Text

Final Safety Analysis Report Update, Revision 32, Chapter 11 - Radioactive Waste Management and Radiation Protection - Tables
	ML16120A610
Person / Time
Site:	Palisades
Issue date:	04/18/2016
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16120A302	List: ML16120A321; ML16120A325; ML16120A326; ML16120A327; ML16120A344; ML16120A345; ML16120A347; ML16120A359; ML16120A360; ML16120A361; ML16120A362; ML16120A379; ML16120A380; ML16120A381; ML16120A382; ML16120A415; ML16120A416; ML16120A417; ML16120A419; ML16120A420; ML16120A421; ML16120A571; ML16120A573; ML16120A574; ML16120A575; ML16120A588; ML16120A589; ML16120A590; ML16120A591; ML16120A596; ML16120A597; ML16120A598; ML16120A599; ML16120A602; ML16120A603; ML16120A604; ML16120A608; ML16120A609; ML16120A610; ML16123A314; ML16123A315; ML16123A316; ML16123A320; ML16123A321; ML16123A326; ML16123A328; ML16123A329; ML16126A109; PNP 2016-015, Final Safety Analysis Report Update, Revision 32, Table of Contents;
References
	PNP 2016-015
	Download: ML16120A610 (40)
	v • d • e

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 1 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel)

Normal Activity Normal (Microcuries/

(Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter)

Centimeter)(a)

(Curies)

(a)

Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.

(b)

Total value consisting of summation of Sr-89 and Sr-90.

H-3 2.80 0.21 860 65 Br-84 4.66 x 10

-2 13.4 Kr-85(m) 1.50 0.030 432 8.6 Kr-85 2.34 3.52 x 10

-4 674 0.10 Kr-87 0.81 0.037 233 10.6 Kr-88 2.48 0.060 714 17.3 Rb-88 2.44 0.122 702 35.1 Rb-89 6.10 x 10

-2 3.05 x 10

-4 0.18 9.0 x 10

-4 Sr-89 5.33 x 10

-3) 2.28 x 10

-5(b) 1.53 )

7.0 x 10

-3(b)

Sr-90 1.50 x 10

-4) 4.3 x 10

-2)

Y-90 5.77 x 10

-4 0.17 Sr-91 3.70 x 10

-3 8.01 x 10

-5 1.06 0.023 Y-91(m) 0.24 1.76 x 10

-3 68.4 0.50 Mo-99 2.26 3.70 x 10

-5 649 0.010 Te-129 2.72 x 10

-2 7.84 I-129 5.66 x 10

-8 1.63 x 10

-5 I-131 4.40 0.114 1,266 32.8 Te-132 0.36 3.22 x 10

-5 102 9.1 x 10

-3

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 2 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel)

Normal Activity Normal (Microcuries/

(Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter)

Centimeter)(a)

(Curies)

(a)

Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.

(b)

Data for nuclides with less than 15 minute half-lives is not documented.

I-132 1.13 0.095 324 27.2 I-133 6.38 0.141 1,830 40.4 Xe-133 255 0.472 6.47 x 10 4

135.7 Cs-134 1.42 1.35 x 10

-5 725 6.9 x 10

-3 Te-134 2.63 x 10

-2 7.55 I-134 0.64 0.134 184 38.5 I-135 2.78 0.142 801 40.9 Xe-135 6.75 0.090 1,943 25.9 Cs-136 0.15 1.90 x 10

-5 43.4 5.5 x 10

-3 Cs-137 10.6 2.32 x 10

-5 3,064 6.7 x 10

-3 Xe-138 0.36 (b) 103 (b)

Cs-138 0.69 0.059 198 16.9 Ba-140 6.78 x 10

-3 5.09 x 10

-4 1.95 0.15 La-140 6.52 x 10

-3 6.97 x 10

-4 1.88 0.20 Co-60 1.1 x 10

-3 2.78 x 10

-5 0.37 9.4 x 10

-3 Fe-59 7.7 x 10

-6 1.41 x 10

-5 2.6 x 10

-3 4.8 x 10

-3 Co-58 7.9 x 10

-3 4.28 x 10

-4 2.67 0.14 Mn-56 2.3 x 10

-2 1.55 x 10

-4 7.77 0.052

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 3 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel)

Normal Activity Normal (Microcuries/

(Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter)

Centimeter)(a)

(Curies)

Mn-54 2.0 x 10

-5 2.70 x 10

-5 6.8 x 10

-3 9.2 x 10

-3 Cr-51 2.4 x 10

-3 5.35 x 10

-4 0.81 0.18 Zr-95 1.9 x 10

-5 1.08 x 10

-5 6.4 x 10

-3 3.6 x 10

-3 Total 275.7 1.708 79,663 497 (a)

Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-2 RADIATION PROTECTION Revision 21 Page 1 of 2 RADIOACTIVE WASTE QUANTITIES OF SIGNIFICANT ACTIVITY Quantity/Year-Liquid Waste Sources Gallons Assumptions Chemical and Volume 69,500 Start-up after refueling Control System 900 Cold shutdown Day 1 37,200 Start-up from cold condition Day 1 13,200 Hot shutdown(a) Day 50 1,200 Start-up from hot condition Day 50 17,400 Hot shutdown(a) Day 140 1,700 Start-up from hot condition Day 140 32,300 Hot shutdown (a) Day 230 2,000 Start-up from hot condition Day 230 2,200 Cold shutdown Day 240 104,300 Start-up from cold condition Day 240 68,900 Hot shutdown(a) Day 270 2,300 Start-up from hot condition Day 270 17,500 cold shutdown to refuel 216,000 Boron reduction for cycle shim bleed Total 586,600 Primary System Drain 1,500 Primary coolant pump seal leakage at Tank 1 gpd per pump for four pumps 1,000 Safety injection check valve leakage 64,900 Drain primary system for maintenance at Day 240 13,800 Drain primary system for refueling 21,300 Drain refueling shield Total 102,500 (a)

Hot shutdown quantities are based on maintaining the shutdown margin during xenon buildup by boron dilution and on Plant start-up eight hours after shutdown during the xenon buildup peak.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-2 RADIATION PROTECTION Revision 21 Page 2 of 2 RADIOACTIVE WASTE QUANTITIES OF SIGNIFICANT ACTIVITY Quantity/Year-Liquid Waste Sources Gallons Assumptions Equipment Drain Tank 11,400 Coolant charging pump seal leakage at 31 gpd maximum leakage 7,000 Spent fuel pool overflow 3,900 Spent resin tank overflow from resin flushing - 260 ft 3/year of resin replacement at 2 ft 3/ft 3 resin 1,900 Demineralizers drain from resin charging - 260 ft 3/year of resin replacement at 1 ft 3/ft 3 resin Total 24,200 Radiochemistry Lab 11,000 12 samples per day at 2.5 gallons Drain Tank per sample Total Liquid Waste of Significant Activity 724,300 Quantity/Year-Gaseous Waste Sources ft 3

Assumptions Degas of Primary System 2,418 Degas to 5 cm 3/kg prior to 3 cold shutdowns including gas in volume control tank Off-Gas Liquid Waste 867 See start-up and shutdown schedule From Shutdowns and above Start-Ups Off-Gas for Chemical 1,011 Boron dilution generates 216,000 Shim Reduction gallons liquid waste with 35 cm 3/kg gas content Off-Gas Liquid Drained 243 for Refueling Maintenance and Miscellaneous Total Gaseous Waste of Significant Activity 4,539

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 1 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

1.

CLEAN WASTE RECEIVER TANKS (T-64A, B, C, D)

Number 4

Material Type 304 Stainless Steel Capacity (Each) 50,000 gal (7,000 ft3)

Design Pressure 5 psig (Vapor Space)

Design Temperature 103°F Code API 620

2.

PRIMARY SYSTEM DRAIN TANK (T-74)

Number 1

Material Type 304 Stainless Steel Capacity 900 gal Design Pressure 50 psig Design Temperature 250°F Code ASME B&PV Code,Section III, Class C

3.

EQUIPMENT DRAIN TANK (T-80)

Number 1

Material Type 304 Stainless Steel Capacity 550 gal Design Pressure 50 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII

4.

SPENT RESIN STORAGE TANK (T-69)

Number 1

Material Type 304 Stainless Steel Capacity 3,000 gal (400 ft3)

Design Pressure 125 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class C

5.

CONTROLLED CHEM LAB DRAIN TANK (T-76)

Number 1 Divided Into 2 Compartments Material Type 304 Stainless Steel Capacity 900 gal (Total)

Design Pressure 50 psig Design Temperature 150°F Code ASME B&PV Code,Section VII

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 2 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

6.

TREATED WASTE MONITOR TANKS (T-66A, B)

Number 2

Material Carbon Steel Internal Coating Baked Phenolic, 6-8 Mils Capacity 5,500 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII

7.

DIRTY WASTE DRAIN TANK (T-60)

Number 1 Divided Into 2 Compartments Material Carbon Steel Capacity 3,800 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII Requirements

8.

FILTERED WATER MONITORING TANKS (T-63)

Number 1 With 2 Compartments Material Carbon Steel Internal Coating Baked Phenolic, 6-8 Mils Capacity 5,500 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII

9.

WASTE GAS SURGE TANK (T-67)

Number 1

Material Carbon Steel Capacity 550 gal (80 ft3)

Design Pressure 20 psig Design Temperature 150°F Code ASME B&PV Code,Section III, Class C

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 3 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

10.

WASTE GAS DECAY TANKS (T-68A, B, C)

Number 3

Material Carbon Steel Capacity 800 gal (100 ft3)

Design Pressure 120 psig Design Temperature 550°F Code ASME B&PV Code,Section III, Class C

11.

LAUNDRY DRAIN TANK (T-70)

Number 1 Divided Into 2 Compartments Material Carbon Steel Capacity 1,000 gal (Total)

Design Pressure 15 psig Design Temperature 150°F Code ASME P&PV Code,Section VIII

12.

