system e Essential cooling water system.
3.4.2.1 Turbine Coolin Water S stem The turbine cooling water system is a closed-loop system that removes heat from turbine plant systems such as the main turbine lube oil system, gland steam packing exhauster system, generator hydrogen cooling system, stator cooling system, exciter air coolers, and other nonnuclear related systems. Approximately 80 million Btu per hour are rejected from this system to the plant cooling water system via either one of the two redundant turbine cooling water heat exchangers.
3.4.2.2 Nuclear Coolin Water S stem The nuclear cooling water system is a closed-loop system that removes heat from normally operating, nuclear, nonsafety-related s
systems. Approximately 110 million Btu per hour are rejected from this system to the plant cooling water system via either one of the two redundant nuclear cooling water heat exchangers.
3.4.2. 3 Essential S ra Pond S stem The essential spray pond system, in conjunction with the essential cooling water system provides the cooling during a reactor shutdown. This system consists of two 100% redundant loops. The major equipment in each loop is one essential spray pond having a sprayed area of approximately 59,000 ft ,
2 one essential spray pond pump, and one essential cooling water heat exchanger. The system flow diagram is given in figure 3.4-9.
3.4-11
PVNGS ER-OL HEAT DISSIPATION SYSTEM The two loops of the essential spray pond system are not used during normal power generation and are in operation only during reactor shutdown or diesel generator operation. Since each loop is completely redundant, only one loop is required to operate during normal reactor shutdown. During reactor shutdown the flow in each loop of the esser1tial spray pond system is approximately 16,900 gallons per minute.
The spray ponds are rectangular, reinforced concrete, Seismic Category I basins. Each spray pond is provided with distribu-tion piping and four spray headers, each header having 80 hollow cone type. spray nozzles.
The pump structures are rectangular reinforced concrete sumps, each one. an integral part of its respective pond. They provide a low point for the spray pond basin and serve as a wet pit intake for the pump. Each spray pond is 345 feet long, 172 feet wide and 15.5 feet deep. with 2 feet of freeboard and 6
a capacity of 6 x 10 gallons.
Each spray pond pump has a capacity of 16,900 gallons per minute. The water quality is given in table 3.4-4.
3.4.2.4 Essential Coolin Water S stem The essential cooling water system (ECWS) is the closed-loop system that removes heat from the safety related auxiliary systems and rejects it to the essential spray pond system. The system consists of two separate, 100% capacity loops. Heat is rejected from each loop of this system to its respective loop in the essential spray pond system via the essential cooling water heat exchanger.
3.4-12
PVNGS ER-OL HEAT DISSIPATION SYSTEM Table 3.4-4 ESSENTIAL SPRAY POND SYSTEM; WATER QUALITY SPECIFICATION Normal Maximum Following Parameter Operation 30 Days w/o Makeup pH at 77F 7.8 7.5 Conductivity, (pmhos/cm) 650 4545 TDS (ppm) 357 2500 Chlorides, as CaCO> (ppm) 99 693 Fluorides, as CaCO> (ppm) 3 21 The ECWS is normally in service only during reactor shutdown or diesel generator operation. Since each loop is 100% redundant, only one loop is required to operate during a reactor shutdown.
Under emergency conditions, however, both loops are activated along with both loops of the essential spray pond system to remove heat.
3.4-13
COMMON PVNGS FACILITIES I I
I I
BLOWDOWN I
PLANT COOLING WATER SYSTEM I
I I
I I I COOLING TOWERS I MAIN tTYPICAL OF THREE)
I PVNGS CONDENSER EVAPORATION I PONDS I
I TURBINE NUCLEAR CONDENSER COOLING COOLING VACUUMPUMP I CIRCULATING TYP WATER SYSTEM WATER SYSTEM SEAL COOLERS WATER SYSTEM OF 2 I
PUMPS TYP I
OF 4 I PUMPS WAST EWATE R FROM PVNGS PHOENIX WATER 91ST AVE R EC LAMATI 0 N SEWAGE PLANT I TREATMENT ESSENTIAL SPRAY POND SYSTEM A I
)LANT I
I I ESSENTIAL I SPRAY DOMESTIC POND I WATER A I SYSTEM ESSENTIAL I COOLING WATER SYSTEM A I
I I
I ESSENTIAL SPRAY POND SYSTEM 8 I
I I.
I ESSENTIAL SPRAY PVNGS POND RESERVOIR I B
I ESSENTIAL TYP OF I COOLING WATER 4 PUMPS I SYSTEM B I
I COMMON PVNGS FACILITIES Palo Verde Nuclear Generating Station ER-OL GENERALIZED HEAT DISSIPATION SYSTEM FLOW DIAGRAM Figure 3.4-1
l 8LOMDONM TOc PLANT CODLING BF-001 MATER RETVRM -001 EyAPORAT D)N POIID (0-6) (C 7)
I C~IN~T~R
~ff FROM POLISHING DEN INERALIZER -002 FROM 10 SVHP CDF-002 CONDENSATE
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( E-5)
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FOAM CONTROL AGENT INJECTION CIF 002 HAIN COMDENSERS PUMPS ( F-I ) NMP I ACID INJECTION CIF 002 PUMPS (F-4) f THC DATA SHOCCN Oh THIS LOW OIAORAIC c~cc aTIN0 cccc ARC fOR DCSZCC TLRCOSCSOALT, ARD RMILC CCSCC DL AS CAICDCS M OCT RATCOh DO hOT RCRRCSCRT CXAOT OR CAJARAh TCCD OTCRATfcOCOhDCTCOh5 HODE PARAHETER
+5 '6 +7 +8 +9 +IO +II FLOM (GPH) 140,000 280.000 280,000 280 000 280c000 560c000 F 29 000 F lc300 587000 196 400 20 000 DESIGN TEHPERATVRE (RF) 87 87 98 109 120 120 102 120 120 120 85 PRESSURE PSIG 80 80 80 80 80 80 80 80 80 80 FLOM (GPH) 140c000 280 000 280.000 280 F 000 280c000 560c000 (R F F 29 000 F lc000 588,000 196,000 16 000 Palo Verrle Nuclear Generating Station NORHAL TEHPERATVRE 75 75 86 97 108 108 90 108 108 108 75 PRESSURE PSIO 45 45 40 35 30 30 30 30 30 30 ER-OL BASIC FLOW DIAGRAM CIRCULATING WATER SYSTEM Figure 3.4-2
100 95 90 I
I-tL 85 O
0 80 75 60 65 '0 75 80 85 WET BULB TEMPERATURE ( F)
Palo Verde Nuclear Generating Station y/.r, ER-OL DESIGN RANGE COOLING TOWER PERFORMANCE CURVE 100% FLOW Figure 3.4-3
1 95 90 D 85 I
K I
CC 80 0
0 75 70 60 65 70 75 80 85 WET BULB TEMPERATURE { F)
Palo Verdh Nuclear Generating Station ER-OL DESIGN RANGE COOLING TOWER PERFORMANCE CURVE 90% FLOW Figure 3.4-4
R 65 25% RH 60 50% RH o
X 50
)~
LU 100% RH U
45 40 35 30 40 50 ~ 60 70 80 90 WET BULB TEMPERATURE ( F)
Palo Verde Nuclear Generating Station ER-OL COOLING TOWER EVAPORATION CURVE 100% FLOW Figure 3.4-5
4 iv
60 25'No RH 50 50% RH O
o X
45 100% RH U
40 35 30 30 40 50 60 70 80 90 WET BULB TEMPERATURE ( F)
Palo Verde Nuclear Generating Station ER-OL COOLING TOWER EVAPORATION CURVE 90% FZDW Figure 3.4-6
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Palo Verde Nuclear Generating Station SAFSKURK ttSICI 40 21 31 21 $1 21 $1 '21 $1 21 1$ Arts 10 Atro Io ER-OL BASIC FLOW DIAGRAM ESSENTIAL SPRAY POND SYSTEM Figure 3.4-9
f TOWER- REF. g K EQUIPMENT ACCESS RAMP EQUIPMENT REMOVAL HATCH MECHANICAL REMOVAL EQUIPMENT STORAGE CABINET g STAIRWAY 8 ACCESS WALKWAY
~ PRECAST DISTRIBUTION BASIN
~ ~.'
OUTLET PRECAST DISTRIBUTION FLUME
-PRECAST LOUVERS IO METER GRP FAN-.
( I6 FANS', REQ'D)
I PERIMETER WINDWALL t
l
'PRECAST FAN DECK FLUME CLEANOUT IPLUGS PLAN VIEW QAQeQOQE PLAN SHOWN FOR TOWER I-CWN-W02,2-CWN-W02,3.CWN.W02 303-0 DIAMETER OUT TO OUT OF TOWER hC O
LIJ O
a)( Palo Verde Nuclear Generating Station
>i OI ER-OL 5!
Si TYPICAL COOLING TOWER ELEVATION QQF Figure 3 '-8
110
~OS qP pS CC I- 70 K
I 60 U
K xU 50 K
0I-10 10 20 30 40 50 60 70 TOWER INLET WET BULB TEMPERATURE ( F)
Palo Verde Nuclear Generating Station ER-OL COOLING TOWER DISCHARGE AIR TEMPERATURE Figure 3.4-7
PVNGS ER>>OL 3.5 RADWASTE SYSTEMS AND SOURCE TERM Information presented in ER-CP Section 3.5 and the FES has been revised and updated to reflect changes in the radwaste system due to:
~ General system evolution
~ Implementation of a dry cleaning laundry facility instead of a wet, laundry
~ Use of ANSI-N237 source strengths instead of 0.25%
failed fuel values as the expected case Issuance and implementation of NUREG-0017 Implementation\ of a cement binder solid radwaste system Minor changes in other PVNGS systems and their opera-tions, which determine the quantity and activity of wastes processed by the radwaste systems.
The radwaste systems are designed to safely collect, process, and dispose of potentially radioactive liquid, gaseous, and solid wastes. The radwaste systems include the following:
e Liquid Radwaste System (LRS) o Gaseous Radwaste System (GRS)
~ Solid Radwaste System (SRS)
A revised description of the radwaste system is presented in this section.
Radwaste systems are not shared between PVNGS units. The PVNGS radwaste systems provide processing for fission products and mobile neutron activation products (crud) produced in the primary coolant as a result of reactor operation. Although other systems will process/accumulate radioactivity during the course of operation, these systems will eventually transfer their radioactivity to the radwaste systems. Thus, the final cleanup and disposal of radioactivity is through the LRS, GRS, and SRS.
3.5-1
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM The radwaste systems are designed to limit the release of activity from PVNGS to ensure that releases as well as indi-vidual and population exposures to restricted and unrestricted areas are as low as is reasonably achievable, in conformance with the guidelines of 10CFR20 and 10CFR50 Appendix I.
The LRS processes radioactive and potentially radioactive liquid wastes. It recovers demineralized water for recycle and concentrates radioactive or chemical liquid wastes for processing by the SRS. There are no radioactive liquid releases from PVNGS.
The GRS collects and processes radioactive and potentially radioactive gaseous wastes prior to release from the plant.
High activity waste gas and low activity aerated waste gas are processed separately. The high activity waste gas is collected and stored to permit the decay of short-lived radionuclides prior to release. The low activity gaseous wastes from the containment, auxiliary, and radwaste buildings are sent to ventilation exhaust systems for processing through charcoal and particulate filters, as appropriate, prior to release via the plant stack. Low activity gaseous waste from the condenser air removal system can be processed through charcoal and particu-late filters prior to release. In addition, should the level of airborne activity in the fuel building require it, its gaseous waste may also be processed through charcoal and particulate filters prior to release.
The SRS solidifies and encapsulates spent resins, evaporator concentrates, laundry solutions, and spent filter cartridges.
The SRS also compacts and packages low activity compressible solid wastes such as rags, paper, or plastics. On-site storage is provided for solid waste which allows decay prior to ship-ment. from the site.
3. 5-2
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM The process and effluent radiation monitors, detect and record radioactivity in selected plant processes and in potentially radioactive gaseous effluents to ensure compliance with applicable regulations.
3.5.1 SOURCE TERM Radioactivity sent to the radwaste systems during normal and anticipated operational occurrences include fission products, and mobile neutron activation products. Expected normal activities in the primary coolant are based on no gas stripping and on the ANSI-N237 model described in FSAR Section 11.1.
Models used to determine tritium and nitrogen-16 activities are described in FSAR Section 11.1. Expected primary coolant activities are presented in table 3.5-1.
Other systems will process and/or accumulate radioactivity during operation. The secondary system will become slightly radioactive in the event of steam generator tube leaks. The chemical and volume control system (CVCS) lets down primary coolant to control water chemistry. The spent fuel pool cooling and cleanup system will process the primary coolant during refueling as well as the spent fuel pool water during operation. Radioactive samples and equipment drains and leak-ages are sent to the LRS which also receives radioactive ion exchanger regenerant wastes from the secondary system. The GRS receives radioactive waste gas from processing equipment, of other systems. The SRS receives concentrated liquid waste and spent resins from radioactive systems.
3.5.1.1 Tritium Source Terms and Releases The tritium concentrations in the plant are dependent on the production rate in the reactor coolant system, the losses due to radioactive decay, discharges from the plant, leakage, and
3. 5-3
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-1 EXPECTED PRIMARY COOLANT ACTIVITIES (pCi/g)
Radionuclide Activity Radionuclide Activity Kr-83M 2. 1 (-02) Sr-89 3.5(-04)
Kr-85M Kr-85
1. 1 (-01) Sr-90 l. 0 (-05)
(-04)
1. 5 (-01) Sr-91 6. 5 Kr-87 6. 0 (-02) Zr-95 6. 0 (-05)
Kr-88 2. 0 (-01) Nb-95 5.0(-05)
Kr-89 5. 0 (-03) Tc-99M 4.8(-02)
Xe-131M 1. 1 (-01) Ru-103 4.5(-05)
Xe-133M 2. 0 (-01) Ru-106 1. 0 (-05)
Xe-133 1. 8 (+01) Rh-103M 4. 5 (-05)
Xe-135M 1. 3 (-02) Rjl-106 1. 0 (-05)
Xe-135 3. 5 (-01) Te-125M 2. 9 (-05)
Xe-137 9. 0 (-03) .Te-127M 2. 8 (-04)
Xe-138 4. 4 (-02) Te-127 8. 5 (-04)
Br-83 4. 8 (-03) Te-129M 1.4(-03)
Br-84 2. 6 (-03) Te-129 1. 6 (-03)
Br-85 3. 0 (-04) Te-131M 2. 5 (-03)
I-130 2. 1 (-03) Te-131 1. 1 (-03)
I-131 2. 7 (-01) Te-132 2. 7 (-02)
I-132 1. 0 (-01) Ba-137M 1. 6 (-02)
I-133 3. 8 (-01) Ba-140 2. 2 (-04)
I-134 4. 7 (-02) La-140 1. 5 (-04)
I-135 1. 9 (-01) Ce-141 7. 0 (-05)
Rb-86 8. 5 (-05) Ce-143 4. 0 (-05)
Rb-88 2. 0 (-01) Ce-144 3. 3 (-05)
Cs-134 2. 5 (-02) Pr-143 5. 0 (-05)
Cs-136 1. 3 (-02) Pr-144 3. 3 (-05)
Cs-137 1. 8 (-02) Np-239 1. 2 (-03)
N-16 1. 4 (+02) Cr-51 1. 9 (-03)
H-3 5. 4 (-01) Mn-54 3.1(-04)
Y-90 Y-91M
l. 2 (-06)
3. 6 (-04)
Fe-55 Fe-59 1.6(-03) 1.0(-03)
Y-91 6. 4 (-05) Co-58 1. 6 (-02)
Y-93 3. 4 (-05) Co-60 2. 0 (-03)
Mo-99 8. 2 (-02) 3.5-4
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM evaporation,. and the .transfer of water between plant systems.
The detailed calculational model used to determine tritium activities in the plant is presented in FSAR Section 11.1.3.
The tritium flow balance diagram used to develop the calcula-tional model is shown on figure 3.5-1. Table 3.5-2 lists the expected. annual tritium releases by pathway and release point.
Tritiated liquid will not be released from PVNGS.
3.5.1.2 Secondar S stem Sources The secondary system will become contaminated if steam genera-tor tube leaks occur. Any such primary-to-secondary leakage is expected to be less than 100 lb/day. Equilibrium expected secondary system activities shown in table 3.5-3 have been determined using the calculational model presented in FSAR Section 11.1.8. The flow model used to determine the equilib-rium activities is presented in FSAR Section 11.1.8.
3.5.1'.3 Fuel Pool Source Terms The primary source of activity in the refueling and spent fuel pools is demineralized and diluted primary coolant. During refueling, the primary coolant and the water in the refueling water tank are mixed. This diluted radioactive water then mixes with the water in the spent fuel pool through the fuel transfer tube.
Activity in the refueling pool is at a maximum at the start of refueling and the activity in the spent fuel pool reaches a maximum 5 days into the refueling operation. These expected peak activities are listed in table.3.5-4. The detailed bases for these values are presented in FSAR Section 11.1.4.
Activity is released from the pools by evaporation. The only significant source of airborne activity above the pools is tritiated water vapor. Other radionuclides are removed by decay and operation of the fuel pool cooling and cleanup 3.5-5
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-2 EXPECTED ANNUAL TRITIUM RELEASES (Curies per year per unit)
Activity Release Point and Pathway Released PLANT VENT Containment Normal Operation 1.7 Refueling 36 Auxiliary/Radwaste Building Exhaust 4.2 Boric Acid Concentrator Distillate Vapor 333 TOTAL 375 FUEL BUILDING 666 TURBINE BUILDING 7.2 TOTAL ANNUAL RELEASE 1048 system. Tritium evolution from the refueling and spent fuel pools during refueling and normal operation is discussed in FSAR Section 11.1.4.
3.5.1.4 Leaka e Sources Systems containing radioactive liquids or gases are potential sources of leakage to the plant buildings and ultimately to the environment through the various ventilation systems.
Liquid leakage is generated from such potential sources as pump seals and valve packings. Although a small fraction of the activity in the leakage will evolve and become a source of airborne activity, the majority is collected in radioactive 3.5-6
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-3 EXPECTED SECONDARY SYSTEM ACTIVITIES (pCi/g) (Sheet 1 of 2)
Steam Generator Radi onucli de Liquid Main Steam Condensate Kr-83M 9. 5 (-09) 9. 5 (-09) 2-2 (-09)
Kr-85M 5. 0 (-08) 5. 0 (-08) 1. 2 (-08)
Kr-85 7.0(-08) 7. 0 (-08) 1. 7 (-08)
Kr-87 2.7 (-08) 2. 7 (-08) 6. 1 (-09)
Kr-88 9. 1 (-08) 9. 1 (-08) 2. 1 (-08)
Kr-89 1. 3 (-09) 1. 3 (-09) 1. 7 (-10)
Xe-131M 5. 1(-08) 5. 1(-08) 1 2 (-08)
l. 0 (-07)
~
Xe-133M 1. 0 (-07) 2 4 (-08)
~
Xe-133 8. 4 (-06) 8. 4 (-06) 2. 0 (-06)
Xe-135M 5. 1 (-09) 5. 1 (-09) 1. 0 (-'09)
Xe-135 1. 6 (-07) 1. 6 (-07) 3 8 (-08)
~
Xe-137 2. 6 (-09) 2. 6 (-09) 3. 4 (-10)
Xe-138 1.7(-08) 1. 7 (-08) 3. 3 (-09)
Br-83 1. 5 (-07) 1. 5 (-09) 1. 4 (-09)
Br-84 2. 2 (-08) 2. 2 (-10) 2. 0 (-10)
Br-85 2. 5 (-10) 2.5(-12) 1. 2 (-12)
I-130 1.6(-07) 1. 6 (-09) 1. 6 (-09)
I-131 3. 1 (-05) 3. 1(-07) 3. 1 (-07)
I-132 3. 0 (-06) 3. 0 (-08) 2. 9 (-08)
I-133 3. 4 (-05) 3. 4 (-07) 3. 4 {-07)
I-134 6. 3 (-07) 6. 3 (-09) 5. 9 (-09)
I-135 1.1(-05) 1.1(-07) 1. 1 {-07)
Rb-86 1.0(-08) 1. 0 (-11) 1. 0 (-11)
Rb-88 1.0(-06) 1. 0 (-09) 8. 8 (-10)
Cs-134 3.0(-06) 3. 0 (-09) 3. 1 (-09)
Cs-136 1. 5 (-06) 1. 5 (-09) l. 6 (-09)
Cs-137 2. 2 (-06) 2. 2 (-09) 2. 2 (-09)
N-16 4. 5 (-06) 4. 5 (-06) 4. 2 (-08)
H-3 1.3(-03) 1. 3 (-03) 1. 3 (-03)
Y-90 1. 3 (-10) 1.3(-13) 1. 3 (-13)
Y-91M 4. 8 (-09) 4. 8 (-12) 4. 5 (-12)
Y-91 7. 6 (-09) 7. 6 (-12) 7. 6 (-12)
Y-93 2. 4 (-09) 2. 4 (-12) 2. 4 (-12)
Mo-99 9. 1 (-06) 9. 1 (-09) 9.1(-09)
Sr-89 4.2(-08) 4. 2 (-11) 4. 2 (-11)
Sr-90 1. 2 (-09) 1. 2 (-12) 1.2(-12)
Sr-91 4. 6 (-08) 4. 6 (-11) 4. 6 (-11)
Zr-95 7. 2 (-09) 7. 2 (-12) 7. 2 (-12)
Nb-95 5. 9 (-09) 5. 9 (-12) 5. 9 (-12) 3.5-7
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-3 EXPECTED SECONDARY SYSTEM ACTIVITIES (pCi/g) (Sheet 2 of 2)
Steam Generator Radionuclide Liquid Main Steam Condensate Tc-99M 2. 7 (-06) 2. 7 (-09) 2. 7 (-09)
RQ-103 5'. 3 (-09) 5. 3 (-12) 5. 4 (-12')
Ru-106 1. 2 (-09) 1. 2 (-12) 1. 2 (-12)
Rh-103M 6. 7 (-10) 6. 7 (-13) 6. 4 (-13)
Rh-106 1. 5 (-12) 1.5(-15) 2. 3 (-16)
Te-125M 3. 5 (-09) 3. 5 (-12) 3. 5 (-12)
Te-127M 3. 3 (-08) 3. 3 (-11) 3. 3 (-11)
Te-127 6. 0 (-08) 6. 0 (-11) 5. 9 (-11)
Te-129M 1. 7 (-07) 1. 7 (-10) 1.7(-10)
Te-129 2. 8 (-08) 2. 8 (-11) 2.7(-11)
Te-131M 2.5(-07) 2. 5 (-10) 2. 4 (-10)
Te-131 7. 7 (-09) 7. 7 (-12) 6. 9 (-12)
Te-132 3. 0 (-06) 3. 0 (-09) 3. 0 (-09)
Ba-137M 1. 2 (-08) 1. 2 (-11) 5. 7 (-12)
Ba-140 2. 6 (-08) 2. 6 (-11) 2. 6 (-11)
La-140 1.5(-08) 1.'5 (-11) 1. 5 (-11)
Ce-141 8. 3 (-09) 8. 3 (-12) 8. 3 (-12)
Ce-143 4. 0 (-09) 4.0(-12) 4. 0 (-12)
Ce-144 3. 9 (-09) 3. 9 (-12) 3. 9 (-12)
Pr-143 5. 9 (-09) 5. 9 (-12) 5. 9 (-12)
Pr-144 1. 6 (-10) 1. 6 (-13) 1. 4 (-13)
Np-239 1. 3 (-07) 1. 3 (-10) 1. 3 (-10)
Cr-51 2. 3 (-07) 2. 3 (-10) 2. 3 (-10)
Mn-54 3. 7 (-08) 3. 7 (-.11) 3. 7 (-11)
Fe-55 1. 9 (-07) 1. 9 (-10) 1. 9 (-10)
Fe-59 1.2(-07) 1. 2 (-10) 1. 2 (-10)
Co-58 1.9(-06) 1. 9 (-09) 1. 9 (-09)
Co-60 2. 4 (-07) 2. 4 (-10) 2.4(-10) 3.5-8
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-4 REFUELING ACTIVITIES (Sheet 1 of 2)
Expected Peak Refueling Activities (pCi/g)
Radionuclide Refueling Pool Spent Fuel Pool Kr-83M 3.4(-12) 0.0 Kr-85M 2.4 (-7) 0.0 Kr-85 2. 2 (-4) 3. 6 (-5)
Kr-87 4. 1 (-15) 0.0 Kr-88 8. 1(-9) 0.0 Kr-89 0.0 0.0 Xe-131M 1. 5 (-4) 1. 8 (-5)
Xe-133M 2. 1 (-4) 6.9 (-6)
Xe-133 2. 2 {-2) 1. 9 (-3)
Xe-135M 0.0 0.0 Xe-135 2. 6 (-5) 4.4(-lo)
Xe-137 0.0 0.0 Xe-138 0.0 0.0 Br-83 1.1(-10) 0.0 Br-84 0.0 0.0 Br-85 0.0 0.0 I-130 1.7(-6) 2. 7 (-11)
I-131 2. 4 (-3) 2. 1 (-5)
I-132 1. 2 (-9) 0.0 I-133 8. 4 (-4) 2. 1 {-7)
I-134 0.0 0.0 I-135 l. 9 (-5) 8.4(-13)
Rb-86 1. 5 (-6) 5.5(-8)
Rb-88 0.0 0.0 Cs-134 6.4 (-4) 2. 9 (-5)
Cs-136 2. 2 (-4) 7. 8 (-6)
Cs-137 4. 8 (-4) 2. 2 (-5)
N-16 0.0 0.0 H-3 3. 8 (-1) 3.7 (-1)
Y-90 7. 2 (-9) 2. 6 (-11)
Y-91M 0.0 0.0 Y-91 9. 6 (-7) 1. 2 (-8)
Y-93 l. 62 (-8) 5. 6 (-14)
Mb-99 5. (-4) 1. 9 (-6)
Sr-89 5. 0 (-6) 6. 2 (-8)
Sr-90 3. 4 (-7) 4. 6 (-9)
Sr-91 2. 6 (-7) 5. 6 (-13)
3. 5-9
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-4 REFUELING ACTIVITIES (Sheet 2 of 2)
Expected, Peak Refueling Activities (uCi/g)
Radionuclide Refueling Pool Spent Fuel Pool Zr-95 9.4 (-7) 1. 2 (-8)
Nb-95 9.4 (-7) 1. 1 (-8)
Tc-99M 2. 7 (-6) 3. 6 (-14)
RU-103 5.8 (-7) 7. 1(-9)
Ru-106 2.7 (-7) 3. 6 (-9)
Rh-103M 0.0 0.0 Rh-106 0.0 0.0 Te-125M 4. 3 (-7) 5. 4 (-9)
Te-127M 5. 5 (-6) 7. 1 (-8)
Te-127 2. 9 (-7) 5. 5 (-13)
Te-129M 1. 7 (-5) 2. 1 (-7)
Te-129 0.0 0.0 Te-131M 8. 8 (-6). 7. 3 (-.9)
Te-131 0.0 0.0 Te-132 1.7 (-4) 7. 9 (-7)
Ba-137M 0.0 0.0 Ba-140 2. 1 (-6) 2. 1(-8)
La-140 6. 9 (-7) 1. 2 (-9)
Ce-141 8.4 (-7) 1. 0 (-8)
l. 58 (-7)
~
Ce-143 1.7(-10)
Ce-144 8. (-7) 1. 2 (-8)
Pr-143 4. 8 (-7) 5. 0 (-9)
Pr-144 0.0 0.0 Np-239 6.9(-6) 2. 1(-8)
Cr-51 1.6(-5) 1. 9 (-7)
Mn-54 3. 3 (-6) 4. 3 (-8)
Fe-55 1. 7 (-5) 2. 3 (-7)
Fe-59 8. 8 (-6) 1. 1 (-7)
Co-58 1. 5 (-4) 1. 9 (-6)
Co-60 2. 2 (-5) 3. 0 (-7) 3.5-10
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM sumps and sent to the IRS for processing. Gaseous leakage is generated from such potential sources as compressor seals and valve packings. This activity becomes immediately airborne and is eventually released via the building ventilation systems. Using the assumptions listed in table 3.5-5, the airborne concentrations shown in table 3.5-6 were calculated.
Credit was taken for filtration where applicable.
3.5.2 LIQUID RADWASTE SYSTEM System and flow diagrams are shown in figures 3.5-2 and 3.5-3, respectively. Table 3.5-7 lists expected inputs and input activities to the LRS. Maximum radioactive inventories of the LRS tanks are listed in table 3.5-8 based on the maximum source terms given in FSAR Section 11.1 and the assumptions in FSAR Section 11.2. Principal specifications of LRS components are listed in table 3.5-9. A separate laundry waste system is not. required as PVNGS will utilize a dry cleaning laundry.
There are no liquid releases from PVNGS.
3.5.3 GASEOUS RADWASTE SYSTEM The GRS has not. changed substantially from the ER-CP and FES presentations. PSI and flow diagrams for the GRS are shown in figures 3.5-4 and 3.5-5 respectively. Table 3.5-10 lists expected inputs and input activities to the GRS. Radioactive inventories of the GRS tanks are listed in table 3.5-8 based on the assumptions given in FSAR Section 11.3. Principal specifications of GRS components are listed in table 3.5-11.
The estimated annual gaseous releases from PVNGS are shown in table 3.5-12.