VACUUM DEGASIFIER

a.

Tank (T-57)

Number 1

Performance Handle Solution With 0-50 Std cm3 H2 (kg of Liquid Waste. Reduced H2 Concentration to 1/40 of Influent Concentration)

Design Flow 0-160 gpm Design Pressure 75 psig & 30" Hg Design Temperature 200°F Material Stainless steel Code ASME B&PV Code,Section III, Class C

b.

Vacuum Pumps (C-51A, B)

Number 2

Capacity 28 scfm @ 28" Hg Type Rotary, Water-Sealed, Water-Lubricated with Closed Cooling Loop Motor 3 hp Material Stainless steel

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 4 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

13.

RADWASTE DEMINERALIZER

a.

Demineralizer Tanks (T-55A, B, C)

Number 3

Material of Tank Stainless Steel Flow Rate (Each) 48 gpm (Rated), 100 gpm (Max)

Unit Flow Rate (at Ratings) 5.0 gpm/ft2 Resin Volume (Each) 32 ft3 Resin Type Equivalent Capacity Mixture of Nuclear Grade Cation and Anion Design Pressure 125 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

b.

Clean Resin Transfer Tank (T-61)

Number 1

Material PVC Lined Carbon Steel Capacity 32 ft3 Design Pressure 125 psig Design Temperature 125°F Code ASME B&PV Code,Section VIII

14.

CLEAN WASTE FILTERS (F-57A, B, C)

Type Cartridge Type With Replaceable Elements Number 3

Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 150 Micron Flow Rate 100 gpm Design Pressure 125 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 5 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

15.

EQUIPMENT DRAIN FILTER (F-56)

Number Cartridge Type with Replaceable Elements Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 25 Microns Design Pressure 125 psig Design Temperature 212°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

16.

DIRTY WASTE FILTER (F-53)

Type Cartridge Type With Replaceable Elements Number 1

Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 200 Microns Flow Rate 75 gpm Design Pressure 100 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

17.

LAUNDRY DRAIN FILTER (F-55)

Type Cartridge Type With Replaceable Elements Number 1

Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 25 Microns Flow Rate 20 gpm Design Pressure 100 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 6 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

18.

PRIMARY SYSTEM DRAIN TANKS PUMPS (T-71A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 75 gpm Head 80 ft TDH Material Type 316 Stainless Steel Motor 5 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

19.

DEGASIFIER PUMPS (P-68A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 160 gpm Head 190 ft TDH Material Type 316 Stainless Steel Motor 20 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

20.

EQUIPMENT DRAIN TANK PUMPS (P-75A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 100 gpm Head 266 ft TDH Material Type 316 Stainless Steel Motor 25 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

21.

CONTROLLED CHEM LAB DRAIN PUMPS (P-61A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 10 gpm Head 158 ft TDH Material Type 316 Stainless Steel Motor 7.5 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 7 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

22.

RECEIVER TANK (CWRT) PUMPS (P-69A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 100 gpm Head 200 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt

23.

RECEIVER TANK (CWRT) CIRCULATING PUMP (P-70)

Type Horizontal Centrifugal With Mechanical Seals Number 1

Capacity (Each) 250 gpm Head 121 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

24.

TREATED WASTE MONITOR PUMPS (P-58A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 150 gpm Head 140 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

25.

SAFETY INJECTION ROOM SUMP PUMPS (P-72A, B AND P-73A, B)

Type Vertical Centrifugal Number 4 (2 Sets With 2 Pumps per Set)

Capacity (Each) 25 gpm Head 35 ft TDH Material Stainless Steel Motor 1 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA,

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 8 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

26.

DIRTY WASTE DRAIN TANK PUMPS (P-60A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 75 gpm Head 160 ft TDH Material Type 316 Stainless Steel Motor 10 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute FILTERED WASTE MONITOR PUMP (P-63)

Type Horizontal Centrifugal With Mechanical Seals Number 1

Capacity (Each) 75 gpm Head 150 ft TDH Material Type 316 Stainless Steel Motor 10 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

28.

WASTE GAS COMPRESSORS (C-50A, B)

a.

Compressor Number 2

Type Single Head, Single Stage Diaphragm Type Capacity (Each) 2.35 scfm at 14.7 psia Suction, 0.44 scfm at 7.5 psia Suction Discharge Pressure 100 psig at Maximum Delivery Material Stainless Steel Motor 2 hp, 3 Phase, 60 Hertz, 460 Volt, TEFC

b.

Aftercoolers Number 2

Type Shell and Tube With Moisture Separator and Drain Trap Material Tube Side (Gas) Stainless Steel, Shell Side (Water) Carbon Steel

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 9 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

29.

WASTE GAS COMPRESSOR (C-54)

a.

Compressor Number 1

Type Diaphragm Type Capacity (Each) 5 scfm Avg Between Suction Pressures of 7.5 and 15.0 psia Discharge Pressure 100 psig Material Motor 7.5

b.

Aftercoolers Number 1

30.

PIPING, FITTING AND VALVES

a.

Liquid Systems Material Stainless Steel Design Pressure Floor Drains - Atmosphere, Process -

50 psig Joints, 2" and Larger Butt Weld 1-1/2" and Smaller 2,000 lb SW Valves, 2" and Larger Stainless Steel, Butt Weld Ends, 150 lb 1-1/2" and Smaller Stainless Steel, 2,000 lb SW Ends, 150 lb Butterfly Valves Stainless Steel, Flangeless, 150 lb Plug Vales Stainless steel, FF Flanged, 150 lb Code ASA B31.1, Code for Pressure Piping, Including Applicable Nuclear Code Cases, ASA B16.5 Radiography All Butt Weld in Nuclear Service Systems Rated for Higher Than 50 psig and 212°F Are Radiographed 100. All Butt Welds in Nuclear Systems Rated for Less Than 50 psig and 212°F Are Radiographed 10%

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 10 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

b.

Gaseous Systems Material Carbon Steel Design Pressure 100 psig Joints, 2" and Larger Butt Weld 1-1/2" and Smaller 3,000 lb SW Valves, 2" and Larger Carbon Steel, 150 lb BW 1-1/2" and Smaller Carbon Steel, 600 lb, 3,000 lb SW Butterfly Carbon Steel, 150 lb, FF Flanged Plug Ductile Iron, 150 lb, FF Flanged Code ASA B31.1, Code for Pressure Piping, Including Applicable Nuclear Code Cases, ASA B16.5 Radiography All Welds Are 100% Radiographed

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 1 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

1.

CLEAN WASTE HOLDUP TANK (T-85)

Number 1

Material of Tank SA240 Type 304 SS Capacity 5,000 gal Design Pressure Atm Design Temperature 212°F Code API-620, 1970 Exam ASME B&PV Code,Section III, 1971

2.

CLEAN WASTE TRANSFER PUMP (P-94)

Type Gould 3196 Number 1

Capacity 80 gpm Head 85 ft Material Stainless Steel Motor 5 hp Code ASME B&PV Code,Section III, Class 3, 1971

3.

CLEAN AND DIRTY WASTE EVAPORATORS (M-59A, B)

a.

Evaporator Vessel Number 2

Material 316 SS Capacity 1,600 gal Design Pressure 15 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class 3, 1971

b.

Recirculation Pump Type Gould 3196 - 3 x 4-13 Number 4

Capacity 200 gpm Head 30 ft Material 316 SS Motor 5 hp, 3 Phase, 60 Hertz, 460 Volt Code ASME B&PV Code,Section III, Class 3, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 2 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

c.

Distillate Pump Type Gould 3196 - 1 x 1-1/2-6 Number 4

Capacity 25 gpm Head 130 ft Material 316 SS Motor 5 hp Code ASME B&PV Code,Section III, Class 3, 1971

d.

Concentrate Pump Type Gould 3196 - 1 x 1-1/2-6 Number 4

Capacity 25 gpm Head 100 ft Material 316 SS Motor 3 hp Code ASME B&PV Code,Section III, Class 3, 1971

e.

Vacuum Pump Type Nash Number 4

Capacity 48 cfm @ 20" vacuum Head 2 psig Material 316 SS Motor 3 hp Code N/A

4.

CLEAN WASTE DISTILLATE TANK (T-86)

Number 1

Material SA240 Type 304 SS Capacity 5,000 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 3 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

5.

CLEAN WASTE DISTILLATE PUMP (P-97A, B)

Type Gould 3196 Number 2

Capacity 80 gpm Head 85 ft Material 316 SS Motor 5 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

6.

CLEAN (MISCELLANEOUS) WASTE CONCENTRATE TANKS (T-94, T-95)

Number 2

Material SA240 Type 304 SS Capacity 1,500 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971

7.

MISCELLANEOUS WASTE FILTER (F-59)

Type Cartridge Type With Replaceable Elements Number 1

Material, Container 304 SS Material, Filter Media Epoxy Impregnated Cellulose Filter Media Rating 150 Micron*

Flow Rate 30 gpm Design Pressure 50 psig Design Temperature 212°F Code ASME B&PV Code,Section III, Class 3, 1971

May be in service with element removed.

8.

CLEAN (MISCELLANEOUS) WASTE CONCENTRATE PUMPS (P-95A, B)

Type Gould 3196, 1 x 2-8 Number 2

Capacity 30 gpm Head 75 ft Material 316 SS Motor 3 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 4 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

9.