3.5-11
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-5 ASSUMPTIONS USED IN DETERMINING AIRBORNE RADIOACTIVITY (Sheet 1 of 2)
Item Value Leakage Primary to secondary, lb/d 100 Auxiliary and radwaste bldg, (with respect to primary coolant), lb/d 160 Turbine building steam, lb/h 1,700 Charging pump room, gal/h Aux bldg ion exchanger (Ix) valve gallery, gal/h 0.15 Radwaste bldg conc tank valve gallery, gal/h 0. 05 Radwaste bldg LRS pump valve gallery, gal/h 0.22 Iodine partition factors Steam generators 0.01 All buildings except containment 0.0075 Containment (fraction of RCS iodine released to building atmosphere per day) 0.00001 Noble gas partition factors All buildings except. containment Containment (fraction of RCS noble gas inventory released to building atmosphere per day) .01 Bldg/area vent flowrates, ft /min 3
Containment Refueling purge exhaust (high volume) 30,000 3.5-12
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-5 ASSUMPTIONS USED IN DETERMINING AIRBORNE RADIOACTIVITY (Sheet 2 of 2)
Item Value Normal purge exhaust (low volume) 2,000 Fuel building exhaust 43,500 Auxiliary building exhaust, 60,000 Radwaste building exhaust 51,000 Turbine building exhaust 328,000 Charging pump room 1,100 Auxiliary bldg ion exchanger (Ix) valve gallery 400 Radwaste bldg conc tanks valve gallery 250 Radwaste bldg LRS pumps valve gallery 500 Building/area free volumes, ft3 Containment. 2.6 x 10 6 Fuel building 7.5 x 10 5 Turbine building 6.9 x 10 6 Auxiliary building 1.2 x 10 6 Charging pump room 8.5 x 10 3 Ion exchanger valve gallery 4.0 x 10 3 Radwaste building 4.6 x 10 5 3
Concentrate tanks valve gallery 1.5 x 10 3
LRS pump valve gallery 4.4 x 10 3.5-13
Table 3.5-6 NORMAL Radwaste Building Kr 85m 6 (-6) 8. 0 (-07) Kr-&5 1 (-5) 4. 6 (-06) Kr-87 1(-6) 1. 5 (-07) Kr-88 1 (-6) 1.0(-06) Kr-&9 1 (-6) 5. 5 {-10) Xe-131m 2 (-5) 3. 4 (-06) Xe-133m 1 (-5) 5. 5 (-06) Xe-133 1(-5) 5.0(-04) Xe-135m 1(-6) 7.1(-09) Xe-135 4 (-6) 4.2(-06) Xe-137 1 (-6) 1.2(-09) Xe-138 1 (-6) 2.2(-08) Br-83 3 (-9) 2.4(-11) Br-84 1 (-6) 2.9(-12) Br-85 1 (-6) 3.1(-14) I-130 3 (-9) 5. 0 (-11) I-131 9 (-9) 4.6(-08) I-132 2 (-7) 4.6(-10) I-133 3 (-8) 1.5(-08) I-134 5 ("7} 8.8(-11) I-135 1(-7) 2.6(-09) Co-60 9 (-9) 1.4 (-09) Co-58 5 (-8) 3. 2 (-09) Fe-59 5 (-8) 3. 2 (-10) AIRBORNE RADIOACTIVITY CONCENTRATIONS (Ci/cm ) (Sheet l of 2) Turbine Auxiliary Building Building NPC Air Containment Building Conc Tk LRS Pumps Radio- (sci/cm3) Fuel Charging Ix Valve Valve Valve Operating nuclide (40 h/Mk) Pre-Access Refueling Bldg Corridor Pump Room Gallery Corridor Gallery Gallery Deck Kr-83m 1 (-6) 7.6(-08) 5.3(-10) 4. 0 (-08) 3. 4 (-09) 5. 3 (-10) 1.2(-14) F 1(-09) 2. 2 (-07) 1. 9 (-08) 3.1 (-09) 6.8( 14) 4.5(-09) 3. 0 (-07) 2. 6 (-08) 4.5 (-09} 3. 0 (-09) 9. 9(-14) 1.4(-09) 1. 1 (-07) 9. 6 (-09) 1. 4 (-09) 3. 4 (-14) 5.3{ 09) 3. 9 (-07) 3. 4 {-08) 5. 3 {-09) 1. 1 (-15) 1. 2 (-13) 2.1( 11) 3.7(-09) 2.7(-10) 2.1( 11) 1.4(-15) 3.2(-09) 2.2(-07) 1.9 (-08) 3.2(-09) 8.7(-10) 5.3(-14) 6.4(-09) 4.4{-07) 3.7(-08) 6.4("09) 4.5(-11) 1.4( 13) 5.3(-07) 3.6(-05) 3.1(-06) 5.3(-07) 4.5(-08) 1.2(-11) 1.7(-10) 1.9(-08). 1.6(-09) 1.7(-10) 5.7(-15) 1.0(-08) 7.0(-07) 6.0(-08) 1.0(-08) 6.2(-15) 2.3(-13) 4.3(-11) 7.6(-09) 5.6(-10) 4.3( ll) 2.7( 15) 5.5(-10) 6.4(-08) 5.1(-09) 5.5{-10) 1.9( 14) 4.5(-12) 7 '(-12) 6.0(-12) 4.5("12) l. 5 (-15) 8.1(-13) 3.4 (-12) 2.8(-12) 8.1(-13) 9.7(-15) 1.6 {-13) 1.1(-13) 9.7( 15) 3.6(-12) 3.2(-12) 2.7(>>12) 3.6(-12) 1.7 (-15) 5.9(-10) 4.1(-10) 3.5(-10) 5.9("10) 8.0(-14) 1.0(-11) 3.2( 13) 9.2(-ll) ).5(-10) 1.2(-10) 9.2(-ll) 3.0(-14} 7.3( 10) 5.8(-10) 4 .9(-10) 7.3(-101 1.1(-14) 3.6 (-14) 2.2(-11) 6.5(-10) 5.4(-11) 2.2(-11) 6.5{ 15) 2.8(-10) 2.8(-10) 2.4(-10) 2.8(-10) 1.2( 13) 3.8 (-11) 4.0(-14) 3.5(-14) 3.8(-11) 2.6(-13) 8. 1(-15) 8.4(-11) 3.2(-13) 2.8(-13) 8.4( 11) 4.1(-13) 3.6(-15) 8.4(-12) 2.0(-14) 1.7 (-14) 8 .4( 12) 2.7(-14) 1.8(-15)
Table 3.5-6 3 NORMAL AIRBORNE RADIOACTIVITY CONCENTRATIONS ()ICi/cm ) (Sheet 2 of 2) Radwaste Building Turbine Auxiliary Building Building HPC Air Containment Building Conc Tk LRS Pumps Radio- (u Ci/cm3) Fuel Charging Ix Valve Valve Valve Operating nuclide (40 h/wk) Pre-Access Refueling Bldg Corridor Pump Room Gallery Corridor Gallery Gallery Deck Mn-54 4 (-8) 9.2( 10) 2. 5 (-11) 6. 3 (-15) 5. 4 (-15) 2. 5 (-11) 2 3 (-12) 1. 1 (-15) Cs-137 1(-8) 1.6(-09) 4. 2 (-11) 1. 8 (-12) 3. 2 (-13) 4. 2 (-11) 2. 7 (-12) 7. 0 (-14) Cs-134 1 (-8) 9.2(-10) 2. 5 (-11) 2. 5 (-12) 4. 4 (-13) 2.5(-11) 1. 4 (-15) 9. 2 (-14) Sr-90 1(-9) l. 3 (-ll) 2. 8 (-13) 2. 0 (-16) 1. 7 (-16) 2 8(-13) 5. 3 (-15) Sr-89 3 (-8) 7 ~ 1 (-11) 1. 8 (-12) 7. 1(-15) 6. 1 (-15) 1. 8 (-12) 8. 6 (-10) H-3 5 (-6) 7.3(-08) 2. 5 (-06) 1.1(-06) 5. 9 (-09) 1. 2 (-07) 2. 0 (-08) 5.9(-09) 1.1(-14) 1.2(-09) 2.9(-,09) C-14 4 (-6) 4. 2 (-08) Ar-41 2 (-6) 1 ~ 1(-06) Total 5 ~ 2 (-04) 2. 5(-06) 1. 1 (-06) 6. 2 (-07) 3. 9 (-05) 3- 3 (-06) 5 7(-07) 8. 7 (-10) 5. 0 (-08) 2. 9 (-09) IrI I 0
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-7 WASTE INPUTS TO THE LRS (Sheet 1 of 2) Expected Flow Design Flow LRS Inputs (gal/d-unit) (gal/d-unit) Activity Hi h TDS Holdu Tan s Containment sump 40 40 1 PCA Auxiliary build- 200 200 0.1 PCA ing floor drains Condensate 20,000 100% of polisher regenerant regenerants waste activity Blowdown 12,000 gal/ 12,000 gal/ 100% of demineralizer 15 days 15 days regenerant regenerants waste activity Chemical drain 115 115 See chemical tank drain tank inputs Laboratory drains 400 400 0.002 PCA Miscellaneous 700 700 0.01 PCA sources Total 2,255 22,255 Low TDS Holdu Tan Turbine building 7,200 7,200 100% of main floor drains steam activity
a. PCA = Primary Coolant Activity.
3.5-16
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-7 WASTE INPUTS TO THE LRS (Sheet 2 of 2) Expected Flow Design Flow LRS Inputs (gal/d-unit) (gal/d-unit) Activity Low TDS Holdu Tan cont. Secondary system 300 300 100% of main samples steam activity Condensate 36,000 100% of polisher regenerant regenerants waste activity Blowdown 12,000 gal/ 12,000 gal/ 100% of demineralizer 15 days 15 days regenerant regenerants waste activity Total 8,300 44, 300 Chemical Drain Tan s Decon station 100 100 See waste plus NUREG 0017, showers Table 2-20 Primary system 15 15 1 PCA samples Total 115 115 3.5-17
Table 3.5-8 MAXIMUM RADIOACTIVITY INVENTORIES OF EQUIPMENT IN THE RADWASTE BUILDING (Ci) (Sheet 1 of 4) High TDS Low TDS Concentrate Rccyclc High Activity Low Activity Radio- Holdup Holdup Honitor Monitor LRS Spent. Rcssn Spent Resin LRS Hixed Bed LRS Adsorption nuclide Tank Tank Tank Tank Evaporator Tank Tank Ion Pxchanger Bed Kr-85m 1. 2 (-1) 4.9(-6) 0.0 4. 6 (-7) 0.0 0.0 0.0 0.0 0.0 Kr-85 1. 2(-1) 9. 9 (-7) 0. 0 5. 6 (-2) 0.0 0.0 0.0 0.0 0~0 Kr-87 1.8 (-2) 8 '(-7) 0.0 2.2(-8) 0.0 0.0 0.0 0.0 0.0 Kr-88 1. 2 (-1) 5-3(-6) 0.0 3.1(-7) 0.0 0.0 0.0 0.0 0.0 Xe-131m 5. 3 (-1) 2. 9 (-6) 0. 0 5.9(-2) 0.0 0.0 0.0 0.0 0.0 Xe-133 3. 8 (+1) 8.5(-4) 0.0 1.9 0. 0 0.0 0.0 0.0 0.0 Xe-135 5. 9 (-1) 3.8(-5) 0.0 7. 1(-6) 0.0 0.0 0.0 0.0 0.0 Xe-138 2. 3 (-3) 9.5(-8) 0.0 4.7(-10) 0.0 0.0 0.0 0.0 0.0 Br-84 2. 9 (-4) 9. 3 (-7) 0. 0 1.0(-11) 0.0 8.2(-01) 0 ' 1.0(-8) 1.0(-8) I-129 1. 2 (-5) 3. 2 (-6) 8. 7 (-5) 2.5(-9) 5. 2(-5) 8.8(-03) 0.0 3.2(-4) 3.2(-4) I-131 3. 0 (+1) 8 ' 1. 4 (+1) 6.0(-3) 5. 5(+1) 2.9(+04) 4.2(+01) 3.3(+1) -3.3 (+1) I-132 2. 6 (-2) 9.3(-4) 0.0 4.4(-8) 0.0 7.1(+01) 0.0 4. 4 (-5) 4. 4 (-5) I-133 1.8 5.5(-1) 8.2(-5) 2.0(-4) 3. 0(-3) 3.6(+03) 0.0 2. 4 (-1) 2. 4 (-1) I-134 7.8 (-3) 5. 9 (-5) 0. 0 1.1(-9) 0.0 2.3(+01) 0.0 1. 1 (-6) 1.1(-6) I-135 2. 9 (-1) 3. 0 (-2) 1. 7 (-13) 4.2(-6) 2. 0 (-11) . 7.6(+02) 0.0 4.1(-3) 4.1(-3) Rb-88 1. 2(-2) 1. 3(-5) 0. 0 3. 9 (-9) 0.0 2.4(+01) 0.0 3. 9 (-8) 3.9(-8) Rb-89 6. 1(-4) 2. 6 (-7) 0. 0 7. 0 (-11) 0.0 1.2 0.0 6.9(-10) 6.9(-10) Cs-134 2. 0 (+1) 5.2 l. 4 (+2) 2.1(-1) 8. 4 (+1) 1.3(+04) 2.3(+02) 2. 3 (+2) 2.3(-2) Cs-136 1.5 4.5(-1) 1.6 1. 7(-2) 3.9 5.3(+02) 1.0 1.5 1.5 Cs-137 8.7(+1) 2.3(+1) 6.3(+2) 9. 2 (-1) 3~8 (+2) 3-9(+04) 1.2(+03) 1. 2 (+31 1.2(+3) Cs-138 7. 8 (-3) 3.0(-5) 0.0 1.7 (-8) 0.0 1.4(+01) 0.0 1. 7 (-7) 1.7(-7) H-3 2.2 1 ~4 (-1) 3. 6 (-1) 5. 7 (-1) 2.2(-1) 0.0 0.0 0.0 0.0 Y-90 9. 1 (-4) 4. 8 (-4) 2. 6 (-5) 2. 9 (-7) 3.0(-4) 1.2(-01) 0.0 6.3(-4) 6.3(-4) (a) Based on design basis source terms.
Table 3.5-8 MAXIMUM RADIOACTIVITY INVENTORIES OF EQUIPMENT IN THE RADWASTE BUILDING (Ci) (Sheet 2 of 4) High TDS Low TDS Conccntrntc Rccyclc High hctivity IA)w hc'tivity Radio- Holdup Holdup Monitor Monitor I.RS gpcnl Rc sin Spent Resin LRS Mixed Bed LRS hdsorption nuclidc Tank Tank Tank Tank Ilvaixir.itnr Tunk 'I'ank Ion Bxchangcr Bcd Y 91 1.7 5. 0(-1) 7.4 3.9(-4) 6.& 3. 8 (+01) 1.3(+01) 1.4 (+1) 1. 4 (+1) Mo-99 3:8 1.8 1.2(-1) 1.1(-3) 1.4 1.7(+03) 2.0 2.4 2.4 Sr-89 3.0(-1) 8.2(-2) 1.2 6.4 (-5) 2.2(+02) 2.0 "2.0 2.0 Sr-90 6.3(-2) 1.7 (-2) 4 .6(-1) 1. 3 (-5) 2- 7 (-1) 3. 0 (+01) 1.0 1.7 1.7 Sr-91 1.1(-3) 1.1(-4) 2.0(-12) 2. 2 (-8) 1.6(-10) 2.8 0.0 2. 2 (-5) 2.2(-5) Zr-95 5.4(-1) 1.5(-1) 2.4 1. 2 (-4) 2.1 5.0(+01) 0.0 4.6 4.6 Hh-95 1.2(-5) 0.0 3. 6 (-5) 1.0(-12) 4. 2(-5) 0.0b 0.0 4.4 (-9) 4.4(-9) RQ-103 3. 7 (-1) 1. 1(-1) 1. 2 &.3(-5) 1.4 2. 2 (+01) 2.0 2.1 2.1 RQ-106 3. 9 (-1) 1. 1 (-1) 2. 6 8. 3 (-5) 1.6 3.o(+ol) 8.0 8.1 8.1 Te-129 1. 9 (-4) 2. 8 (-6) 0. 0 6.8(-11) 0.0 5.2(-01) 0.0 6.7(-8) 6. 7 (-8) Te-132 8.4(-1) 3.0(-1) 4.6(-2) 1.9(-4) 4.4(-1) 7. 4 (+02) 0.0 4.9 (-1) 4.9(-1) Te-134 3.2(-4) 2.4(-6) 0.0 3.5(-11) 0.0 9.5(-01) 0.0 3. 5 (-8) 3. 5 (-8) Ba-140 F 2(-1) 3.4(-2) 1-2(-1) 2.5(-51 3.0(-1) 7.4(tol) 0.0 2. 1 (-1) 2. 1 (-1) La-140 4.9 (-3) 2. 6 (-3) 1. 9 (-5) 1.3(-61 3.6(-4) 3.4 0.0 2. 1 (-3) 2. 1(-3) Ce-144 8.3(-1) 2.3(-1) 5.3 1.8(-4) 3. 5 7.0(+01) 1. 6 (+01) l. 6 (+1) l. 6 (+1) Fr-143 9. 0 (-2) 2. 9 (-2) 1. 0 (-1) 2.1(-5) 2. 4 (-1) 1.0(+01) 0.0 1. 9 (-1) 1. 9 (-1) Cr-51 7.7 (-2) 2. 1(-2) 2. 0(-1) 1.6(-5) 2.6(-1) 5.5 0.0 2. 9 (-1) 2. 9 (-1) Mn-54 7. 2 (-2) 1. 9 (-2) 4. 7 (-1) 1.5(-5) 3. 1(-1) 4.8 1.0 1.4 1.4 Fe-55 4.6(-1) 1.2(-1) 3.2 9. 8 (-5) 2.0 3.0(tol) 1.1(+01) l. 1 (+1) 1.1(+1) Fe-59 6. 6 (-2) 1. 8 (-2) 2. 4 (-1) 1. 4 (-5) 2.5(-1) 4.6 0.0 4.0(-1) 4.0(-1) Co-58 1.6 4.5(-1) 7.6 3. 5 (-4) 6.5 1.1(+02) l. 4 (+01) l. 5 (+1) 1.5(+1) Co-60 6.1(-1) 1.6(-1) 4.3 1. 3 (-4) 2.6 4.0(+01) 1.5(+01) l. 5 (+1) 1.5(+1)
Table 3.5-8 MAXIMUM RADIOACTIVITY INVENTORIES OF EQUIPMENT IN THE RADWASTE BUILDING (Ci) (Sheet 3 of 4) Boric Acid Boric Acid . Waste Gas Waste Gas Condensate Waste Gas Waste Gas Condensate Radionuclide Surge Tank Decay Tank Ion Exchanger Radio>>>>elide Surge"Fink Bccay Tank Ion, Exchanger Kr-83m 1. 7 (+1) 0.0 Rb-86 4.2(-7) 4.7(-6) 0.0 Kr-85m 1.1(+2) 1.4(+1) 3. 3 (-8) Rb-88 3.0(-4) 1.1(-5) 2.9(-8) Kr-85 1.7(+2) 3. 3 (+3) 2. 9 (-8) Rb-89 0.0 0.0 1.5(-9) Kr-87 4.5(+1) 2.2 9.2(-9) Cs-134 l. 2 (-4) 3.4 (-3) 4.5(-7) Kr-88 1.8(+2) 1. 6 (+1) 5.7(-8) Cs-136 6.6(-5) 6. 1 (-4) 1.9(-7) Kr-89 3. 8 (-1) 7. 1(-3) 0.0 Cs-137 9.0( 5) 2. 6 (-3) 1.2(-6) Xe-131m 1.2(+2) 7. 3 (+2) 1.3(-7) Cs-138 0.0 0.0 1.9(-8) Xe-133m 2.5(+2) 3.2(+2) 0.0 H-3 0.0 0.0 0.0 Xe-133 2.0(+4) 6.2(+4) 9. 9 (-6) Y-90 1.8(-8) 9.5(-1) 1.6(-10) Xe-135m 4.0 9.3(-2) 0.0 Y-91m 2.8(-6) 1.2( 7) 0.0 Xe-135 3.9(+2) 9.3(+1) 2 '(-7) Y-91 9.4(-7) 1.3(-5) 7.0(-9) Xe-137 8. 7 (-1) 1.6(-2) 0-0 Y-93 4.5(-7) 1.4(-7) 0.0 Xe-138 1. 2 (+1) 2. 8 {-1) l. 2 (-9) Mo-99 1.2(-3) 2.3(-3) 2.3( 6) Br-83 5.4(-5) 4. 7 (-6) 0.0 Sr-89 5.2(-6) 6. 7 (-5) 4.8(-8) Br-84 1.6(-5) 5.7(-7) 6.7 (-10) Sr-90 1.5(-7) 3. 3 (-6) 1.7 (-9) Br-85 2. 9(-7) 6. 1 (-9) 0.0 Sr-91 9.0(-6) 2. 6 {-6) 4.9 (-9) I-129 0.0 0.0 1. 9 (-9) Zr-95 9.0(-7) 1. 3 (-5) 8.7 (-9) I-130 2. 9 (-5) 1.1(-5) 0.0 Rb-95 7.3(-7) 8. 3 (-6) 0.0 I-131 4.1(-3) 2.1 (-2) 3. 8 (-3) Tc-99m 1. 2 (-4) 0.0 I-132 1. 1 (-3) 9. 6 (-5) 2.4(-7) Ru-103 6.6(-7) 7.8{ 6) 5.7 (-9) I-133 5. 4 (-3) 3. 3(-3) 8.9(-5) Ru-106 1 5(-7) 3.0(-6) 2. 3 (-9) I 134 3.8(-4) 1. 7 (-5) 3. 0(-8) Rh-103m 3. 8 (-7) 1.7( 8) 0.0 I-135 2.5(-3) 5. 2 (-4) 7.1(-6) Rh-106 1.7 (-9) 3. 5 (-11) 0.0
Table 3.5-8 MAXIMUM RADIOACTIVITY INVENTORIES OF EQUIPMENT IN THE RADWASTE BUILDING (Ci) (Sheet 4 of 4) Boric Acid Boric Acid Waste Gas Waste Gas Condensate Waste Gas Waste Gas Condensate Radionuclide Surge Tank Decay Tank Ion Exchanger Radionuclide Surge Tank Decay Tank Ion Exchanger Te-125m 4. 2 (-7) 5. 7 (-6) 0.0 Ce-141 1. 0 (-6) 1.1(-5) 0 ' Te-127m 4. 2 (-6) 6. 7 (-5) 0.0 Ce-143 5.8(-7) 5.5(-7) 0.0 Te-127 1. 2 (-5) 3.3 (-6) 0.0 Ce-144 4.9(-7) 9.4(-6) 5. 5 (-9) Te-129m 2. 1(-5) 2. 3 (-4) 0.0 Pr-143 7.3(-7) 5.3(-6) 6. 2 (-9) Te-129 1. 5 (-5) 7. 8 (-7) 8.9(-10) Pr-144 1.4(-7) 4.0(-9) 0.0 Te-131m 3. 7 (-5) 3. 2 (-5) 0.0 Hp-239 1.7(-5) 2.8(-5) 0.0 Te-131 6.0(-6) l. 9 (-7) 0.0 Cr-51 3.2(-4) 2.9 (-3) 1.9(-9) Te-132 4.1(-4) 9.1(-4) 5. 6(-5) Hn-54 5.2(-5) 8.9(-4) 1.9(-9) Te-134 0.0 0.0 1. 0(-9) Fe-55 2.7(-4) 5.0(-3) 3.7(-10) Ba-137m 1. 3 (-5) 2.8(-7) 0.0 Fe-59 1.7(-4) 1.8(-3) 1.1(-9) Ba-140 3. 3 (-6) 2.3(-5) 4. 8 (-8) Co-58 2.7(-3) 3. 4 (-2) 1.8(-8) La-140 2. 2 (-6) 2.5(-6) 4. 9 (-9) Co-60 3.3(-4) 6. 3 (-3) 2.4(-9)
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-9 LIQUID RADWASTE SYSTEM (LRS) EQUIPMENT DESCRIPTIONS (Sheet 1 of 7) Tanks High TDS Holdup Tanks (T-Ol A,B) Quantity/unit Capacity (each) 30,000 gal Design pressure/temp 15 psig/250F Operating pressure/temp Atmos/80F Material 304 SS Low TDS Holdup Tank (T-Ol C) Quantity/unit Capacity (each), gal 30,000 gal Design pressure/temp 15 psig/250F Operating pressure/temp Atmos/80F Material 304 SS Chemical Drain Tanks (T-05 A,B) Quantity/unit Capacity (each), gal 1100 gal Design pressure/temp 15 psig/250F Operating pressure/temp Atmos/80F Material 304 SS Anti-Foam Tank (T-07) Quantity/unit Capacity 110 gal of anti-foaming agent Design pressure/temp Atmos/120F Operating pressure/temp Atmos/80F Material 304 SS 3.5-22
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-9 LIQUID RADWASTE SYSTEM (LRS) EQUIPMENT DESCRIPTIONS (Sheet 2 of 7) Tanks (Continued) Concentrate Monitor Tanks (T-03 A,B) Quantity/unit 2'000 Capacity (each), gal Design pressure/temp 15 psig/2SOF Operating pressure/temp Atmos/170F Material Carpenter 20 Cb-3 Caustic Storage Tank (T-08) Quantity/unit Capacity, gal of caustic 2000 Design pressure/temp 1S psig/250F Operating pressure/temp Atmos/12 OF Material ASTM A-283-C Caustic Batch Tank (T-10) Quantity/unit 1 Capacity, gal 25 Design pressure/temp 1S psig/120F Operating pressure/temp Atmos/12 OF Material ASTM A53B Acid Storage Tank (T-06) Quantity/unit Capacity, gal of acid 450 Design pressure/temp 15 psig/120F Operating pxessure/temp Atmos/120F Material ASTM SA-515-70 3~5 23
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-9 LIQUID RADWASTE SYSTEM (LRS) EQUIPMENT DESCRIPTIONS (Sheet 3 of 7) Tanks (Continued) Acid Batch Tank (T-09) Quantity/unit Capacity 25 gal Design pressure/temp 15 psig/120F Operating pressure/temp Atmos/120F Material ASTM A53B Recycle Monitor Tanks (T-04 A,B) Quantity/unit Capacity/each 30,000 gal Design pressure/temp 15 psig/250F Operating pressure/temp Atmos/80F Material 304 SS Pumps LRS Holdup Pumps (P-Ol A,B,C) Quantity/unit Type Centrifugal Capacity 250 gal/min Design pressure/temp 98 psig/150F Material 316L SS Motor rpm/bhp 3600/25 Chemical Drain Pumps (P-02 A,B) Quantity/unit 2 Type Centrifugal Capacity 30 gal/min Design pressure/temp 74 psig/150F 3.5-24
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-9 LIQUID RADWASTE SYSTEM (LRS) EQUIPMENT DESCRIPTIONS (Sheet 4 of 7) Pumps (Continued) Chemical Drain Pumps (P-02 A,B) (Continued) Material 316L SS Motor rpm/bhp 3600/7.5 Anti-Foam Pump (P-07) Quantity/unit Type Positive displacement Capacity 54 gal/h Design pressure/temp 205 psia/175F Material 316 SS Motor rpm/bhp 1725/0.5 Recycle Monitor Pump (P-03) Quantity/unit 1 Type Centrifugal Capacity 150 gal/min Design pressure/temp 52 psig/150F Material 316L SS Motor rpm/bhp 3600/10 LRS Evaporator Main Recycle Pump (P-08) Quantity/unit 1 Type In-line propeller Capacity 10,500 gal/min Design pressure/temp 40 psig/250F Material Carpenter 20 Cb-3 Motor rpm/bhp 1750/75 3.5-25
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-9 LIQUID RADWASTE SYSTEM (LRS) EQUIPMENT DESCRIPTIONS E (Sheet 5 of 7) Pumps (Cont inued) LRS Evaporator Distillate Pumps (P-09 A,B) Quantity/unit 2 Type Centrifugal Capacity 30 gal/min Design pressure/temp 34 psig/250F
.Material 316 SS Motor rpm/bhp 3500/20 LRS Evaporator Concentrate Pumps (P-10 A,B)
Quantity/unit 2
'gype Centrifugal Capacity 50 gal/min Design pressure/temp 35 psig/224F Material Gould-A-Loy 20 Motor rpm/bhp 1750/0.75 LRS Steam Condensate Pump (P-11)
Quantity/unit 1 Type Centrifugal Capacity 22,000 lb/h Design pressure/temp 35 psig/281F Material 316 SS Motor rpm/bhp 3505/5 Concentrate Monitor Tank Pumps (P-04 A,B) Quantity/unit 2 Type Centrifugal Capacity 50 gal/min Design pressure/temp 43 psig/170F 3.5-26
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-9 LIQUID RADWASTE SYSTEM (LRS) EQUIPMENT DESCRIPTIONS (Sheet 6 of 7) Pumps (Continued) Concentrate Monitor Tank Pumps (P-04 A,B) Material 316 SS Motor rpm/bhp 3600/5 Filters LRS Ion Exchanger Prefilters (F-01 A,B) Quantity/unit Size 5pm 98%, 25 pm 100'50 Capacity gal/min Design pressure/temp 200 psig/250F Operating pressure/temp 90 psig/125F Material (shell) 304 SS Ion Exchangers LRS Adsorption Bed (D-01) Quantity/unit 1 Capacity 50 ft carbon 3 of activated Flowrate 130 gal/min Design pressure/temp 200 psig/250F Material (shell) 304L SS Operating pressure/temp 90 psig/125F LRS Mixed Bed Ion Exchangers (D-02 A;B) Quantity/unit 2 Capacity 50 ft of 2:1 cation-to-anion 3 resin Flowrate 130 gal/min Design pressure/temp 200 psig/250F'.5-27
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-9 LIQUID RADWASTE SYSTEM (LRS) EQUIPMENT DESCRIPTIONS (Sheet 7 of 7) Ion Exchangers (Continued) LRS Mixed Bed Ion Exchangers (D-02 A,B) (Continued) Material (shell) 304L SS Operating pressure/temp = 90 psig/l25F Evaporator 'I LRS Evaporator Package Quantity/unit l Capacity 30 gal/min Type forced circulation Design pressure/temp 40 psig/250F Material Incoloy 825 (concentrate side) 304 SS (distillate side) 3.5-28
Table 3.5-10 MAJOR SOURCES / VOLUMES g AND FLOWRATES OF GASES TO THE GASEOUS RADWASTE SYSTEM Maximum Annual Volum~ Flowrate Annual Flowrate Source Gas (Standard ft ) (Standard ft /min) (Standard ft3/min) Volume control H2 2,500 0.006 tank N2 610 20 0.002 65 1.6E-4, Gas Stripper (b) 142,000 0.338 H2 N2 2,950 20 0.007 02 40 9.5E-5 Reactor drain H2 tank N2 7,759 20 0.02 02 Refueling failed H2 fuel detector U N2 2,000 20 0.005 O td O to
a. Flowrates are estimated expected maximums, not continuous.

b. Gas stripper values assume continuous gas stripping.