POLISHING (MISCELLANEOUS WASTE) DEMINERALIZERS (T-88, T-89A, B)

Number 3

Material of Tank 304 SS Flow Rate 50 gpm (Rated), 100 gpm (Max)

Unit Flow Rate (At Max) 10 gpm/ft2 Resin Volume 32 ft3 Resin Type Equivalent Capacity Mixture of Nuclear Grade Cation and Anion

10. MISCELLANEOUS WASTE HOLDUP TANKS (T-92A, B, C)

Number 3

Material SA240 Type 304 SS Capacity 20,000 gal Design Pressure Atm Design Temperature 212°F Code API-620, 1970 Exam ASME B&PV Code,Section III, 1971

11. MISCELLANEOUS WASTE TRANSFER PUMPS (P-92A, B)

Type Gould 3196, 2 x 3-13 Number 2

Capacity 80 gpm Head 120 ft Material 316 SS Motor 10 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

12. MISCELLANEOUS WASTE DISTILLATE TANK (T-87)

Number 1

Material SA240 Type 304 SS Capacity 8,000 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 5 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

13. MISCELLANEOUS WASTE DISTILLATE PUMPS (P-89A, B)

Type Gould 3196, 1-1/2 x 3-6 Number 2

Material 316 SS Capacity 80 gpm Head 110 ft Motor 7-1/2 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

14. RADWASTE SPENT RESIN STORAGE TANK (T-100)

Number 1

Material 304 SS Capacity 200 ft3 Design Pressure 125 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class 3, 1971

15. WASTE GAS DECAY TANKS (T-101A, B, C)

Number 3

Material Carbon Steel Capacity 225 ft3 Design Pressure 120 psig Design Temperature 550°F Code ASME B&PV Code,Section III, Class 3, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 6 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

16. PIPING, FITTINGS AND VALVES

a.

Liquid Radwaste System (Process)

Material Stainless Steel Design Pressure 125 psig and 150 psig Fittings 2-1/2" and Larger 150 lb Thickness To Match Pipe Butt Weld Ends 2-1/2" and Smaller 3,000 lb Socket Weld Valves 2-1/2" and Larger 150 lb Butt Weld Ends 2" and Smaller 150 lb Socket Weld Ends Joints 2-1/2" and Larger Butt Weld Ends 2" and Smaller Socket Weld Ends Code ASME B&PV Code,Section III, Nuclear Power Plant Components, Nuclear Class 3, 1971, per AEC Safety Guide 26, March 27, 1972

b.

Atmospheric Radwaste Drainage Piping Material Stainless Steel Design Pressure Atmospheric Fittings 8" and Smaller Butt Weld Ends Joints 8" and Smaller Butt Weld Code ANSI B31.1.0 - 1967 Power Piping

c.

Gaseous Radwaste System (Process)

Material Carbon Steel Design Pressure 150 psig Fittings 2-1/2" and Larger 150 lb Thickness To Match Pipe Butt Weld Ends 2" and Smaller 3,000 lb Socket Weld Ends Valves 2-1/2" and Larger 150 lb Butt Weld Ends 2" and Smaller 600 lb Socket Weld Ends Joints 2-1/2" and Larger Butt Weld Ends 2" and Smaller Socket Weld Code ASME B&PV Code,Section III, Nuclear Power Plant Components, Nuclear Class 3, 1971, per AEC Safety Guide 26, March 23, 1972

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 7 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

17. PRIMARY SYSTEM MAKEUP STORAGE TANK (T-90)

Number 1

Material Carbon Steel Capacity 200,000 gal Design Pressure Atmospheric Code API-650, 1970

18. UTILITY WATER STORAGE TANK (T-91)

Number 1

Material Carbon Steel Capacity 75,000 gal Design Pressure Atmospheric Code API-650, 1970

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-5 RADIATION PROTECTION Revision 21 Page 1 of 1 PRIMARY SYSTEM DRAIN TANK Letdown and Regenerative HX Drain Shutdown Cooling Header Relief SI Tanks Leakage PCS Loop Drains Quench Tank Drains Flange Leak Detector Drain Controlled Bleed-Off Relief PCS Pump Seal Leakage

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-6 RADIATION PROTECTION Revision 30 Page 1 of 1 EQUIPMENT DRAIN TANK Spent Resin Storage Tanks Primary Coolant Sample Drain Clean Resin Transfer Tank Radwaste Demineralizer Drains Fuel Pool Overflow Fuel Pool HX Drains Fuel Pool Demineralizer Drains Fuel Pool Filter Drains Blowdown Drain Tank HPI Header Relief SIRW Tank Overflow Drain SIRW Tank HX Drain SI Tank Sample Flush Waste Gas Surge Tank Drain Chemical Addition Tank Drain Charging Pump Relief and Drains VCT Drain Purification Filters Drain

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-7 RADIATION PROTECTION Revision 21 Page 1 of 1 DIRTY WASTE DRAIN TANK Radwaste Addition Area Sample Sink Drains Clean Resin Transfer Tank Drains Pump Leak-Offs Auxiliary Building Floor Drains Decontamination Pit Drains Cask Washdown Area Drains Controlled Chemical Laboratory Drain Tank Drains Component Cooling Surge Tank Drain Boric Acid Batching Tank Drain Boric Acid Filter Drains Treated Waste Monitor Tanks VCT Relief Vacuum Degasifier Relief Turbine Building Sump Pump Discharge Containment Sump Drains Shutdown Cooling HX Drains Spent Resin Storage Tank (T-100)

Primary System Makeup and Utility Water Tanks Overflow Laundry Drain Tank Drains Auxiliary Building Sump Pumps

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-8 RADIATION PROTECTION Revision 26 Page 1 of 2 LIQUID RADWASTE Clean Liquid Waste Activities (Ci/cm 3)*

Dirty Liquid Waste Activities (Ci/cm 3)*

After After After Processiong After After As Received Processing Processing Through Processing Processing in Receiver After 30 Through Two Through Polishing As Received Through Through Isotope Half-Life Tanks Days' Decay Demineralizers Evaporator Demineralizer in Drain Tank Evaporator Demineralizers Fission Products Br-84 32m 1.25 x 10

-2 (a)

(a)

(a) 4.66 x 10

-4 4.66 x 10

-8 (a)

Rb-88 18m 6.61 x 10

-1 (a)

(a)

(a) 2.44 x 10

-2 2.44 x 10

-6 2.44 x 10

-8 Rb-89 15m 1.66 x 10

-2 (a)

(a)

(a) 6.10 x 10

-4 6.10 x 10

-8 (a)

SR-89 54d 1.44 x 10

-3 9.80 x 10

-4 9.80 x 10

-6 (a)

(a) 5.33 x 10

-5 (a)

(a)

Sr-90 28y 4.00 x 10

-5 4.00 x 10

-7 (a)

(a) 1.50 x 10

-6 (a)

(a)

Y-90 64h 1.55 x 10

-4 6.51 x 10

-8 (a)

(a)

(a) 5.77 x 10

-6 (a)

(a)

Sr-91 9.7h 1.00 x 10

-3 (a)

(a)

(a) 3.70 x 10

-5 (a)

(a)

Y-91 58d 6.50 x 10

-2 4.53 x 10

-4 4.53 x 10

-8 (a) 2.40 x 10

-3 2.40 x 10

-7 (a)

Mo-99 67h 6.12 x 10

-1 3.67 x 10

-4 3.67 x 10

-6 (a)

(a) 2.26 x 10

-2 2.26 x 10

-6 2.26 x 10

-8 Te-129 33d 7.36 x 10

-3 3.93 x 10

-5 (a)

(a) 2.72 x 10

-4 2.72 x 10

-8 (a)

I-129 1.7 x 10 7y 1.52 x 10

-8 1.52 x 10

-8 (a)

(a)

I-131 8.0d 1.18 8.87 x 10

-2 8.87 x 10

-4 8.87 x 10

-7 8.87 x 10

-8 4.40 x 10

-2 4.40 x 10

-5 4.40 x 10

-7 Te-132 77h 9.75 x 10

-2 1.46 x 10

-4 1.46 x 10

-6 (a)

(a) 3.60 x 10

-3 3.60 x 10

-7 (a)

I-132 2.3h 3.05 x 10

-1 (a)

(a)

(a) 1.13 x 10

-2 1.13 x 10

-5 1.13 x 10

-7 I-133 21h 1.73 (a)

(a)

(a) 6.38 x 10

-2 6.38 x 10

-5 6.38 x 10

-7 Cs-134 2.3y 3.84 x 10

-1 3.78 x 10

-1 3.70 x 10

-3 3.78 x 10

-7 3.78 x 10

-8 1.42 x 10

-2 1.42 x 10

-6 1.42 x 10

-8 Te-134 44m 7.12 x 10

-3 (a)

(a)

(a) 2.63 x 10

-4 2.63 x 10

-8 (a)

I-134 52m 1.73 x 10

-1 (a)

(a)

(a) 6.40 x 10

-3 6.40 x 10

-5 6.40 x 10

-7 I-135 6.7h 7.53 x 10

-1 (a)

(a)

(a) 2.78 x 10

-2 2.78 x 10

-6 2.78 x 10

-8 Cs-136 13d 4.06 x 10

-2 8.20 x 10

-3 8.20 x 10

-5 (a)

(a) 1.50 x 10

-3 1.50 x 10

-7 (a)

Cs-137 30y 2.87 2.87 2.87 x 10

-2 2.87 x 10

-6 2.87 x 10

-7 1.06 x 10

-1 1.06 x 10

-5 1.06 x 10

-7 Cs-138 32m 1.87 x 10

-1 (a)

(a)

(a) 6.90 x 10

-3 6.90 x 10

-7 (a)

Ba-140 12.8d 1.84 x 10

-3 3.65 x 10

-4 3.65 x 10

-6 (a)

(a) 6.78 x 10

-5 (a)

(a)

La-140 40.2h 1.27 x 10

-3 (a)

(a)

(a) 6.52 x 10

-5 (a)

(a)

Corrosion Products Cr-51 27d 6.50 x 10

-4 3.02 x 10

-6 (a)

(a) 2.4 x 10

-5 (a)

(a)

Mn-54 300d 5.22 x 10

-6 4.87 x 10

-8 (a)

(a) 2.0 x 10

-7 (a)

(a)

Mn-56 2.58h 6.00 x 10

-3 (a)

(a)

(a) 2.3 x 10

-4 2.3 x 10

-8 (a)

Co-58 71d 2.07 x 10

-3 1.55 x 10

-5 (a)

(a) 7.9 x 10

-5 (a)

(a)

Fe-59 45d 2.02 x 10

-6 1.27 x 10

-8 (a)

(a) 7.7 x 10

-8 (a)

(a)

Co-60 5.2y 2.98 x 10

-4 2.95 x 10

-6 (a)

(a) 1.1 x 10

-5 (a)

(a)

Zr-95 65d 4.96 x 10

-6 3.61 x 10

-8 (a)

(a) 1.9 x 10

-7 (a)

(a)

(a) Less Than 10

-8

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-8 RADIATION PROTECTION Revision 26 Page 2 of 2 LIQUID RADWASTE Assumptions:

Factor of 10 reductionin each demineralizer for all isotopes except tritium.