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-11 GASEOUS RADWASTE SYSTEM PROCESS EQUIPMENT DESCRIPTION Design Pressure/ Flowrate/ Material of Temperature Equipment Quantity Capacity Construction (psig/oF) Gas surge tank 760 ft Carbon steel with plastic 380/200 lining Compressors 10 std Stainless 380/150 ft3/min steel Waste gas 760 ft Carbon steel with plastic 380/200 decay tank lining 3.5.4 SOLID RADWASTE SYSTEM The Solid Radwaste System (SRS) has not changed substantially from the ER-CP and FES presentations. PVNGS utilizes a cement binder solidification syst: em. System and flow diagrams are shown in figures 3.5-6 and 3.5-7 respectively. Table 3.5-13 lists expected input activities to the SRS. Principal speci-fications of the SRS components are listed in table 3.5-14. Expected annual shipment activities from the SRS are provided in table 3.5-15. 3.5.5 PROCESS AND EFFLUENT MONITORING The process and effluent radiation monitors measure the radio-activity of selected process streams and of all principal gaseous effluent discharge paths. For additional information concerning process and effluent monitoring system refer to FSAR Section 11.5. 3.5-30
PVNGS ZR-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-12 NORMAL RADIOLOGICAL RELEASES (Curies per year .per unit) Nuclide Release Activity Kr-83m 8.0 (-1) Kr-85m 4.3 Kr-85 2.0 (+4) Kr-87 2.2 Kr-88 7:9 Kr-89 8.7 (-2) Xe-131m 3.3 (+2) Xe-133m 9.9 Xe-133 1.9 (+3) Xe-135m 3.5 (-1) Xe-135 1.5 (+1) Xe-137 1.7 (-1) Xe-138 1.2 BR-83 3.1 (-4) BR-84 9.9 (-'5) BR-85 2. (-6) 6'.1 I-130 (-4) I-131 4.0 (-2) I-132 6.5 (-3) I-133 4.3 (-2) I-134 2.2 (-3) I-135 1.7 (-2) Cs-134 5.0 (-4) Cs-137 8.0 (-4) Sr-89 3.6 (-5) Sr-90 5.6 (-6) H-3 1.0 (+3) C-14 8.0 Ar-41 2.5 (+1) Mn-54 4.5 (-4) Fe-59 1.6 (-4) Co-58 1.6 (-3) Co-60 7.0 (-4) 3.5-31
Table 3.5-13 SRS INPUT ACTIVITIES (Ci/hr) (Sheet 1 of 4) (PER UNIT) Evaporator Spent Resin SGB IX Cartridge Disposable Dry Nuclide Concentrates Beads Regenerants Filters Crud Filters Wastes BR-83 0.0 0.0 5. 9 (-06) 0.0 0.0 (b) BR-84 0.0 4. 3 (-01) 2. 0.(-07) 0.0 0.0 (b) BR-85 0.0 0.0 2. 0 (-10) 0.0 0.0 (b) I-129 0.0 4.4 (-03) 0.0 0.0 0.0 (b) I-130 0.0 0.0 3. 3 (-05) 0.0 0.0 (b) . I-131 1. 9 (-03) 1. 4 (+04) 1. 0 (-01) 0.0 0.0 (b) I-132 0.0 3. 7 (-01) 1.1(-04) 0.0 0.0 (b) I-133 0.0 l. 9 (+03) 1. 2 (-02) 0.0 0.0 (b), I-134 0.0 l. 2 (+Ol) 9. 2 (-08) 0.0 0.0 (b) I-135 0.0 4. 0 (+02) 1. 2 (-03) 0.0 0.0 (b) . as-86 l. 2 (-04) 0.0 7. 3 (-05) 0.0 0.0 (b) RB-88 0.0 1- 3 (+01) 4. 8 (-06) 0.0 0.0 (b) ', as-89 0.0 1.2 0.0 0.0 0.0 (b)'b) 4.9 6.'7'(+03) . 2. 1 (-01) 0.0 ,0. 0 CS-134 I r r R CS-136 .. ~ 3. 2 (-03) 2.7 (+02) 7. 8 (-03) 0.0 ~ 0; 0 (b) r 0 a0 Expected waste generation conditions only, maximum waste generation conditions are not tabulated because they are short-term inputs that are not representative of a year's continuous operation.
b. Nuclide breakdown was not made. Total activity is based on WASH 1258 estimates.
Table 3.5-13 SRS INPUT ACTIVITIES (Ci/hr) (Sheet 2 of 4) (PER UNIT) Evaporator Spent Resin SGB IX Cartridge Disposable Dry Nuclide Concentrates Beads Regenerants Filters Crud Filters Wastes CS-137 4.2 1. 9 (+04) 1. 7 (-Ol) 0.0 0.0 (b) CS-138 0.0 7.5 0.0 0.0 0.0 (b) N-16 0.0 0.0 0.0 0.0 0.0 (b) H-3 1.4 0.0 0.0 0.0 0.0 (b) Y-90 0.0 5. 8 (-02) 1. 5 (-07) 0.0 0.0 (b) Y-91M 0.0 0.0 7. 0 (-08) 0.0 0.0 (b) Y-91 2. 2 (-03) l. 9 (+01) 1. 8 (-04) 0.0 0.0 (b) Y-93 0.0 0.0 4.3(-07) 0.0 0.0 (b) MO-99 7. 1 (-11) 8. 5 (+02) 1. 1 (-02) 0.0 0.0 (b) SR-89 9. 6 (-03) l. 1 (+02) 8. 7 (-04) 0.0 0.0 (b) SR-90 2.4 (-03) 1. 5 (+01) 1. 0 (-04) 0.0 0.0 (b) SR-9 1 0.0 1.4 7. 8 (-06) 0.0 0.0 (b) ZR-95 2. 5 (-03) 2. 5 (+01) 1.9(-04) 2.7 1.7 (b)
4. 4 (-09) 8. 8 (-05) 0.0 0.0 (b)
NB-95 TC-99M
6. 3 (-04) 0.0 0.0 2. 9 (-04) 0.0 0.0 (b)- I RU-103 7. 1 (-04) 1. 1 (+Ol) 8. 9 (-05) 0.0 0.0 (b) 0 C td RU-106 2. 2 (-03) 1. 5 (-01) 7. 9 (-05) 0.0 0.0 (b) O M RH-103M 0.0 0.0 1. 1 (-08) 0.0 0.0 (b)'b)
RH-106 0.0 0.0 2. 2 (-13) 0.0 0.0
Table 3.5-13 SRS INPUT ACTIVITIES (Ci/hr) (Sheet 3 of 4) (PER UNIT) Evaporator Spent Resin SGB IX Cartridge Disposable Dry Nuclide Concentrates Beads Regenerants Filters Crud Filters Wastes TE-125M 9..6 (-04) 0.0 8. 2 (-05) 0.0 0.0 (b) TE-127M 2. 2 (-02) 0.0 1.3(-03) 0.0 0.0 (b) TE-127 0.0 0.0 9. 9 (-06) 0.0 0.0 (b) TE-129M 1.5(-02) 0.0 2. 3 (-03) 0.0 0.0 (b) TE-129 0.0 2. 7 (-01) 5. 8 (-07) 0.0 0.0 (b) TE-131M 0.0 0.0 1. 3 (-04) 0.0 0.0 (b) TE-131 0.0 0.0 5.6(-08) 0.0 0.0 (b) TE-132 8. 5 (-10) 3. 9 (+02) 4. 1 (-03) 0.0 0.0 (b) TE-134 0.0 5. 0 (-01) 0.0 0.0 0.0 (b) BA-137M 0.0 0.0 9. 2 (-09) 0.0 0.0 (b) BA-140 4.6(-05) 3. 7 (+01) 1. 4 (-04) 0.0 0.0 (b) LA-140 0.0 1.7 1. 1 (-05) 0.0 0.0 (b) CE-141 6. 8 (-04) 0.0 1. 1 (-04) 0.0 0.0 (b) CE-143 0.0 0.0 2. 3 (-06) 0.0 0.0 (b) CE-144 6. 0 (-03) 3. 5 (+ol) 2. 4 (-04) 0.0 0.0 (b) PR-143 1. 5 (-05) 5.0 3.4 (-05) 0.0 0.0 (b) PR-144 0.0 0.0 8. 2 (-10) 0.0 0.0 (b) NP-239 2. 0 (-14) 0.0 1.3(-04) 0.0 0.0 (b) CR-51 1. 2 (-02) 2a I 2.6(-03) 2. 8 (+01) l. 6 (+02) (b)
Table 3.5-13 SRS INPUT ACTIVITIES (Ci/hr) (Sheet 4 of 4) (PER UNIT) Evaporator Spent Resin SGB IX Cartridge Disposable Dry Nuclide Concentrates Beads Regenerants Filters Crud Filters Wastes MN-54 4. 9 (-02) 2.4 2. 3 (-03) 2. 5 (+Ol) 3.6 (b) FE-55 3. 4 (-01) 1. 5 (+Ol) 1.5(-02) l. 5 (+02) 0.0 (b) FE-59 2. 1 (-02) 2.3 2. 2 (-03) 2.39+01) 2.0 (b) CO-58 7. 4 (-01) 5. 6 (+01) 5. 4 (-02) 5. 6 (+02) 3. 2 (+02) (b) CO-60 4. 6 (-01) 2. 0 (+Ol) l. 9 (-02) 2. 0 (+08) 3. 6 (+01) (b) TOTAL l. 2 (+01) 4. 4 (+04) 1.2 1. 0 (+03) 5. 2 (+02) 1. 0 (+Ol) u 0 C
Table 3.5-14 SRS OUTPUT ACTIVITIES (Ci/yr/unit) (Sheet 1 of 4) Evaporator Spent Resin Cartridge Disposable Crud Nuclide Concentrates Beads Filters Filters Dry Wastes 'R-83 0.0 0.0 0.0 0.0 (b) BR-84 0.0 0.0 0.0 0.0 (b) BR-85 0.0 0.0 0.0 0.0 (b) I-129 0.0 4. 4 (-03) 0.0 0.0 (b) I-130 0;0 0.0 0.0 0.0 (b) I-131 1. 4 (-03) 1.9(-04) 0.0 0.0 (b) I-132 0.0 0.0 ~ 0.0 0.0 (b) I-133 0. 0.0 0.0 0.0 (b) 0'.0 I-134 0.0 0.0 0.0 (b) I-135 0.0 0.0 0.0 0.0 (b) RB-86 3.9(-05) 0.0 0.0 0.0 (b) RB-88 0.0 0.0 0.0 0.0 (b) RB-89 0.0 0.0 0.0 0.0 (b) CS-134 4.8 5.5(+03) 0.0 0.0 (b) CS-136 6.5(-04) 4.1(-03) 0.0 0.0 (b) CS-137 4.2 1.9(+04) 0.0 0.0 (b)
a. Expected waste generation conditions only. maximum waste generation conditions are not tabulated because they are short-term inputs that are not representative of 1 year's continuous operation.

b. Nuclide breakdown was not made. Total activity is based on WASH 1268 estimates.
Table 3.5-14 SRS OUTPUT ACTIVTTXES (Ci/yr/unit) (Sheet 2 of 4) Evaporator Spent Resin Cartridge Disposable Crud Nuclide Concentrates Beads Filters Filters Dry Wastes CS-138 0.0 0.0 0.0 0.0 (b) N-16 0.0 0.0 0.0 0.0 (b) H-3 1.4 0.0 0.0 0.0 (b) Y-90 0.0 0.0 0.0 0.0 (b) Y-91M 0.0 0.0 0.0 0.0 (b) Y-91 1. 5 (-03) 1.6 0.0 0.0 (b) Y-93 0.0 0.0 0.0 0.0 (b) MO-99 3. 6 (-14) 0.0 0.0 0.0 (b) SR-89 6. 3 (-03) 6.1 0.0 0.0 (b) SR-90 2. 4 (-03) 1. 5 (+01) 0.0 0.0 (b) SR-91 0.0 0.0 0.0 0.0 (b) ZR-95 1. 8 (-03) 2.6 1.4 1.7 (b) NB-95 3. 5 (-04) 0.0 0.0 0.0 (b) TC-99M 0.0 0.0 0.0 0.0 (b) RU-103 4. 2 (-04) 2. 7 (-01) 0.0 0.0 (b) U RU-106 2. 1 (-03) 1. 0 (+01) .0. 0 0.0 (b) 0.0 (b) 0 RH-103M 0.0 0.0 0.0 C 0.0 (b) O M RH-106 0.0 0.0 0.0 TE-125M 6. 7 (-04) 0.0 0.0 0.0 (b)
Table 3.5-14 SRS OUTPUT ACTIVITIES (Ci/yr/unit) (Sheet 3 of 4) Evaporator Spent Resin Cartridge Disposable Crud Nuclide Concentrates Beads Filters Filters Dry Wastes TE-127M 1. 8 (-02) 0.0 0.0 0.0 (b) TE-127 0.0 0.0 0.0 0.0 (b) TE-129M 7. 9 (-03) 0.0 0.0 0.0 (b) TE-129 0.0 4. 4 (-03) 0.0 0.0 (b) TE-131M 0.0 0.0 0.0 0.0 (b) TE-131 0.0 0.0 0.0 0.0 (b) TE-132 1.5(-12) 0.0 0.0 0.0 (b) TE-134 0.0 0.0 0.0 0.0 (b) BA-137M 0.0 0.0 0.0 0.0 (b) BA-140 9. 1 (-06) 4. 2 (-04) 0.0 0.0 (b) LA-140 0.0 0.0 0.0 0.0 (b) CE-141 3. 6 (-04) 0.0 0.0 0.0 (b) CE-143 , 0.0 0.0 0.0 0.0 (b) CE-144 5.6 (-03) 2.1(+01) 0.0 0.0 (b) PR-143 3. 2 (-06) 1.1(-04) 0.0 0.0 (b) PR-144 0.0 0.0 0.0 0.0 (b) 0 C NP-239 0.0 0.0 0.0 0.0 (b) W O M CR-51 5.3 (-03) 1. 4 (-02) 2. 7 (+01) 1. 6 (+02) (b) MN-54 4.6(-02) 1.5 2. 4 (+01) 3.6 (b) FE-55 3. 1 (-01) l. 3 (+Ol) l. 5 (+02) 0.0 (b)
Table 3.5-14 SRS OUTPUT ACTIVITIES (Ci/yr/unit)'Sheet 4 of 4) Evaporator Spent Resin Cartridge Disposable Crud Nuclide Concentrates Beads Filters Filters Dry Wastes FE-59 1. 3 (-02) 8.8(-02) 2. 3 (+Ol) 2.0 (b) CO-58 5. 5 (-01) 7.2 5. 6 (+02) 3.2(+02) (b) CO-60 4. 6 (-01) 1. 9 (+01) 2. 0 (+02) 3.6(+Ol) (b) TOTAL 1. 2 (+Ol) 2. 5 (+04) 9. 9 (+02) 5.2(+02) 1,0 (+01)
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM Table 3.5-15 SRS EQUIPMENT DESCRIPTIONS (Sheet 1 of 2) Materials of Item Quantity Capacity Construction Tanks Spent resin 250 ft3 total Stainless Steel tanks, 200 operating Waste feed tank 140 ft3 total Incoloy 825 120 ft operating Chemical addi- 250 gal Polyethylene tion tank Cement feed 90 ft Carbon steel tank Dry additive 12 ft Carbon steel feed tank Pumps Resin transfer/ 75 gal/min Stainless steel, dewatering with Buna 'N'tator pump Waste feed 16 gal/min Stainless steel, pump with Buna 'N'tator Chemical feed 220 gal/h PVC pump Other Disposable liners Consum-able 80 ft / 55-gal drum Carbon steel Cement/waste 250 lb/min Carbon steel mixer clad with type 316 stainless
'steel 3.5-40
PVNGS ER-OL RADNASTE SYSTEMS AND SOURCE TERM Table 3.5-15 o SRS EQUIPMENT DESCRIPTIONS (Sheet 2 of 2) Materials of Item Quantity Capacity Construction Cement screw 0.6-3.6 Carbon steel conveyor ft3/min Cement hopper 2.6 ft /min 3 Carbon steel Dry additive 0.37 ft /min 3 Carbon steel hopper Radwaste baler 55-gallon Carbon steel drums and stainless steel 3.5.5.1 Desi n Ob'ectives Effluent monitoring is provided during normal operation and anticipated operational occurrences to ensure compliance with applicable regulations. Design objectives and functional performance requirements for the effluent monitors are to: A. Alert plant personnel if it appears that technical specification limits may be reached or exceeded B. Provide a record of the rate, quantity and isotopic identification of radioactive material released to the environment C. Provide control signals that initiate automatic plant actions to terminate releases before technical speci-fication limits are exceeded. 3.5.5.2 S stem Description The minimum sensitivities, equipment ranges, and alarm set-points of the effluent monitors 'are based on meeting the guide-lines of 10CFR50 Appendix I and 10CFR20. 3.5-41
PVNGS ER-OL RADWASTE SYSTEMS AND SOURCE TERM The airborne effluent monitors obtain representative airborne concentrations by sampling plant releases in accordance with ANSI-N13.1. Although there are no pathways for the release of radioactive liquids to the environment from PVNGS and no liquid effluent monitors, several LRS process monitors are provided as described in FSAR Section 11.5.2. 3.g-Q2
(SPENT FUEL POOL EVAPORATION) (TRITIUM PRODUCTION) (MAKEUP-NONTRITIATED) (LEAKAGE TO LRS) REACTOR REACTOR MAKEUP SPENT COOLANT FUEL SYSTEM WATER TANK POOL BORIC ACID CONC 0. (DECAY) O LU (DISCHARGE) O O lU O 0 (REFUELING POOL EVAPORATION) (MAKEUP) (PR I MARY-TO-SECONDAR Y REFUELING LEAKAGE) WATER TANK (FUEL TRANSFER) (DECAY) Palo Verde Nuclear Generating Station ER-OL TRITIUM BALANCE FLOW DIAGRAM Figure 3.5-1
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PVNGS ER>>OL 3.6 CHEMICAL AND BIOCIDE WASTES Information presented in ER-CP Section 3.6 and the FES has been updated. As part of this update, detailed parameters such as flowrates, chemical consumption and operational frequencies are presented. 3.6.1 PREOPERATIONAL AND PERIODIC CLEANING WASTES Prior to the initial startup of each unit, the feedwater system from the condensers to the containment isolation valves (approximately 450,000 gal) will be flushed and chemically cleaned to remove dirt, grease, oil, rust, and mill scale. This will be accomplished by the following operations: A. Dirt and construction debris, estimated at 7470 lb, will be removed by flushing the piping with a high velocity water flush of approximately two system volumes of demineralized water. B. Chemical cleaning is not expected to be required. Should it become necessary, however, the following steps would be performed: Grease, oil, and dirt, estimated at 3735 lb, will be removed by flushing each system with approxi-mately 450,000 gallons of an alkaline phosphate solution of approximately 1% concentration. This will be followed with a rinse of approximately two system volumes of demineralized water.
2. Rust'. and mill scale will be removed from each system by circulating a 3% organic acid (2% hydrox-yacetic, 1% formic) solution containing a 0.2% acid inhibitor, such as Dow Chemical Co. A-145, for, several hours. This will be followed with a rinse of approximately two system volumes of demineral-ized water containing an estimated 5600 lb of citric acid. An estimated 33,615 lb of iron will be removed.
3.6-1
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES C. The system may be passivated by filling with demineral-ized water containing 200-400 ppm hydrazine and 0-60 ppm ammonia, to a pH of 9.0-10.0. Estimated total water volume used in a complete cleaning would be approximately 4,050,000 gallons. Wastes from this cleaning process will be directed to the onsite evaporation ponds. Periodic, non-radioactive opera-tional equipment cleaning wastes will be discharged to the evaporation ponds. 3.6.2 NONRADIOACTIVE OPERATIONAL WASTES The plant is designed to have no requirement, for offsite dis-posal of any chemical or liquid wastes. Operational nonradio-active'liquid wastes are collected and discharged to the onsite evaporation ponds. During normal operation of the plant, nonradioactive wastes come from the following sources: o Water reclamation plant e Circulating water system o Demineralized water system o Domestic water system o Condensate polishing demineralizer system e Laboratories and laundry o Floor drains Figure 3.3-1 diagrams all plant water and wastewater flows and includes a tabulation of the respective flow rates at various operating conditions. Table 3.6-1 includes a summary of the expected maximum and average concentrations of dissolved solids in the plant influent water from the City of Phoenix 91st Avenue Sewage Treatment Plant and the onsite wells. The table includes the quality of the circulating water which is discharged as cooling tower blowdown and drift.
~~3. 6-2~~
Table 3.6-1 ESTIMATED MAXIMUM AND AVERAGE CONCENTRATION OF CHEMICALS IN THE INFLUENT AND EFFLUENT WATER SYSTEMS (ppm) (Sheet 1 of 2) Influent Streams Effluent Streams Influent from Effluent from Phoenix 91st Avenue Circulating Water System Sewage Treatment Influent from (Cooling Tower Blowdown Plant Onsite Wells and Drift) Maximum Average Chemical Maximum Average Maximum Average (20 cycles) (15 cycles) Calcium 67.2 52.9 250.0 41.0 356.0 336.0 Magnesium 29.6 22.9 130.0 19.0 34.0 29.0 Sodium 192 186 li800.0 590.0 5,400.0 4i620..0 I Chloride 270 253 3,250.0 740.0 5,140.0 4,650.0 n o Sulfate 95.0 91.0 li330. 0 220.0 3,500.0 2i750.0 3: H Nitrate 4.20 1.85 200.0 30.0 2,300.0 1,990.0 n Silica 32.0 28.8 44.0 40.0 83.0 72.0 Phosphate 68.9 22.1 0.1 7.2 5.0 Fluoride 4.8 3.5 10.0 6.2 24.0 18.0 H Potassium 14.7 13.8 8.0 3.2 0 n H Copper 0.022 0.017 0.1 0.04 6.0 2 ' a Zinc 0.080 0.067 0.8 0.6 Iron 0.041 0 '35 0.1 0.08 3.5 1.0 Arsenic 0.006 0.005 0.02 0.01 0.4 0.3
Table 3.6-1 ESTIMATED MAXIMUM AND AVERAGE CONCENTRATIONS OF CHEMICALS IN THE INFLUENT AND EFFLUENT WATER SYSTEMS (ppm) (Sheet 2 of 2) Influent Streams Effluent Streams Influent from Effluent from Phoenix 91st Avenue Circulating Water System Sewage Treatment Influent from (Cooling Tower Blowdown Plant Onsite Wells and Drift) Maximum Average Chemical Maximum Average Maximum Average (20 cycles) (15 cycles) Boron 0.09 0.037 7.0 3.2 5.6 4.2 Q Ammonia-N 45.4 30.9 0.3 0.08 15.0 12.5 Phenol 0.018 0.009 0.01 0.009 0.01 0.006 I Dissolved A 0 Oxygen 8.2 6.7 7.0 7.0 F H Suspended n Solids 68 35 ' 150.0 110. 0 COD 187.7 87 14. 0 6.0 660.0 514.0 Alkalinity 285 272 230. 0 143.0 65.0 38.0 TDS li 083 1,039 5 g 980 ~ 0 1 g 520 ~ 0 17,000.0 14,600.0 N H 0n H
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES 3.6.2.1 Water Reclamation Plant The water reclamation plant receives the wastewater effluent from the City of Phoenix 91st Avenue Sewage Treatment, Plant, processes it further in four stages of treatment, and stores it in the onsite reservoir. This onsite treatment of the station makeup water is required to reduce the concentration levels of calcium, phosphate, silica, magnesium, and ammonia. Some incidental removal of organics occurs. The removal of these compounds allows the treated effluent to be concentrated to approximately 15 cycles in each generating unit circulating water system without excessive scaling or fouling of system components and heat exchangers. The water reclamation plant process is shown schematically in figure 3.6-1. The four stages of treatment are: e Biological nitrification o Lime treatment e Filtration o Chlorination The influent to the water reclamation plant (WRP) consists of effluent from the Phoenix treatment plant which provides pri-mary sedimentation and secondary activated sludge treatment. No further removal of organics is required in order to use the WRP influent water for cooling purposes in the power plant; therefore, treatment processes in the WRP have not, been designed to remove organics. However, some incidental remov-als will occur in certain processes as estimated by the following: Treatment Process Removal Biological nitrification 10 to 20% removal of dissolved (see section 3.6.2.1.1) (or colloidal) organics, measured as BOD 5 (5-day 3.6-5
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES Treatment Process Removal bio-chemical oxygen demand) or COD (chemical oxygen demand). Lime soda softening and Setter than 95% removal of clari.fication (see suspended organics, measured section'3.6.2.1.2) as volatile suspended solids, and 5 to 10% removal of col-loidal BOD5 and COD. Entire WRP, considered as Better than 95% removal of a whole suspended organics, and 10 to 25% removal of dissolved or colloidal organics. The WRP influent will contain an average of about 30 mg/k BOD5, 40 mg/R suspended solids, and 100 mg/2 COD. Lime clarification should provide high removal rates for viruses and bacteria, so pathogen levels in the WRP effluent are expected to be low. However, this water is expected to contain the broad spectrum of organics which typically occur in secondary sewage effluent due to their relative resistance to biodegradation. 3.6.2.1.1 Biological Nitrification Biological nitrification refers to the bacterial conversion of ammonia nitrogen to the nitrate nitrogen form., The following equations summarize the two-step reaction: NH
~~+ + 3/2 0 2 bacteria NO 2 + 2H+ + H 0 2~~
~~NO 2~~
~~+ 1/2 0 2 bacter>a NO 3~~
For nitrification, the trickling filter process has been selec-ted. In this process, nitrifying bacteria're attached to a solid medium along with other microorganisms. By distribution 3.6-6
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES of the wastewater effluent over the medium, ammonia comes into contact. with the nitrifying bacteria and is oxidized along with organic materials in the water. 3.6.2.1.2 Lime Treatment Following nitrification, the effluent is passed through a two-stage lime treatment process to reduce the concentrations of calcium, phosphate, silica, and magnesium. The first stage of treatment is the addition of lime (CaO), which produces a reaction between the calcium ion and the orthophosphate ion to precipitate the insoluble compound hydroxyapatite (Ca10(OH)2(P04)6). Simultaneously, the lime reacts with bicarbonate alkalinity, precipitating calcium carbonate. Because the addition of lime raises the pH, the solubility of the hydroxyapatite decreases. At a pH of approximately ll, most of the phosphate has been converted to this insoluble form. At this pH, the precipitation of magnesium hydroxide occurs and silica is adsorbed in the precipitate. The water, which still contains some dissolved calcium car-bonate and noncarbonate calcium hardness, flows to the second stage solids contact clarifier. Here, soda ash (Na2CO3) is added to precipitate the noncarbonate calcium hardness. At the same time, carbon dioxide gas is added to the flow stream to lower the pH and precipitate the excess calcium remaining in the water. The precipitated solids are settled in the clarifier, producing a sludge that is high in calcium,.car-bonate and ideally suited for recalcination. Following the second stage of lime treatment, the water still contains solids that have not been removed. by flocculation and settling. With a pH of approximately 10, the liquid is gen-erally supersaturated with calcium carbonate. Therefore, a small amount of sulfuric acid is added to lower the pH to approximately 9. This increases the solubility of the calcium 3.6-7
PVNGS 'ER-OL CHEMICAL AND BIOCIDE WASTES carbonate still in solution so it will not precipitate on the succeeding filtration media. 3.6.2.1.3 Chlorination Chlorination of the reclaimed water is provided for biological growth control of the water prior to storage in the, reservoir. A maximum of approximately 1.8 tons of chlorine per day is to be used in the water reclamation plant. Chlorine is added as a sodium hypochlorite solution. 3.6.2.1.4 Filtration Effluent from the chlorination process is filtered to remove residual amounts of suspended phosphorus, calcium, and other solids as shown in figure 3.6-1. The filtration process increases the reliability of the effluent guality by preventing the possibility of a carryover of suspended solids from the lime treatment process. The water reclamation plant includes trickling filter units and gravity filtration units. The trickling filter media consist of a PVC plastic tower packing which supports a film of microbiological organisms. The gravity filtration media con-sists of a 12-inch layer of 0.5 mm diameter silica sand support-ing a 24-inch layer of 0.9 mm diameter anthracite coal. 3.6.2.1.5 Wastes Generated Wastes generated from the water reclamation plant consist. of the precipitated solids from the lime softeners. These solids are directed to a recalciner where a portion of the sludge is recalcinated into lime (CaO) and. is reused in the lime softeners. Solid waste handling from the water reclamation plant is dis-cussed in section 3.7.
~~3. 6-8~~
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES 3.6.2.2 Circulatin Water S stem Each generating unit is provided with an independent circula-ting water system. This system, shown schematically in fig-ure 3.6-2, removes waste heat developed during normal operation and rejects it to the atmosphere via the three mechanical draft cooling towers. The circulating water system is discussed in section 3.4. Waste from the circulating water system consists of blowdown and drift from the cooling towers. Blowdown is continuously discharged to the evaporation ponds as required to maintain water quality. Drift is maintained at approximately 0.0044% of the 587,000 gal/min combined flow of the circulating water and plant cooling water system by the use of integral drift eliminators. in the cooling towers. Drift from the cooling towers is discussed in sections 5.1 and-5.3. Chlorine is added to the circulating system, as a sodium hypo-chlorite solution, to control biological growth. The amount of chlorine added is dependent upon the rate of biological growth in the circulating water. During the summer, because of in-creased biological growth on warm days, chlorine is injected in approximately three 40-minute injection periods per day for shock treatment. During the winter, when chlorine demand is low, only two 40-minute injection periods per day are required. It is expected that approximately 3500 pounds per day per unit of chlorine during the summer, and approximately 2300 pounds per day per unit of chlorine during the winter will be required for biogrowth control. The process consists of injecting the chlorine into the circulating water and the plant cooling water pump suctions in sufficient quantity to maintain a chlorine residual at the discharge of the condenser and heat exchangers of approximately 1 to 2 parts per million. Since the chlorine is injected in the hypochlorite form, no elemental chlorine is released to the atmosphere.