10 3 reduction for iodine in evaporator.

10 4 reduction for all other isotopes except tritium.

19% of clean waste is direct from primary system.

81% of clean waste is from Chemical and Volume JControl System and passes through one ion exchanger prior to entering clean waste receiver tanks.

No holdup period assumed in Miscellaneous Waste Holdup Tank.

1% defective fuel.

Dirty waste activity is 1% of primary coolant activity.

The above information pertaining to isotopic activities are based on decontamination factors (DF) which were provided as part of the initial safety analysis or added as changes to the systems were made. Operating experience has demonstrated that the reactor coolant activity levels are much lower than the activity levels assumed in the radwaste system design. The ODCM provides information pertaining to the monitoring of waste streams and ensures the resultant offsite doses are in compliance with current regulatory requirements. The above information is considered historical.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-9 RADIATION PROTECTION Revision 21 Page 1 of 1 MAXIMUM CALCULATED TRITIUM RELEASE DUE TO EVAPORATION FROM REFUELING CAVITY AND SPENT FUEL POOL Conc in Release From Conc in Release From Spent Fuel Spent Fuel Total Yr of Contain Bldg Contain Bldg Bldg Bldg Release Oper (Ci/cm3)

(Ci/Yr)

(Ci/cm3)

(Ci/Yr)

(Ci/Yr) 5 1.1 x 10-13 18 8.5 x 10-14 13 31 10 2.1 x 10-13 35 2.2 x 10-13 33 68 15 3.0 x 10-13 50 3.6 x 10-13 53 103 20 3.8 x 10-13 63 4.9 x 10-13 72 135 25 4.5 x 10-13 75 6.1 x 10-13 90 165 30 5.1 x 10-13 85 7.1 x 10-13 105 190 35 5.6 x 10-13 93 8.0 x 10-13 118 211 40 6.0 x 10-13 100 8.6 x 10-13 127 227

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-10 RADIATION PROTECTION Revision 21 Page 1 of 1 LADTAP INPUT DATA AND RESULTS MAXIMUM INDIVIDUAL DOSE CALCULATIONS Usage Rates (kg/yr or h/yr)

Exposure Pathway Dilution Factor Transit Time (h)

Adult Teen Child Infant Fish Ingestion 15 12 21.0 16.0 6.9 0.0 Water Ingestion 1,000 24 730.0 510.0 510.0 510.0 Shoreline Use 1

0 12.0 67.0 14.0 0.0 Swimming 1

0 12.0 67.0 14.0 0.0 Boating 15 0

52.0 52.0 29.0 0.0 Dose Results (mrem/yr)(a)

Adults Teenager Exposure Pathway T Body Liver Skin T Body Liver Skin Fish Ingestion 5.25(-1)(b) 6.96(-1) 2.97(-1) 6.91(-1)

Water Ingestion 5.66(-4) 6.13(-4) 3.10(-4) 4.06(-4)

Shoreline Use 7.96(-3) 7.96(-3) 9.3(-3) 4.45(-2) 4.45(-2) 5.19(-2)

Swimming 8.24(-5) 8.24(-5) 4.6 (-4) 4.6 (-4)

Boating 1.19(-5) 1.19(-5) 1.19(-5) 1.19(-5)

Totals 5.34(-1) 7.04(-1) 9.3(-3) 3.43(-1) 7.36(-1) 5.19(-2)

(a) Doses to other individuals and organs are smaller than those presented.

(b) 5.25(-1) = 5.25 x 10

-1

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-11 RADIATION PROTECTION Revision 21 Page 1 of 1 ACTIVITY IN COOLANT AND GASEOUS WASTE Activity Activity in Surge Tank Fraction of 10 CFR 20 Ci/cm 3

Ci/cm 3 H2 10 CFR 20 Limit at Boundary Isotope Half-Life Coolant As Received 60-Day Hold Ci/cm 3

No Hold 60-Day Hold Kr-85(m) 4.4h 1.50 42.9 (a) 1 x 10

-7

.0065 (a)

Kr-85 10.4y 2.34 66.9 65.6 3 x 10

-7

.0034

.0034 Kr-87 78m 0.81 23.1 (a) 2 x 10

-8

.017 (a)

Kr-88 2.8h 2.48 70.9 (a)

(b)

Xe-133 5.27d 225 6,430 2.48 3 x 10

-7 0.32

.00012 Xe-135 9.2h 6.75 193 (a) 1 x 10

-7

.029 (a)

Xe-138 17m 0.36 10.3 (a)

(b)

(a)Less than 10

-8 (b)Unlisted in 10 CFR 20

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-12 RADIATION PROTECTION Revision 21 Page 1 of 1 SPECIAL LOCATION GASPAR INPUT DATA Distance Normal Depleted Deposition Number (Miles)

Direction Description X/Q(s/m

3)

X/Q(s/m

3)

D/Q(1/m

2) 1 0.63 S

Residence 5.56(-6) 4.66(-6) 3.08(-8) 2 0.88 ENE Garden 2.06(-6) 1.67(-6) 2.31(-8) 3 1.00 ESE Meat Animal 2.13(-6) 1.69(-6) 1.49(-8) 4 2.50 NE Goat Milk 2.60(-7) 1.85(-7) 8.14(-10) 5 2.75 ENE Milk Cow 1.81(-7) 1.26(-7) 1.59(-9)

Value for Parameter Appropriate Locations Fraction fresh leafy vegetables grown locally 1.0 Fraction of year cows, cattle, goats on pasture 0.5 Fraction of vegetable intake grown in garden 0.76 Fraction of feed from pasture while on pasture 1.0 Air water content, g/m 3

8.0

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-13 RADIATION PROTECTION Revision 21 Page 1 of 1 DOSE RESULTS FOR SPECIAL LOCATIONS MAXIMUM INDIVIDUAL DOSES BY AGE GROUP AND ORGAN mrem/yr(a)

Adults Teenagers Children Infants Location(a)

Description T Body Skin Thyroid T Body Skin Thyroid T Body Skin Thyroid T Body Skin Thyroid 1

Plume 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1)

Ground 1.43(-1) 1.68(-2) 1.43(-2) 1.43(-2) 1.68(-2) 1.43(-2) 1.43(-2) 1.60(-2) 1.43(-2) 1.43(-2) 1.68(-2) 1.43(-2)

Inhalation 9.25(-2) 9.20(-2) 3.40(-1) 5.13(-2) 5.09(-2) 2.58(-1) 5.22(-2) 5.16(-2) 3.25(-1) 5.57(-2) 5.49(-2) 5.23(-1) 2 Garden 2.05(-1) 1.99(-1) 1.71(0) 2.43(-1) 2.37(-1) 1.43(0) 5.02(-1) 4.95(-1) 2.30(0) 3 Meat 5.09(-2) 5.06(-2) 1.10(-1) 3.52(-2) 3.50(-2) 7.62(-2) 6.16(-2) 6.14(-2) 1.24(-2) 4 Goat Milk 1.45(-2) 1.36(-2) 2.58(-1) 1.84(-2) 1.72(-2) 3.84(-1) 3.66(-2) 3.46(-2) 7.60(-1) 6.84(-2) 6.49(-2) 1.81(0) 5 Cow Milk 6.79(-3) 6.33(-3) 1.84(-1) 9.47(-3) 8.77(-3) 2.76(-1) 2.03(-2) 1.90(-2) 5.48(-1) 3.89(-2) 3.74(-2) 1.31(0)

(a) See Table 11-12 for location data

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 1 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control Service Water, RE0833 Scintillation detector/detector well in service water line to discharge structure.

Digital indicator 10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Steam Generator Blowdown, RE0707 Scintillation detector/external to blowdown tank, drain to P98A/B suction.

Digital rate meter 10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation signal; isolates blowdown tank.

Radwaste Liquid Discharge, RE1049 Scintillation detector on radwaste liquid line to discharge structure.

Digital rate meter 10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, cirtuit failure. Isolates radwaste release.

Component Cooling Water, RE0915 Scintillation detector/piping, valves, and detector housing.

CC pump dP for flow.

Digital indicator 10-107 CPM.

5 x 10-5 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure; isolates component cooling water surge tank vent.

Circ Water Discharge, RE1323 Scintillation detector/piping, valves, sample pump and detector housing; circulating from mixing basin prior to discharge.

Digital indicator 10-107 CPM.

4 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Off-Gas Monitoring, RE0631 Scintillation detector/piping, valves and detector housing; main condenser steam jet air ejector noncondensibles to stack.

Digital rate meter analyzer 10-107 CPM.

1 x 10-5 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 2 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control Radwaste Area Ventilation, RE1809 Geiger-Mueller tube/piping, valves, sample pump and detector housing; air monitoring prior to discharge to stack.