~~3. 6-9~~
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES Sulfuric acid is added to maintain the pH at approximately 7 to prevent deposition of calcium carbonate scale. Acid, 66 Baume, is diluted and distributed in the circulating water stream upstream of the circulating water pumps to ensure complete mixing and pH adjustment prior to entering the pumps. A dispersant is added to the circulating water to inhibit the formation of scale on condenser and heat exchanger tube surfaces. The main condenser and heat exchanger tubes are titanium'ith negligible corrosion rate. No other sources of corrosion products are expected since the circulating water lines are constructed of concrete and the plant cooling water lines and cooling tower risers are suitably lined, as are all valves and ferrous fittings. Since the rate of corrosion is minimal, it, is anticipated that no corrosion inhibitors will need to be added to the system. 3.6.2.3 Domestic Water S stem The domestic water system consists of four reverse osmosis modules in parallel. The reverse osmosis product is shared between the domestic and demineralized water systems. Interna" valves in the reverse osmosis system allow the output to be distributed on a 1:3, 1:1, or 3:1 basis to the receiving systems. A schematic flow diagram of the domestic water system is shown as figure 3.6-3. The reverse osmosis modules rated at approximately 200 gallons per minute each, remove approximately 90% of the total dis-solved solids (TDS) in the water, to bring the water guality within U.S. Public Health Service limits. The units reject approximately 20% of the incoming water as a.concentrate con-taining the removed dissolved solids. This concentrate is discharged into the evaporation pond. Sodium hypochlorite is added downstream of the reverse osmosis units 'prior to storage in the domestic water chlorine contact tank. 3.6-10
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES 3.6.2.4 Demineralized Water S stem The demineralized water system consists of three mixed bed ion exchangers, two normally operating in series and one on standby. Water is supplied to the demineralized water system from the reverse osmosis units in the domestic water system. A sche-matic flow diagram of the demineralized water system is shown as figure 3.6-4. The reverse osmosis product water is next passed through a degasifier, then is pumped through two mixed ion exchangers in series to remove dissolved solids to produce demineralized water. Periodically, the resins become depleted and the ion exchangers must be regenerated. The regeneration cycle consists of a back-wash to remove particulate matter, and to loosen and separate the resins, regeneration with an acid or caustic solution as appropriate, and a rinse to remove the spent regenerant. The backwash, spent regenerant, and rinse water are discharged into the spent regenerant sump. The neutralized waste in the sump is pumped to the evaporation ponds. It is estimated that the total PVNGS use of regenerant chemicals is approximately 850 lb of sodium hydroxide and 1000 lb of sulfuric acid per day. 3.6.2.5 Condensate Polishin Demineralizer S stem The secondary system fullflow condensate polishing deminerali-zer system, shown in figure 3.6-5, removes dissolved solids, in the secondary system. The system consists of six mixed bed demineralizers (five normally in service and one on standby) with the required regeneration equipment. 4 In the event of a steam generator tube leak, radioactive chem-ical regenerant, waste will be directed to the liquid radwaste system, as discussed in section 3.5. Nonradioactive, concen-trated chemical regenerant waste is directed to the evaporation 3.6-11
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES ponds. Dilute waste is discharged to the main circulating water system. An additional demineralizer system is provided for the steam generator blowdown. This system consists of a heat exchanger, mixed bed demineralizers, and the required regeneration equip-ment. Upon depletion of the resin in a given mixed bed, the resin is regenerated in place. The concentrated regenerant wastes are neutralized,*analyzed for radioactivity, and are discharged to the evaporation ponds or to the liquid radwaste system as appropriate. Wastes low in dissolved solids are analyzed for radioactivity and are discharged to the radwaste system or to the main circulating water system. It is estimated that one condensate polisher per unit will be r generated every 140 hours, and that 1040 lb of sodium hydroxide and 1870 lb of sulfuric acid will be required for each regeneration. It is estimated that a blowdown polisher will be regenerated every 900 hours, using 560 lb of sodium hydroxide and 750 lb of sulfuric acid for each regeneration. 3.6.2.6 Laboratories and Dr Cleanin Laundries Laboratories are provided for routine chemical analyses. Any radioactive samples are analyzed in separate "hot" laboratories, and all drains are directed to the liquid radwaste system. Other laboratory wastes are directed to the neutralizing tanks in the chemical waste system along with condensate and blowdown demineralizer wastes. The quantity of laboratory wastes is expected to be very small. The laundries are dry cleaning laundries; sludge wastes are sent to the solid radwaste system. 3.6.2.7 Floor Drains Floor drains from each unit are routed to the unit's oily-water separator, prior to discharge to the evaporation ponds. 3.6-12
PVNGS ER-OL CHEMICAL AND BIOCIDE WASTES Provisions are made to direct floor drains to the liquid rad-waste system or to the neutralizer tanks, if necessary. 3.6.3 NONRADIOACTIVE LIQUID WASTE DISPOSAL I All chemical and liquid waste is disposed of in the onsite evaporation ponds. 3.6.3.1 Eva oration Ponds The onsite evaporation ponds receive liquid waste from the generating units and remove moisture by natural evaporation. Initially, 250 acres of evaporation ponds will be constructed. The evaporation ponds may be expanded to contain additional liquid wastes. The ponds will be lined with a suitable mate-rial to limit seepage to. the groundwater. The evaporation ponds are sized to retain all liquid wastes. 3.6-13
C02 2 3, SODIUM HYPOCHLOR ITE Cao H3 SO4 FROM PHOENIX 91ST AVE BIOLOGICAL LIME TO NITR IF ICATION TREATMENT CHLORINATION F ILTR ATION SEWAGE RESERVOIR TREATMENT PLANT TO SOLID WASTE DISPOSAL Palo Verde Nuclear Generating Station r.;/Pz ER-OL WATER RECLAMATION PLANT - SCHEMATIC FLOW DIAGRAM Figure 3. 6-1
ll MECHANICALDRAFT COOLING TOWERS TURBINE AND NUCLEAR CONDENSER COOLING WATER HEAT EXCHANGERS CIRCULATINGWATER SYSTEM INTAKE STRUCTURE PLANT COOLING WATER SYSTEM FOAM CONTROL AGENT H SO SODIUM 2 4 HYPOCHLOR ITE D IS P ER SANT Palo Verde Nuclear Generating Station Zb ER-OL CIRCULATING WATER AND PLANT COOLING WATER SYSTEMS SCHEMATIC FLOW DIAGRAM Figure 3.6-2
TO DEMINERALIZED WATER SYSTEM VACUUM DEGASIF IER SODIUM HYPOCHLORITE DOMESTIC DOMESTIC ONSITE REVERSE WATER WATER TO PLANT OSMOSIS CHLORINE EACH UNIT WELLS UN ITS CONTACT 8( COMMON TANK FACILITIES CONCENTRATE EVAPORATION POND Palo verde Nuclear Generating Station ER-OL DOMESTIC WATER SYSTEM SCHEMATIC FLOW DIAGRAM Figure 3.6-3
VACUUM DEGASIF IER FROM DOMESTIC WATER SYSTEM REVERSE OSMOSIS UNITS HZSO4 Na OH DEMINERALIZED ION WATER TO EACH EXCHANGERS UNIT SPENT REGENERANT EVAPORATION POND SPENT REGENERANT SUMP Palo Verde Nuclear Generating Station ER-OL DEMINERALIZED WATER SYSTEM SCHEMATIC FLOW DIAGRAM Figure 3.6-4
RAW POLISHED CONDENSATE CONDENSATE CONDENSATE POLISHING DEMINERALI2ERS SPENT REGENERATED RESIN RESIN H2 SO~ RESIN REGENERATOR Na OH WASTE TO EVAPORATION POND Palo Verde Nuclear Generating Station ER-OL CONDENSATE POLISHING DEMINERALIZER SYSTEM SCHEMATIC PLOW DIAGRAM Figure 3.6-5
,A PVNGS ER-OL 3.7 SANITARY AND OTHER WASTE SYSTEMS The information presented in ER-CP Section 3.7 and the FES has been updated to reflect peak construction work force and gaseous effluent quantities based on plant specific equipment data. The information is updated and summarized in this section. 3.7.1 LIQUID WASTES 3.7.1.1 Sanitar Wastes It Facilities are provided to treat sanitary wastes produced dur-ing construction and operation except for that produced by field construction workers. Chemical toilets are used by field con-struction workers; wastes from the chemical toilets are hauled approximately 10 miles to the Maricopa county land fill site for disposal. The peak construction workforce (office plus field) was about 6200. The estimated quantity from chemical toilets is 34,000 gal/d based on 3400 field workers at 10 gal/d. It is estimated that a peak sanitary waste flowrate of 30,000 gal/d will be processed by the onsite sewage treatment .package plants. This sanitary waste will contain approximately 300 ppm of 5-day BOD and 300 ppm suspended solids. During construction, two package sewage treatment plants will be used, each with a rated capacity of 17.,500 gal/d for,a total capacity of 35,000 gal/d. During normal plant operation, the expected sewage load will be less than 15,000 gal/d. The treated effluent is recycled to the onsite water reclamation plant. Solid wastes are transported to, the onsite solid waste disposal area discussed in section 3.7.2.2. 3.7-1
PVNGS ER-OL SANITARY AND OTHER WASTE SYSTEMS 3.7.1.2 Other Li id Wastes Chemical laboratory wastes, dry cleaning waste, and decontamina-tion .solutions are described in section 3.6.2. 3.7.2 SOLID WASTES 3.7.2.1 Sources of Solid Waste 4 3.7.2.1.1 Water Reclamation Plant Sludge produced by the two-stage lime treatment process from the water reclamation plant is further concentrated in a classification centrifuge. A portion of the concentrated sludge is recalcined to recover lime for reuse in the lime A softening process. Approximately 15,500 tons of sludge per PVNGS unit requiring disposal is produced annually at the water reclamation plant. 3.7.2.1.2 Sanitary Waste Treatment Plant Sanitary sludge is produced in the package sewage treatment plants. Approximately 8 tons of dried sludge are produced annually during normal plant operation. 3.7.2.1.3 Service Buildings Wastes from the service buildings'consist of paper, rags, grit, and other nonrecyclable materials. This waste essentially ~ is in solid form. Approximately 150 tons per year are expected from this source. 3.7.2.1.4 Miscellaneous Various other solid wastes, such as those obtained in inter-mittent cleaning of the plant cooling tower basins and water storage reservoir, are anticipated and require disposal. The quantities produced will be small compared to other sources. 3 ~7 2
PVNGS ER-OL SANITARY AND OTHER WASTE SYSTEMS 3.7.2.2, Solid Waste Dis osal Area The solid waste'isp'osal 'area is approximately 200 acres., Sludge waste will be. spread in. the. area to dry out. '.Water reclamation plant waste is centrifuge dried prior to disposal in the solid waste di'sposal area. 3.7.3 GASEOUS EFFLUENTS 3.7.3.1 Diesel Generators Each diesel generator (two per unit.) nominally operates foi test purposes once a month for approximately 1 hour, and dis-charges approximately 2300 pounds NO , 540 pounds SO , and 35 pounds of hydrocarbons annually. Each diesel generator discharges through its own stack approximately 93 feet above plant grade. 3.7.3.2 AuxiliarI Boilers During operation, the auxiliary boilers are available for backup and are not normally used after initial startup. The three units share one set of two auxiliary boilers. When the boilers operate (approximately 8 days per unit per initial startup) they will produce about 2300 pounds NOx , 2812 pounds SO , and 682 pounds of hydrocarbons anually. The auxiliary boilers discharge through their own stacks 50 feet above plant grade. 3.7.3.3 Water Reclamation Plant Gaseous wastes from the wastewater reclamation system will be generated from the lime recalcination operations. The furnace exhaust gas discharged will contain' maximum of 84 pounds ~ particulate matter, 144 pounds SO , 23 pounds CO, 17 pounds 3 7 3
~
PVNGS ER-OL SANITARY AND OTHER WASTE SYSTEMS hydrocarbons, and 456 pounds NOX , daily, after treatment in a wet scrubber. Under normal plant operating conditions, the major portion of the exhaust gases will be injected into the water in the second stage solids contact clarifiers as a -source of C02 for recarbination. This will tend to reduce the dis-charges of all of the above pollutants from the maximum levels specified.
~~3. 7-4~~
PVNGS ER-OL 3.8 REPORTING OF RADIOACTIVE MATERIAL MOVEMENT The transportation of new fuel to the site and irradiated fuel from the site and the transportation of solid radioactive wastes from the site to a waste disposal site is within the scope of paragraph (G) of 10CFR51.20. The environmental effects of such transportation are as set forth in summary table S-4 of 10CFR Part 51. 3.8-1
PVNGS ER-OL 3.9 TRANSMISSION FACILITIES 3.9.1 ELECTRIC TRANSMISSION FACILITIES Information presented in ER-CP Section 3.9.1 and the FES has been updated to reflect final line routings and the addition of a transmission line from PVNGS to Devers substation in California. The descriptions of the .transmission system associated with PVNGS are updated and summarized- in this section. The transmission system associated with PVNGS is composed of
~ Project 1 PVNGS to Westwing PVNGS to Kyrene PVNGS to Saguaro ~ Project 3 Greenlee to Rio Grande ~ PVNGS to Devers Projects 1 and 3 are described in the ER-CP and FES. A final route description for the PVNGS to Westwing line and a pre-liminary route description for the PVNGS to Kyrene line were provided (as required by the FES) to the Nuclear Regulatory Commission in letters from E. E. Van Brunt, Jr., Vice President, Arizona Public Service Company, dated December 7, 1978 and December 3, 1979, respectively.
Projects 2 and 4, described in the ER-CP and FES, are no longer under consideration. Project 2, a proposed 525 kV line from the Saguaro Generating Station to a proposed Winchester Sub-station, is no longer under consideration as a result of Tucson Gas and Electric Company's sale of its 15.4% interest in PVNGS to Southern California Edison. Project 4, a proposed : 525 kV line from the Mohave Generating Station to a proposed 3.9-1
PVNGS ER-OL TRANSMISSION FACIIITIES Red Lake Canyon Substation, is no longer, under consideration as a result of the indefinite suspension of the Kaiparowits Project. Project 4 has been replaced by a proposed 525 kV line from PVNGS to Devers Substation. Information concerning the impacts of the PVNGS to Devers line is presented. in .the U.S. Department of Interior, Bureau of Land Management and U.S. Nuclear Regulatory Commission Final Environ-. ment Statement, Palo Verde-Devers 500 kV Transmission Line, February, 1979. Final route approval has yet to be issued by the Bureau of Land Management. Pursuant to an agreement between the Department. of Water and Power of the City of Los Angeles (LADWP) and the Salt River Project (SRP), LADWP will acquire from SRP a 5.7% interest in PVNGS at such time as Unit 1 is placed into commercial opera-tion. LADWP will transmit its energy over existing or currently planned transmission lines. in addition to the transmission system associated with PVNGS, another transmission line is currently planned to connect the PVNGS switchyard with the San Diego Gas & Electric (SDG&E) l Miguel substation. This line is scheduled to be in service by May, 1984, for the purposes of transmitting power purchased or sold by SDG&E from utilities in Arizona (other than APS), New Mexico, and West Texas, power exchange between APS and SDG&E, and improving the power supply to the Yuma, Arizona area. This interconnection has not been finalized, but it is anticipated that the interconnection will utilize one of the spare l'i'ne positions available in the PVNGS switchyard.