Linear rate meter 0-106 CPM.

4 x 10-5 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure; isolates radwaste vent system.

Engineered Safeguards Pump Rooms Vent, RE1810, 1811 Geiger-Mueller tube; piping, valves, sample pump and detector housing; to stack, 2 systems, East and West rooms.

Digital rate meter 10-107 CPM.

1 x 10-4 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure; isolates pump room vent supply and exhausts.

Waste Gas Radiation, RE1113 Geiger-Mueller tube/piping, valves and detector housing; from the waste gas surge tank and waste gas decay tanks to stack.

Digital rate meter 10-107 CPM.

1 x 10-4 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure; isolation waste gas surge tank and decay tanks.

Containment Building Gas Monitoring System, RE1817 Geiger-Mueller tube/piping solenoid valves and detector housing; from 5 sample locations on (4) cooler fan discharges.

Linear rate meter 10-107 CPM.

1 x 10-4 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure.

Failed Fuel, RE0202 Scintillation detector/detector housing in letdown line.

Linear rate meter, 0-106 CPM, local.

N/A Alarm on high radiation, circuit failure.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 3 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control Steam Generator Blowdown Vent, RE2320 Scintillation detector/in well on blowdown vent line.

Digital rate meter,10-107 CPM.

2 x 10-5 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Turbine Building Sump, RE5211 Scintillation detector/piping, valves, and detector housing, sump pump discharge to drain.

Digital rate meter,10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Radwaste Addition Vent, RE5711 Beta scintillation/dP across roughing filter used for flow.

Digital rate meter,10-107 CPM.

5 x 10-6 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation circuit failure; high radiation isolates radwaste addition vent.

Fuel Building Addition Vent, RE5712 Beta scintillation/dP across roughing filter used for flow.

Digital rate meter,10-107 CPM.

5 x 10-6 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation circuit failure; high radiation isolates fuel building vent.

RGEMS 2327 Scintillation detectors for beta, gamma, ionization chamber/piping, valves, filters, sample collection bottle; discharge to stack inlet.

Log count rate meter, recorded; stack flow, recorded; sample flow recorded;10-106 CPM beta (log),10-107 CPM (log),

gamma 1-107 mr/h (ion chamber) or 4 x 106 Ci/s digital.

1 x 10-6 Ci/cm3 of Xe-133 equivalent.

Alarm, set recorder speed, isolate samples on alert level. Alarm transfer flow to upper range on high radiation.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 4 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control RGEMS RE2325, RE2326 Scintillation detectors for beta, gamma, ionization chamber/piping, valves, filters, sample collection bottle; discharge to stack inlet.

Digital rate meter RIA-2325: 10-106 CPM RIA-2326: 10-107 CPM 3.9 x 10-7 Ci/cm3 of Xe-133 equivalent.

Alarm, set recorder speed, isolate samples on alert level. Alarm transfer flow to upper range on high radiation.

Main Steam, RE2323, 2324 Geiger-Mueller tube/in lead collimator adjacent to main steam lines.

Digital rate meter 10-107 CPM.

5 x 10-2 Ci/cm3 of dose equivalent I-131 Alarm on high radiation.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-16 RADIATION PROTECTION Revision 21 Page 1 of 2 AREA RADIATION DETECTORS (a) Sensitivity for all instruments except containment detectors has energy dependence of +/-20% of the actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV (b) Sensitivity for containment detector instruments has an energy dependence of

+/-15% of actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV.

(c) Sensitivity for the radwaste monitor is +/-30% of the actual intensity over a photon energy spectrum from 80 keV to 1.33 MeV.

Instrument(a), (b)

Range Containment 590' Elev NW Side (b) 10 10 4 Rem/hr Containment 590' Elev SW Side (b) 10 10 4 Rem/hr Containment 590' Elev NE Side (b) 10 10 4 Rem/hr Containment 590' Elev SE Side (b) 10 10 4 Rem/hr East Engineering Safeguards Room 0.1-10 7 mrem/hr Radwaste Service Corridor 0.1-10 7 mRem/hr Radwaste Control Area (C-40 Panel) 0.1-10 7 mrem/hr 2.4 kV Switchgear Room (1C) 0.1-10 7 mRem/hr Control Lab Corridor 0.1-10 7 mrem/hr Access Control Station 0.1-10 7 mrem/hr Outside Cont Personnel Air Lock 607' Elev 0.1-10 7 mrem/hr Containment Purge Unit Room-North 0.1-10 7 mrem/hr Radwaste Demineralizer Room Roof 0.1-10 7 mrem/hr Control Room/Turbine Bldg Corridor 0.1-10 7 mrem/hr Control Room Entrance 0.1-10 7 mrem/hr Turbine Floor East Side 0.1-10 7 mrem/hr Health Physics Offices 0.1-10 7 mrem/hr Spent Fuel Pool-South 0.1-10 7 mrem/hr Air Room 590' Elev 0.1-10 7 mrem/hr Inside of Cont Personnel Air Lock 1.0-10 7 mrem/hr Containment 649' Elev Rx Cavity 1.0-10 7 mRem/hr Containment 649' Elev Rx Cavity 1.0-10 7 mRem/hr Containment Hi range-left channel 1-10 7 Rem/hr Containment Hi range-right channel 1-10 7 Rem/hr Decontamination Room 0.1-10 7 mrem/hr Evaporator "A" 0.1-10 7 mrem/hr Evaporator "B" 0.1-10 7 mrem/hr Evaporator Control Panel C-105 0.1-10 7 mrem/hr Waste Gas Decay Tank T-101, A, B & C 0.1-10 7 mrem/hr

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-16 RADIATION PROTECTION Revision 21 Page 2 of 2 AREA RADIATION DETECTORS (a) Sensitivity for all instruments except containment detectors has energy dependence of +/-20% of the actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV (b) Sensitivity for containment detector instruments has an energy dependence of

+/-15% of actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV.

(c) Sensitivity for the radwaste monitor is +/-30% of the actual intensity over a photon energy spectrum from 80 keV to 1.33 MeV.

Environmental Lab Entrance 0.1-10 7 mrem/hr Radwaste Packaging Area-East 0.1-10 7 mrem/hr Radwaste Packaging Area-West 0.1-10 7 mrem/hr Radwaste Demineralizer 649' Elev 0.1-10 7 mrem/hr Steam Dumps Area 0.1-10 7 mrem/hr Radwaste Monitors (c) Local Readout East Processing Building 1.0-10 5 mRem/hr East Storage Building 1.0-10 5 mRem/hr South Storage Building 1.0-10 5 mRem/hr (Not Used for Radwaste Storage at this time)

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-17 RADIATION PROTECTION Revision 28 Page 1 of 2 Primary Coolant Fission and Corrosion Product Activities for AST Dose Analyses Nuclide Activity*

Nuclide Activity*

(PCi/g)

Co-58 7.0E-03 Np-239 Co-60 8.0E-04 Pu-238 Cr-51 4.7E-03 Pu-239 Fe-55 1.8E-03 Pu-240 Fe-59 4.5E-04 Pu-241 Mn-54 2.4E-03 Am-241 Kr-85 5.3E-01 Cm-242 Kr-85m 1.2E+00 Cm-244 Kr-87 7.5E-01 I-130 1.1E-01 Kr-88 2.2E+00 Kr-83m 3.2E-01 Rb-86 1.5E-02 Xe-138 4.7E-01 Sr-89 5.4E-03 Xe-131m 4.5E-01 Sr-90 4.9E-04 Xe-133m 1.7E+00 Sr-91 1.5E-03 Xe-135m 4.8E-01 Sr-92 5.9E-04 Cs-138 7.0E-01 Y-90 6.4E-04 Cs-134m 4.6E-02 Y-91 1.8E-02 Rb-88 2.3E+00 Y-92 7.2E-04 Rb-89 5.8E-02 Y-93 4.4E-04 Sb-124 1.1E-03 Zr-95 1.2E-03 Sb-125 9.2E-03 Zr-97 4.9E-04 Sb-126 6.2E-04 Nb-95 1.2E-03 Te-131 1.5E-02 Mo-99 4.2E+00 Te-133 6.1E-03 Tc-99m 3.2E+00 Te-134 2.1E-02 Ru-103 1.2E-03 Te-125m 2.0E-03 Ru-105 1.4E-04 Te-133m 1.2E-02 Ru-106 5.3E-04 Ba-141 9.1E-05 Rh-105 5.5E-04 Ba-137m 2.5E+01 Sb-127 4.3E-02 Pd-109 Sb-129 2.4E-02 Rh-106 5.3E-04 Te-127 4.6E-02 Rh-103m 1.2E-03 Te-127m 7.2E-03 Tc-101 1.5E-02 Te-129 3.8E-02 Eu-154 Te-129m 2.2E-02 Eu-155 Te-131m 3.7E-02 Eu-156 Te-132 4.8E-01 La-143 1.1E-05 I-131 5.2E+00 Nb-97 8.1E-05 I-132 1.2E+00 Nb-95m 8.5E-06

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-17 RADIATION PROTECTION Revision 28 Page 2 of 2 Primary Coolant Fission and Corrosion Product Activities for AST Dose Analyses Nuclide Activity*

Nuclide Activity*

(PCi/g)

I-133 5.4E+00 Pm-147 1.2E-04 I-134 4.7E-01 Pm-148 1.7E-04 I-135 2.3E+00 Pm-149 3.0E-04 Xe-133 7.0E+01 Pm-151 8.3E-05 Xe-135 7.4E+00 Pm-148m 2.6E-05 Cs-134 4.9E+01 Pr-144 9.3E-04 Cs-136 4.3E+00 Pr-144m 1.6E-05 Cs-137 2.6E+01 Sm-153 Ba-139 4.3E-04 Y-94 1.4E-05 Ba-140 7.1E-03 Y-95 8.6E-06 La-140 3.4E-03 Y-91m 8.9E-04 La-141 2.4E-04 Br-82 2.5E-02 La-142 6.8E-05 Br-83 6.6E-02 Ce-141 1.1E-03 Br-84 2.7E-02 Ce-143 6.3E-04 Am-242 Ce-144 9.3E-04 Np-238 Pr-143 1.0E-03 Pu-243 Nd-147 4.3E-04

Activities based on 1% failed fuel. Listed activities are adjusted to Technical Specification limits for performance of AST dose calculations.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 1 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel)

Normal Activity Normal (Microcuries/

(Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter)

Centimeter)(a)

(Curies)

(a)

Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.