~~\ A 3.9.1.1 Transmission Route Descri tions'.~~
~~3.9.1.1.1 Project 1 PVNGS TO WESTWING A detailed'escripti'on and analysis of the final corridor alignments for the PVNGS-Westwing lines was submitted to the~~
~~3. 9-2~~
PVNGS ER-OL TRANSMISSION FACILITIES Nuclear Regulatory Commission (NRC) by Arizona Public Service Co. (APS) on December 8, 1978. (1) Approval of this analysis was reported to APS by. the NRC Environmental Projects Branch 2 on January 4, 1979. The existing Westwing Substation is situated northwest of Phoenix in Maricopa County. The Westwing transmission line route (figure 3.9-1) leaves PVNGS in an easterly direction, 2 miles from the plant the line turns northeast crossing the I Hassayampa River and Interstate Highway 10 (I-10). At mile ll the line heads north, passing to the west of the White Tank Mountains. At mile 26 the route turns east, passing to the north of the White Tank Mountains. The line crosses U.S. High-way 60, 4 miles before entering the Westwing Substation. Construction of the 44 mile long PVNGS-Westering line No. 1 commenced in January, 1979 and was complete in November 1979. Transmission system planning subsequent to the PVNGS 1,2S3 ER-CP indicates the PVNGS-Westwing line No. 2 is currently not required for transmission of power from PVNGS. However, the route and its associated environmental impacts have been analyzed for a two line corridor. Should future planning indicate a need for this previously approved line, it will be constructed in the existing right-of-way of the PVNGS-Westwing line. PVNGS TO KYRENE Changes in the PVNGS-Kyrene corridor were necessary subsequent to the ER-CP. The majority of the new corridor was originally described as an alternate in the PVNGS Transmission System Environmental Analysis. Subsequent to the change, further environmental studies on the new segments of the corridor were conducted and a detailed description and analysis of the corridor alignments were reported to the NRC on December 3, 1979. (3)
~~3. 9-3~~
PVNGS ER;OI TRANSMISSION FACILITIES The existing Kyrene Generating Station and Substation 'are located in the southern part of Tempe, Arizona, and east of South Mountain Park, in Maricopa County. ,The Kyrene trans-mission line route (figure 3.9-1) leaves PVNGS in a common corridor with the Saguaro line to the south, crossing the Gila River south of Gillespie Dam at mile 12 and Arizona Highway 85 at mile 21, 10 miles south of Buckeye. From mile 7 to mile 24.6 the corridor parallels an El Paso, Natural Gas Company (EPNG) pipeline route in a generally easterly direction. At this point the line turns in a northeasterly direction, passing through Rainbow Valley, and traversing 10 miles to an EPNG pipeline route, which it parallels for 2.1 miles (miles 34.6 to 36.7). A Tucson Electric Power Company, 345 kV line is then parallel for about 3.5 miles. The route then turns east, paralleling a United States Bureau of Reclamation (USBR) 230 kV for 4.7 miles. The line then turns southeastward and proceeds about 9.5 miles to the boundary of the Gila River Indian Reservation. The line then turns eastward, proceeding in a easterly direction for about 10 miles, where, at mile 69 it crosses I-10. The line turns northeastward 1/2 mile later and reaches Kyrene Substation at mile 74. Construction of the PVNGS-Kyrene line is scheduled to commence in April 1981, with completion anticipated by August, 1982. PVNGS TO SAGUARO The existing Saguaro Substation is on the east side of I-10 in the southern part of Pinal County. As shown, in S figure 3.9-1 the Saguaro transmission line route I leaves the PVNGS to the south in a common corridor with the Kyrene line. From mile 7 to mile 50 the corridor parallels an EPNG pipeline route in a southeasterly direction through the southern extent of the Rainbow Valley along the foothills of the Maricopa Mountains. 3.9-4
PVNGS ER-OL TRANSMISSION FACILITIES For 45 miles the line will be adjacent to the 345 kV transmission line from Westwing to Vail. The route passes east of the Table Top Mountain range and crosses the intersection of Interstate Highway 8 (I-8) and Highway 84 at mile 64. Continuing in a southeasterly direction, the route passes through the northeast corner of the Papago Indian Reservation and crosses Route 15 at mile 84. At mile 95, the Saguaro route turns east, following an existing 230 kV wood pole transmission line, passing to the north of the Silver Bell Mountains. The Saguaro route crosses the Santa Cruz River at mile 118 in the Avra Valley and I-10 south of Red Rock, then terminating at Saguaro Substation located just east of I-10. The transmission line from PVNGS to Saguaro will be 121 miles long. Construction is to start in June 1984, with completion expected in April 1986. 3.9.1.1.2 Project 3 GREENLEE TO RIO GRANDE From the existing Greenlee Substation, located approximately 2 miles northeast of Greenlee County Airport, the route (see figure 3.9-2 runs parallel to the existing Greenlee-Newman 345 kV line south-southeast 15 miles to a point 2 miles north-west of Duncan, Arizona. There it crosses U.S. Highways 70 and 75, the Gila River, and the Southern Pacific Railroad. The route continues south-southeastward, roughly paralleling the railroad for approximately 20 miles to Summit, New Mexico (mile 35). Here the line turns easterly for about 18 miles, crossing U.S. Highway 70, New Mexico road 464 and U.S. Highway 180, to where it intersects with an EPNG pipeline route at mile 53, about 6 miles north of Lordsburg. 3.9-5
PVNGS ER-OL TRANSMISSION FACILITIES Still paralleling the Greenlee-'Newman line, Project 3 follows the pipeline to the compressor station'15 miles west of. Deming, at, mile 97. It then crosses State Highway 26 and U.S. Highway 260, about, 2.5 miles north of"Deming, continuing due east to Carne at mile 122. At this point, the line turns slightly south, again paralleling 'the railroad to a point of intersection with the EPNG pipeline, at mile 157. The Project 3 line then leaves the Greenlee-Newman line, turning southeast-ward and generally paralleling the railroad, to the Rio,Grande Substation, located on the Rio Grande River near the Inter-national Boundary between the United States and Mexico, in Township 29 South, Range 4 East, New Mexico. The Greenlee to Rio Grande Line will be 195 miles long; construction is to begin in January, 1983 with completion expected in May; 1984. 3.9.1.1.3 PVNGS To Devers Information concerning the PVNGS to Devers line is contained in the U.S. Department of Interior Bureau of Land Management and U.S. Nuclear Regulatory Commission Final Environmental Statement, Palo Verde-Devers 500 kV Transmission Line, February 1979, Descriptions are presented for preferred and alternate routes. Final route approval has not been received from the Bureau of Land Management. V 3.9.1.2.1 Projects 1 and 3 Portions of each transmission line will require new access roads. Existing public and private roads will be used to the greatest extent possible for access during" construction.. The paralleling of'existing and proposed transportation and utility rights-of-way and corridors will permit, the use of existing maintenance roads thereby limiting the length of new access
~~3. 9-6~~
PVNGS ER-OL N TRANSMISSION FACILITIES roads for each system. A 12 to 14 foot wide road will be constructed along the rights-of-way in those segments in which maintenance roads do not exist. No clear cutting of trees or vegetation within the transmission right-of-way is required. Clearing of vegetation will only be required within the eon-at tower sites, at pulling sites, and within
'truction,roads, other areas where construction activities at batching plants and staging areas are actually taking place. The environmental effects of construction and operation of the PVNGS transmission system is discussed further in section'.5.
3.9.1.2.2 PVNGS to Devers Information concerning the PVNGS to Devers line is contained in the U.S. Department of Interior Bureau of Land Management and U.S. Nuclear Regulatory Commission Final Environmental Statement, Palo Verde-Devers 500 kV Transmission Line, February 1979. Descriptions are presented for preferred and alternate routes. Final route approval has not been received from the Bureau of Land Management. 3.9.1.3.1 .Project 1 PVNGS To WESTWING There will be three highway crossings on the Westwing route. The first crossing is the Buckeye-Salome Road east of Wintersburg. The second is I-10, about 1 mile east of the Hassayampa River, between Wintersburg and Buckeye. The third highway crossing is at U.S. 60, 4 miles west of the Westwing Substation. The White Tank Mountains are visible to the south and the Heiroglyphic -Mountains to the north, although the views are interrupted by transmission lines and billboards. This area provides a modified appea'rance from the road. 3.9-7
PVNGS ER-OL TRANSMISSION FACILITIES PVNGS TO KYRENE The Kyrene/Saguaro common corridor crosses old US 80 near .Gillespie Dam. The crossing is of above average scenic quality related to long views of hills and mountains in the distance, and to riparian vegetation associated with the Gila River. Nine miles east of this crossing, the Kyrene/Saguaro common corridor crosses Arizona 85. This crossing is of average scenic quality.
)he Kyrene line crosses I-10 approximately 5 miles south of Tempe. The line parallels I-10 at approximately 1-1/2 miles from this crossing into Kyrene Station. There is a modified appearance from the road in this area.
PVNGS TO SAGUARO After separating from the Kyrene line, the Saguaro line will cross two highways and a reservation road. The first crossing occurs at. the intersection of I-8 and State Highway 84 in an area characterized by clear views of the Table Top Mountains. Vegetation and topography with a background of mountain views are of above average visual quality at this crossing. The second crossing occurs on Reservation Route 15 in the Silver Reef Valley and the Papago Indian Reservation. Views of the nearby Tat Momoli and Silver Reef Mountains occur at this crossing. The high scenic quality of this area is modified by an existing transmission line and a soon to be built Westwing-Vail transmission line which will be paralleled through the area. The Saguaro line crosses I-10 at the Saguaro Generating Station. Views of the Picacho Peak and Picacho Mountains are modified at this crossing by billboards, existing transmission lines and industrial facilities. The scenic quality at this mileage point is rated as modified. 3.9-8
PVNGS ER-OL TRANSMISSION FACILITIES 3.9.1.3.2 Project 3 This route was divided into the nine segments indicated in figure 3.9-2. Each segment is discussed separately. The transmission line will follow an existing 345 kV line except through segments 8 and 9, which will modify the visual impact of this additional 345 kV line. Segment 1 and segment 2 will not intersect frequently traveled public roads. Segment 3 will have a low visual impact on the agricultural land located at Highways 7Q and 75. The presence of a second power line could also'detract from the scenic Gila River Valley. Aesthetic modification could also occur at the points where the line crosses these. The major part of segment. 4 will cover isolated desert lands. Visual interference to motorists will be almost nonexistent. However, the line does intersect U.S. Highway 70 north of Lordsburg. Segment 5 will create only slight visual effects from frequently traveled public roads. The initial 3 to 5 miles of the eastern portion is within 1 to 2 miles of the highway. However, tele-phone wires and poles immediately border this highway, already obstructing the view of the motorist. The remainder of this segment is in a very remote area beyond the view of the motorist. Segment 6 will have the greatest aesthetic impact where the line will cross State Roads 26 and 260 about 2 miles north of Deming. For the greater portion of this segment, infringement on the landscape will be minimized by the remote location of the line. Segment 7 will intersect I-10 at a point 2 miles west of the Luna-Dona Ana County line. Some visual disruption is likely to occur at this intersection point. Segment 8 will not cross frequently traveled public roads. In segment 9 the Anapra area will be subject to the highest visual modification from frequently traveled public roads. 3.9-9
PVNGS ER-OL TRANSMISSION FACILITIES 3.9.1.3.3 PVNGS To Devers Information concerning the PVNGS to Devers line is contained in the U.S. Department of Interior Bureau of Land Management and U.S. Nuclear Regulatory Commision Final Environmental Statement, Palo Verde-Devers 500 kV Transmission Line, February, 1979. Descriptions are presented for preferred and alternate routes. Final route approval has 'not been received from the Bureau of Land Management. 3.9.1.4 Structures 3.9.1.4.1 Project 1 Structures Figure 3.9-3 illustrates the structures which will be used for the Project 1 Lines. The transmission towers will be of open lattice-type construction, with dull finish. Grey shaded suspension insulators will be used on the towers. These features will tend to make'he transmission lines less visible from a distance against the desert backdrop, and the blending effect of the lattice construction and color help make the line less noticeable when visually compared with other man-made features which are more opaque, or of a more contrasting color. The self-supporting steel lattice towers average approximately 129 feet high. The towers used on straight portions of the transmission line are tangent structures, which support the conductor vertically and absorb other loads such as wind forces or ice loads on the conductor. This is the basic type of tower used on the line. Each tower will have five attachments for cables. There will be three sets of conductors (a total of at least six conductors) with each set attached to a separate point on the tower. Two statics will be suspended above the three sets of conductors. The average length of conductor span from tower to tower will vary from approximately 1280 to 1650 feet.. 3.9-10
PVNGS ER-OL TRANSMISSION FACILITIES WESTWING SUBSTATION The Arizona Public Service Company (APS) Westwing Substation is located in Maricopa County approximately 8 miles north of Sun City. The substation is on flat desert terrain and is rela-tively isolated from land use development except for scattered rural dwellings located primarily to the east. The immediate area around the substation has been landscaped. KYRENE SUBSTATION The Kyrene Generating Station and Substation, owned by the Salt River Project, is'located in the City of Tempe. The Generating Station is surrounded by a 1/4 mile radius buffer zone on the north and east sides. Within the buffer zone, the City of Tempe has constructed a municipal golf course. Beyond the buffer zone, to the north and east, tracts of single family dwellings have been constructed. Substation expansion will be into agricultural land to the south and/or west of the existing substation. In either case, the substation will be adjacent to Elliott Road, a paved east-west road. The substation will be visible from Elliott and also from Kyrene and Rural Roads, which are paved, north-south roads. The substation expansion will also be visible from I-10 which is approximately two miles to the west of the existing substation. SAGUARO SUBSTATION The Saguaro Generating Station and Substation is owned by APS. The station is located on the east side of I-10, approximately 3 miles northeast of the Marana Airport and 2.5 miles southeast of Red Rock in Pinal County. The substation is surrounded by vacant desert terrain. 3.9-11
PVNGS ER-OL TRANSMISSION FACILITIES 3.9.1.4.2 Project 3 Structures Transmission line towers used in Project 3 will be of 345 kV modified wooden H-frame construction, as shown in figure 3.9-4. The towers will use Douglas fir poles, and will be full length treated with pentachlorophenol. Towers will be located and sized to provide a minimum final ground clearance of 30 feet to any conductor at 60F, resulting in a typical tower approximately 70 feet high and 47 feet wide. When ground terrain requires, or at road crossings or other lines, taller towers may have to be used, although the width will remain the same. There will normally be 6.6 struc-tures per mile, with an average span of 800 feet. 3.9.1.4.2.1 Greenlee Substation. Greenlee Substation is a compensation point in Tucson Gas & Electric Company lines from San Juan Power Station to Vail, Arizona. It is located 2 miles northeast of Greenlee County Airport and is situated 1 mile south of the nearest, paved road. The substation is not visible from the airport or any public road in the area. Project 3 will require the addition of one 345 kV circuit breaker and a shunt compensating reactor to the Greenlee Substation. No increase in fenced area is anticipated. 3.9.1.4.2.2 Rio Grande Substation. The Rio Grande Sub-station is a part of Rio Grande Power Station. The station is located on the Rio Grande River, near the intersection of the Texas, New Mexico, and Mexico borders. The addition of the 345 kV terminal to the Rio Grande switchyard will be accomplished within the fenced site and will be difficult to distinguish in the panorama of generating station facilities already present on the site. 3.9-12
PVNGS*ER-OL TRANSMISSION FACILITIES 3.9.1.4.3 PVNGS To Devers Structure Information concerning the PVNGS to Devers line is contained in the U.S. Department of Interior Bureau of Land Management and U.S. Nuclear Regulatory Commission Final Environmental Statement, Palo Verde-Devers 500 kV Transmission Line, February, 1979. Descriptions are presented for preferred and laternate routes. Final route approval has not been received from the Bureau of Land Management. 3.9.2 PVNGS WASTEWATER CONVEYANCE SYSTEM Information presented in ER-CP Section 3.9.2 and the FES has been updated to reflect final pipeline routing. Description of the wastewater conveyance system is updated and summarized in this section. As shown in figure 3.9-5, the wastewater conveyance system route extends from the City of Phoenix 91st Avenue Sewage Treatment Plant approximately 36.5 miles to the PVNGS site. A 114-inch diameter pipeline leaves the 91st Avenue Sewage Treatment Plant, conveying treated wastewater effluent by gravity flow for about 6 miles, where it is reduced to a 96-inch diameter. The 96-inch diameter pipeline continues gravity flow for about 4 miles to a turnout for delivery of effluent to the Buckeye Irrigation Company (BIC) canal. From 1 the turnout, the 96-inch pipeline proceeds by gravity flow generally parallel to the BIC canal for about 18.5 miles to a pumping station near the Hassayampa River. The remaining 8 miles to the PVNGS site are traversed by a 66-inch diameter pipeline. The entire 36.5 miles of pipeline will be underground with above ground structures limited to manholes approximately each 1/2 mile and vents at high points, about 6 feet above grade; these are anticipated to have minimal visual impact. A 50 foot wide permanent access right-of-way will be required for the entire length of the pipeline. 3.9-13
PVNGS ER-OL TRANSMISSION FACILITIES The majority of the wastewater conveyance pipeline passes ~ through agricultural land. The remaining areas are scattered residential, mostly associated with the agricultural activities, and some scattered light industry. There are no existing recreational areas along the route. After construction the right-of-way will be regraded, and topsoil will be replaced in agricultural areas for future cultivation. Table 3.9-1 lists the land types and the distances associated with the wastewater conveyance pipeline route. Table 3.9-1 LAND TYPE ADJACENT TO WASTEWATER CONVEYANCE PIPELINE Land Use Types Route Open land 12.5 miles Agricultural land 19.0 miles Residential areas 3.5 miles Industrial areas 0.5 mile Other 1.0 mile 3.
~~9.3 REFERENCES~~
Letter dated December 7, 1978 from E. E. Van Brunt, Jr., Arizona Public Service Company, Vice President, Nuclear Projects to Dr. Robert A. Gilbert, Project Manager, Environmental Projects Branch 3, U.S. Nuclear Regula-tory Commission.
~~2. Letter dated January 4, 1979 from W. H. Regan, Jr.,~~
~~Chief, Environmental Projects Branch 2, U.S. Nuclear Regulatory Commission to E. E. Van Brunt, Jr.~~
~~3. Letter dated December 3, 1979 from E. E. Van Brunt, Jr.,~~
Arizona Public Service Company, Vice President, Nuclear Projects to Dr. Robert A. Gilbert, Project Manager, Environmental Projects Branch 3, U.S. Nuclear Regulatory Commission. 3.9-14
PVNGS ER-OL TRANSMISSION FACILITIES Final Environmental Statement Palo Verde-Devers 500 kV Transmission Line, United States Department of the Interior (Bureau of Land Management) and the Nuclear Regulatory Commission, February, 1979. 3.9-15
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r PVNGS ER-OL APPENDIX 3A RESPONSES TO NRC UESTIONS
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ML17296A542

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9.3 REFERENCES

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