(b)

Total value consisting of summation of Sr-89 and Sr-90.

H-3 2.80 0.21 860 65 Br-84 4.66 x 10

-2 13.4 Kr-85(m) 1.50 0.030 432 8.6 Kr-85 2.34 3.52 x 10

-4 674 0.10 Kr-87 0.81 0.037 233 10.6 Kr-88 2.48 0.060 714 17.3 Rb-88 2.44 0.122 702 35.1 Rb-89 6.10 x 10

-2 3.05 x 10

-4 0.18 9.0 x 10

-4 Sr-89 5.33 x 10

-3) 2.28 x 10

-5(b) 1.53 )

7.0 x 10

-3(b)

Sr-90 1.50 x 10

-4) 4.3 x 10

-2)

Y-90 5.77 x 10

-4 0.17 Sr-91 3.70 x 10

-3 8.01 x 10

-5 1.06 0.023 Y-91(m) 0.24 1.76 x 10

-3 68.4 0.50 Mo-99 2.26 3.70 x 10

-5 649 0.010 Te-129 2.72 x 10

-2 7.84 I-129 5.66 x 10

-8 1.63 x 10

-5 I-131 4.40 0.114 1,266 32.8 Te-132 0.36 3.22 x 10

-5 102 9.1 x 10

-3

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 2 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel)

Normal Activity Normal (Microcuries/

(Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter)

Centimeter)(a)

(Curies)

(a)

Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.

(b)

Data for nuclides with less than 15 minute half-lives is not documented.

I-132 1.13 0.095 324 27.2 I-133 6.38 0.141 1,830 40.4 Xe-133 255 0.472 6.47 x 10 4

135.7 Cs-134 1.42 1.35 x 10

-5 725 6.9 x 10

-3 Te-134 2.63 x 10

-2 7.55 I-134 0.64 0.134 184 38.5 I-135 2.78 0.142 801 40.9 Xe-135 6.75 0.090 1,943 25.9 Cs-136 0.15 1.90 x 10

-5 43.4 5.5 x 10

-3 Cs-137 10.6 2.32 x 10

-5 3,064 6.7 x 10

-3 Xe-138 0.36 (b) 103 (b)

Cs-138 0.69 0.059 198 16.9 Ba-140 6.78 x 10

-3 5.09 x 10

-4 1.95 0.15 La-140 6.52 x 10

-3 6.97 x 10

-4 1.88 0.20 Co-60 1.1 x 10

-3 2.78 x 10

-5 0.37 9.4 x 10

-3 Fe-59 7.7 x 10

-6 1.41 x 10

-5 2.6 x 10

-3 4.8 x 10

-3 Co-58 7.9 x 10

-3 4.28 x 10

-4 2.67 0.14 Mn-56 2.3 x 10

-2 1.55 x 10

-4 7.77 0.052

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 3 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel)

Normal Activity Normal (Microcuries/

(Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter)

Centimeter)(a)

(Curies)

Mn-54 2.0 x 10

-5 2.70 x 10

-5 6.8 x 10

-3 9.2 x 10

-3 Cr-51 2.4 x 10

-3 5.35 x 10

-4 0.81 0.18 Zr-95 1.9 x 10

-5 1.08 x 10

-5 6.4 x 10

-3 3.6 x 10

-3 Total 275.7 1.708 79,663 497 (a)

Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-2 RADIATION PROTECTION Revision 21 Page 1 of 2 RADIOACTIVE WASTE QUANTITIES OF SIGNIFICANT ACTIVITY Quantity/Year-Liquid Waste Sources Gallons Assumptions Chemical and Volume 69,500 Start-up after refueling Control System 900 Cold shutdown Day 1 37,200 Start-up from cold condition Day 1 13,200 Hot shutdown(a) Day 50 1,200 Start-up from hot condition Day 50 17,400 Hot shutdown(a) Day 140 1,700 Start-up from hot condition Day 140 32,300 Hot shutdown (a) Day 230 2,000 Start-up from hot condition Day 230 2,200 Cold shutdown Day 240 104,300 Start-up from cold condition Day 240 68,900 Hot shutdown(a) Day 270 2,300 Start-up from hot condition Day 270 17,500 cold shutdown to refuel 216,000 Boron reduction for cycle shim bleed Total 586,600 Primary System Drain 1,500 Primary coolant pump seal leakage at Tank 1 gpd per pump for four pumps 1,000 Safety injection check valve leakage 64,900 Drain primary system for maintenance at Day 240 13,800 Drain primary system for refueling 21,300 Drain refueling shield Total 102,500 (a)

Hot shutdown quantities are based on maintaining the shutdown margin during xenon buildup by boron dilution and on Plant start-up eight hours after shutdown during the xenon buildup peak.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-2 RADIATION PROTECTION Revision 21 Page 2 of 2 RADIOACTIVE WASTE QUANTITIES OF SIGNIFICANT ACTIVITY Quantity/Year-Liquid Waste Sources Gallons Assumptions Equipment Drain Tank 11,400 Coolant charging pump seal leakage at 31 gpd maximum leakage 7,000 Spent fuel pool overflow 3,900 Spent resin tank overflow from resin flushing - 260 ft 3/year of resin replacement at 2 ft 3/ft 3 resin 1,900 Demineralizers drain from resin charging - 260 ft 3/year of resin replacement at 1 ft 3/ft 3 resin Total 24,200 Radiochemistry Lab 11,000 12 samples per day at 2.5 gallons Drain Tank per sample Total Liquid Waste of Significant Activity 724,300 Quantity/Year-Gaseous Waste Sources ft 3

Assumptions Degas of Primary System 2,418 Degas to 5 cm 3/kg prior to 3 cold shutdowns including gas in volume control tank Off-Gas Liquid Waste 867 See start-up and shutdown schedule From Shutdowns and above Start-Ups Off-Gas for Chemical 1,011 Boron dilution generates 216,000 Shim Reduction gallons liquid waste with 35 cm 3/kg gas content Off-Gas Liquid Drained 243 for Refueling Maintenance and Miscellaneous Total Gaseous Waste of Significant Activity 4,539

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 1 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

1.

CLEAN WASTE RECEIVER TANKS (T-64A, B, C, D)

Number 4

Material Type 304 Stainless Steel Capacity (Each) 50,000 gal (7,000 ft3)

Design Pressure 5 psig (Vapor Space)

Design Temperature 103°F Code API 620

2.

PRIMARY SYSTEM DRAIN TANK (T-74)

Number 1

Material Type 304 Stainless Steel Capacity 900 gal Design Pressure 50 psig Design Temperature 250°F Code ASME B&PV Code,Section III, Class C

3.

EQUIPMENT DRAIN TANK (T-80)

Number 1

Material Type 304 Stainless Steel Capacity 550 gal Design Pressure 50 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII

4.

SPENT RESIN STORAGE TANK (T-69)

Number 1

Material Type 304 Stainless Steel Capacity 3,000 gal (400 ft3)

Design Pressure 125 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class C

5.

CONTROLLED CHEM LAB DRAIN TANK (T-76)

Number 1 Divided Into 2 Compartments Material Type 304 Stainless Steel Capacity 900 gal (Total)

Design Pressure 50 psig Design Temperature 150°F Code ASME B&PV Code,Section VII

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 2 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

6.

TREATED WASTE MONITOR TANKS (T-66A, B)

Number 2

Material Carbon Steel Internal Coating Baked Phenolic, 6-8 Mils Capacity 5,500 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII

7.

DIRTY WASTE DRAIN TANK (T-60)

Number 1 Divided Into 2 Compartments Material Carbon Steel Capacity 3,800 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII Requirements

8.

FILTERED WATER MONITORING TANKS (T-63)

Number 1 With 2 Compartments Material Carbon Steel Internal Coating Baked Phenolic, 6-8 Mils Capacity 5,500 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII

9.

WASTE GAS SURGE TANK (T-67)

Number 1

Material Carbon Steel Capacity 550 gal (80 ft3)

Design Pressure 20 psig Design Temperature 150°F Code ASME B&PV Code,Section III, Class C

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 3 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

10.

WASTE GAS DECAY TANKS (T-68A, B, C)

Number 3

Material Carbon Steel Capacity 800 gal (100 ft3)

Design Pressure 120 psig Design Temperature 550°F Code ASME B&PV Code,Section III, Class C

11.

LAUNDRY DRAIN TANK (T-70)

Number 1 Divided Into 2 Compartments Material Carbon Steel Capacity 1,000 gal (Total)

Design Pressure 15 psig Design Temperature 150°F Code ASME P&PV Code,Section VIII

12.

VACUUM DEGASIFIER

a.

Tank (T-57)

Number 1

Performance Handle Solution With 0-50 Std cm3 H2 (kg of Liquid Waste. Reduced H2 Concentration to 1/40 of Influent Concentration)

Design Flow 0-160 gpm Design Pressure 75 psig & 30" Hg Design Temperature 200°F Material Stainless steel Code ASME B&PV Code,Section III, Class C

b.

Vacuum Pumps (C-51A, B)

Number 2

Capacity 28 scfm @ 28" Hg Type Rotary, Water-Sealed, Water-Lubricated with Closed Cooling Loop Motor 3 hp Material Stainless steel

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 4 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

13.

RADWASTE DEMINERALIZER

a.

Demineralizer Tanks (T-55A, B, C)

Number 3

Material of Tank Stainless Steel Flow Rate (Each) 48 gpm (Rated), 100 gpm (Max)

Unit Flow Rate (at Ratings) 5.0 gpm/ft2 Resin Volume (Each) 32 ft3 Resin Type Equivalent Capacity Mixture of Nuclear Grade Cation and Anion Design Pressure 125 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

b.

Clean Resin Transfer Tank (T-61)

Number 1

Material PVC Lined Carbon Steel Capacity 32 ft3 Design Pressure 125 psig Design Temperature 125°F Code ASME B&PV Code,Section VIII

14.

CLEAN WASTE FILTERS (F-57A, B, C)

Type Cartridge Type With Replaceable Elements Number 3

Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 150 Micron Flow Rate 100 gpm Design Pressure 125 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 5 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

15.

EQUIPMENT DRAIN FILTER (F-56)

Number Cartridge Type with Replaceable Elements Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 25 Microns Design Pressure 125 psig Design Temperature 212°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

16.

DIRTY WASTE FILTER (F-53)

Type Cartridge Type With Replaceable Elements Number 1

Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 200 Microns Flow Rate 75 gpm Design Pressure 100 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

17.

LAUNDRY DRAIN FILTER (F-55)

Type Cartridge Type With Replaceable Elements Number 1

Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 25 Microns Flow Rate 20 gpm Design Pressure 100 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 6 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

18.

PRIMARY SYSTEM DRAIN TANKS PUMPS (T-71A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 75 gpm Head 80 ft TDH Material Type 316 Stainless Steel Motor 5 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

19.

DEGASIFIER PUMPS (P-68A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 160 gpm Head 190 ft TDH Material Type 316 Stainless Steel Motor 20 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

20.

EQUIPMENT DRAIN TANK PUMPS (P-75A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 100 gpm Head 266 ft TDH Material Type 316 Stainless Steel Motor 25 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

21.

CONTROLLED CHEM LAB DRAIN PUMPS (P-61A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 10 gpm Head 158 ft TDH Material Type 316 Stainless Steel Motor 7.5 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 7 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

22.

RECEIVER TANK (CWRT) PUMPS (P-69A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 100 gpm Head 200 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt

23.

RECEIVER TANK (CWRT) CIRCULATING PUMP (P-70)

Type Horizontal Centrifugal With Mechanical Seals Number 1

Capacity (Each) 250 gpm Head 121 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

24.

TREATED WASTE MONITOR PUMPS (P-58A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 150 gpm Head 140 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

25.

SAFETY INJECTION ROOM SUMP PUMPS (P-72A, B AND P-73A, B)

Type Vertical Centrifugal Number 4 (2 Sets With 2 Pumps per Set)

Capacity (Each) 25 gpm Head 35 ft TDH Material Stainless Steel Motor 1 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA,

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 8 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

26.

DIRTY WASTE DRAIN TANK PUMPS (P-60A, B)

Type Horizontal Centrifugal With Mechanical Seals Number 2

Capacity (Each) 75 gpm Head 160 ft TDH Material Type 316 Stainless Steel Motor 10 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute FILTERED WASTE MONITOR PUMP (P-63)

Type Horizontal Centrifugal With Mechanical Seals Number 1

Capacity (Each) 75 gpm Head 150 ft TDH Material Type 316 Stainless Steel Motor 10 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute

28.

WASTE GAS COMPRESSORS (C-50A, B)

a.

Compressor Number 2

Type Single Head, Single Stage Diaphragm Type Capacity (Each) 2.35 scfm at 14.7 psia Suction, 0.44 scfm at 7.5 psia Suction Discharge Pressure 100 psig at Maximum Delivery Material Stainless Steel Motor 2 hp, 3 Phase, 60 Hertz, 460 Volt, TEFC

b.

Aftercoolers Number 2

Type Shell and Tube With Moisture Separator and Drain Trap Material Tube Side (Gas) Stainless Steel, Shell Side (Water) Carbon Steel

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 9 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

29.

WASTE GAS COMPRESSOR (C-54)

a.

Compressor Number 1

Type Diaphragm Type Capacity (Each) 5 scfm Avg Between Suction Pressures of 7.5 and 15.0 psia Discharge Pressure 100 psig Material Motor 7.5

b.

Aftercoolers Number 1

30.

PIPING, FITTING AND VALVES

a.

Liquid Systems Material Stainless Steel Design Pressure Floor Drains - Atmosphere, Process -

50 psig Joints, 2" and Larger Butt Weld 1-1/2" and Smaller 2,000 lb SW Valves, 2" and Larger Stainless Steel, Butt Weld Ends, 150 lb 1-1/2" and Smaller Stainless Steel, 2,000 lb SW Ends, 150 lb Butterfly Valves Stainless Steel, Flangeless, 150 lb Plug Vales Stainless steel, FF Flanged, 150 lb Code ASA B31.1, Code for Pressure Piping, Including Applicable Nuclear Code Cases, ASA B16.5 Radiography All Butt Weld in Nuclear Service Systems Rated for Higher Than 50 psig and 212°F Are Radiographed 100. All Butt Welds in Nuclear Systems Rated for Less Than 50 psig and 212°F Are Radiographed 10%

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 10 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT

b.

Gaseous Systems Material Carbon Steel Design Pressure 100 psig Joints, 2" and Larger Butt Weld 1-1/2" and Smaller 3,000 lb SW Valves, 2" and Larger Carbon Steel, 150 lb BW 1-1/2" and Smaller Carbon Steel, 600 lb, 3,000 lb SW Butterfly Carbon Steel, 150 lb, FF Flanged Plug Ductile Iron, 150 lb, FF Flanged Code ASA B31.1, Code for Pressure Piping, Including Applicable Nuclear Code Cases, ASA B16.5 Radiography All Welds Are 100% Radiographed

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 1 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

1.

CLEAN WASTE HOLDUP TANK (T-85)

Number 1

Material of Tank SA240 Type 304 SS Capacity 5,000 gal Design Pressure Atm Design Temperature 212°F Code API-620, 1970 Exam ASME B&PV Code,Section III, 1971

2.

CLEAN WASTE TRANSFER PUMP (P-94)

Type Gould 3196 Number 1

Capacity 80 gpm Head 85 ft Material Stainless Steel Motor 5 hp Code ASME B&PV Code,Section III, Class 3, 1971

3.

CLEAN AND DIRTY WASTE EVAPORATORS (M-59A, B)

a.

Evaporator Vessel Number 2

Material 316 SS Capacity 1,600 gal Design Pressure 15 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class 3, 1971

b.

Recirculation Pump Type Gould 3196 - 3 x 4-13 Number 4

Capacity 200 gpm Head 30 ft Material 316 SS Motor 5 hp, 3 Phase, 60 Hertz, 460 Volt Code ASME B&PV Code,Section III, Class 3, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 2 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

c.

Distillate Pump Type Gould 3196 - 1 x 1-1/2-6 Number 4

Capacity 25 gpm Head 130 ft Material 316 SS Motor 5 hp Code ASME B&PV Code,Section III, Class 3, 1971

d.

Concentrate Pump Type Gould 3196 - 1 x 1-1/2-6 Number 4

Capacity 25 gpm Head 100 ft Material 316 SS Motor 3 hp Code ASME B&PV Code,Section III, Class 3, 1971

e.

Vacuum Pump Type Nash Number 4

Capacity 48 cfm @ 20" vacuum Head 2 psig Material 316 SS Motor 3 hp Code N/A

4.

CLEAN WASTE DISTILLATE TANK (T-86)

Number 1

Material SA240 Type 304 SS Capacity 5,000 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 3 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

5.

CLEAN WASTE DISTILLATE PUMP (P-97A, B)

Type Gould 3196 Number 2

Capacity 80 gpm Head 85 ft Material 316 SS Motor 5 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

6.

CLEAN (MISCELLANEOUS) WASTE CONCENTRATE TANKS (T-94, T-95)

Number 2

Material SA240 Type 304 SS Capacity 1,500 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971

7.

MISCELLANEOUS WASTE FILTER (F-59)

Type Cartridge Type With Replaceable Elements Number 1

Material, Container 304 SS Material, Filter Media Epoxy Impregnated Cellulose Filter Media Rating 150 Micron*

Flow Rate 30 gpm Design Pressure 50 psig Design Temperature 212°F Code ASME B&PV Code,Section III, Class 3, 1971

May be in service with element removed.

8.

CLEAN (MISCELLANEOUS) WASTE CONCENTRATE PUMPS (P-95A, B)

Type Gould 3196, 1 x 2-8 Number 2

Capacity 30 gpm Head 75 ft Material 316 SS Motor 3 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 4 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

9.

POLISHING (MISCELLANEOUS WASTE) DEMINERALIZERS (T-88, T-89A, B)

Number 3

Material of Tank 304 SS Flow Rate 50 gpm (Rated), 100 gpm (Max)

Unit Flow Rate (At Max) 10 gpm/ft2 Resin Volume 32 ft3 Resin Type Equivalent Capacity Mixture of Nuclear Grade Cation and Anion

10. MISCELLANEOUS WASTE HOLDUP TANKS (T-92A, B, C)

Number 3

Material SA240 Type 304 SS Capacity 20,000 gal Design Pressure Atm Design Temperature 212°F Code API-620, 1970 Exam ASME B&PV Code,Section III, 1971

11. MISCELLANEOUS WASTE TRANSFER PUMPS (P-92A, B)

Type Gould 3196, 2 x 3-13 Number 2

Capacity 80 gpm Head 120 ft Material 316 SS Motor 10 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

12. MISCELLANEOUS WASTE DISTILLATE TANK (T-87)

Number 1

Material SA240 Type 304 SS Capacity 8,000 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 5 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

13. MISCELLANEOUS WASTE DISTILLATE PUMPS (P-89A, B)

Type Gould 3196, 1-1/2 x 3-6 Number 2

Material 316 SS Capacity 80 gpm Head 110 ft Motor 7-1/2 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971

14. RADWASTE SPENT RESIN STORAGE TANK (T-100)

Number 1

Material 304 SS Capacity 200 ft3 Design Pressure 125 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class 3, 1971

15. WASTE GAS DECAY TANKS (T-101A, B, C)

Number 3

Material Carbon Steel Capacity 225 ft3 Design Pressure 120 psig Design Temperature 550°F Code ASME B&PV Code,Section III, Class 3, 1971

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 6 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

16. PIPING, FITTINGS AND VALVES

a.

Liquid Radwaste System (Process)

Material Stainless Steel Design Pressure 125 psig and 150 psig Fittings 2-1/2" and Larger 150 lb Thickness To Match Pipe Butt Weld Ends 2-1/2" and Smaller 3,000 lb Socket Weld Valves 2-1/2" and Larger 150 lb Butt Weld Ends 2" and Smaller 150 lb Socket Weld Ends Joints 2-1/2" and Larger Butt Weld Ends 2" and Smaller Socket Weld Ends Code ASME B&PV Code,Section III, Nuclear Power Plant Components, Nuclear Class 3, 1971, per AEC Safety Guide 26, March 27, 1972

b.

Atmospheric Radwaste Drainage Piping Material Stainless Steel Design Pressure Atmospheric Fittings 8" and Smaller Butt Weld Ends Joints 8" and Smaller Butt Weld Code ANSI B31.1.0 - 1967 Power Piping

c.

Gaseous Radwaste System (Process)

Material Carbon Steel Design Pressure 150 psig Fittings 2-1/2" and Larger 150 lb Thickness To Match Pipe Butt Weld Ends 2" and Smaller 3,000 lb Socket Weld Ends Valves 2-1/2" and Larger 150 lb Butt Weld Ends 2" and Smaller 600 lb Socket Weld Ends Joints 2-1/2" and Larger Butt Weld Ends 2" and Smaller Socket Weld Code ASME B&PV Code,Section III, Nuclear Power Plant Components, Nuclear Class 3, 1971, per AEC Safety Guide 26, March 23, 1972

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 7 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -

ADDITIONAL EQUIPMENT INSTALLED 1971-1973

17. PRIMARY SYSTEM MAKEUP STORAGE TANK (T-90)

Number 1

Material Carbon Steel Capacity 200,000 gal Design Pressure Atmospheric Code API-650, 1970

18. UTILITY WATER STORAGE TANK (T-91)

Number 1

Material Carbon Steel Capacity 75,000 gal Design Pressure Atmospheric Code API-650, 1970

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-5 RADIATION PROTECTION Revision 21 Page 1 of 1 PRIMARY SYSTEM DRAIN TANK Letdown and Regenerative HX Drain Shutdown Cooling Header Relief SI Tanks Leakage PCS Loop Drains Quench Tank Drains Flange Leak Detector Drain Controlled Bleed-Off Relief PCS Pump Seal Leakage

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-6 RADIATION PROTECTION Revision 30 Page 1 of 1 EQUIPMENT DRAIN TANK Spent Resin Storage Tanks Primary Coolant Sample Drain Clean Resin Transfer Tank Radwaste Demineralizer Drains Fuel Pool Overflow Fuel Pool HX Drains Fuel Pool Demineralizer Drains Fuel Pool Filter Drains Blowdown Drain Tank HPI Header Relief SIRW Tank Overflow Drain SIRW Tank HX Drain SI Tank Sample Flush Waste Gas Surge Tank Drain Chemical Addition Tank Drain Charging Pump Relief and Drains VCT Drain Purification Filters Drain

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-7 RADIATION PROTECTION Revision 21 Page 1 of 1 DIRTY WASTE DRAIN TANK Radwaste Addition Area Sample Sink Drains Clean Resin Transfer Tank Drains Pump Leak-Offs Auxiliary Building Floor Drains Decontamination Pit Drains Cask Washdown Area Drains Controlled Chemical Laboratory Drain Tank Drains Component Cooling Surge Tank Drain Boric Acid Batching Tank Drain Boric Acid Filter Drains Treated Waste Monitor Tanks VCT Relief Vacuum Degasifier Relief Turbine Building Sump Pump Discharge Containment Sump Drains Shutdown Cooling HX Drains Spent Resin Storage Tank (T-100)

Primary System Makeup and Utility Water Tanks Overflow Laundry Drain Tank Drains Auxiliary Building Sump Pumps

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-8 RADIATION PROTECTION Revision 26 Page 1 of 2 LIQUID RADWASTE Clean Liquid Waste Activities (Ci/cm 3)*

Dirty Liquid Waste Activities (Ci/cm 3)*

After After After Processiong After After As Received Processing Processing Through Processing Processing in Receiver After 30 Through Two Through Polishing As Received Through Through Isotope Half-Life Tanks Days' Decay Demineralizers Evaporator Demineralizer in Drain Tank Evaporator Demineralizers Fission Products Br-84 32m 1.25 x 10

-2 (a)

(a)

(a) 4.66 x 10

-4 4.66 x 10

-8 (a)

Rb-88 18m 6.61 x 10

-1 (a)

(a)

(a) 2.44 x 10

-2 2.44 x 10

-6 2.44 x 10

-8 Rb-89 15m 1.66 x 10

-2 (a)

(a)

(a) 6.10 x 10

-4 6.10 x 10

-8 (a)

SR-89 54d 1.44 x 10

-3 9.80 x 10

-4 9.80 x 10

-6 (a)

(a) 5.33 x 10

-5 (a)

(a)

Sr-90 28y 4.00 x 10

-5 4.00 x 10

-7 (a)

(a) 1.50 x 10

-6 (a)

(a)

Y-90 64h 1.55 x 10

-4 6.51 x 10

-8 (a)

(a)

(a) 5.77 x 10

-6 (a)

(a)

Sr-91 9.7h 1.00 x 10

-3 (a)

(a)

(a) 3.70 x 10

-5 (a)

(a)

Y-91 58d 6.50 x 10

-2 4.53 x 10

-4 4.53 x 10

-8 (a) 2.40 x 10

-3 2.40 x 10

-7 (a)

Mo-99 67h 6.12 x 10

-1 3.67 x 10

-4 3.67 x 10

-6 (a)

(a) 2.26 x 10

-2 2.26 x 10

-6 2.26 x 10

-8 Te-129 33d 7.36 x 10

-3 3.93 x 10

-5 (a)

(a) 2.72 x 10

-4 2.72 x 10

-8 (a)

I-129 1.7 x 10 7y 1.52 x 10

-8 1.52 x 10

-8 (a)

(a)

I-131 8.0d 1.18 8.87 x 10

-2 8.87 x 10

-4 8.87 x 10

-7 8.87 x 10

-8 4.40 x 10

-2 4.40 x 10

-5 4.40 x 10

-7 Te-132 77h 9.75 x 10

-2 1.46 x 10

-4 1.46 x 10

-6 (a)

(a) 3.60 x 10

-3 3.60 x 10

-7 (a)

I-132 2.3h 3.05 x 10

-1 (a)

(a)

(a) 1.13 x 10

-2 1.13 x 10

-5 1.13 x 10

-7 I-133 21h 1.73 (a)

(a)

(a) 6.38 x 10

-2 6.38 x 10

-5 6.38 x 10

-7 Cs-134 2.3y 3.84 x 10

-1 3.78 x 10

-1 3.70 x 10

-3 3.78 x 10

-7 3.78 x 10

-8 1.42 x 10

-2 1.42 x 10

-6 1.42 x 10

-8 Te-134 44m 7.12 x 10

-3 (a)

(a)

(a) 2.63 x 10

-4 2.63 x 10

-8 (a)

I-134 52m 1.73 x 10

-1 (a)

(a)

(a) 6.40 x 10

-3 6.40 x 10

-5 6.40 x 10

-7 I-135 6.7h 7.53 x 10

-1 (a)

(a)

(a) 2.78 x 10

-2 2.78 x 10

-6 2.78 x 10

-8 Cs-136 13d 4.06 x 10

-2 8.20 x 10

-3 8.20 x 10

-5 (a)

(a) 1.50 x 10

-3 1.50 x 10

-7 (a)

Cs-137 30y 2.87 2.87 2.87 x 10

-2 2.87 x 10

-6 2.87 x 10

-7 1.06 x 10

-1 1.06 x 10

-5 1.06 x 10

-7 Cs-138 32m 1.87 x 10

-1 (a)

(a)

(a) 6.90 x 10

-3 6.90 x 10

-7 (a)

Ba-140 12.8d 1.84 x 10

-3 3.65 x 10

-4 3.65 x 10

-6 (a)

(a) 6.78 x 10

-5 (a)

(a)

La-140 40.2h 1.27 x 10

-3 (a)

(a)

(a) 6.52 x 10

-5 (a)

(a)

Corrosion Products Cr-51 27d 6.50 x 10

-4 3.02 x 10

-6 (a)

(a) 2.4 x 10

-5 (a)

(a)

Mn-54 300d 5.22 x 10

-6 4.87 x 10

-8 (a)

(a) 2.0 x 10

-7 (a)

(a)

Mn-56 2.58h 6.00 x 10

-3 (a)

(a)

(a) 2.3 x 10

-4 2.3 x 10

-8 (a)

Co-58 71d 2.07 x 10

-3 1.55 x 10

-5 (a)

(a) 7.9 x 10

-5 (a)

(a)

Fe-59 45d 2.02 x 10

-6 1.27 x 10

-8 (a)

(a) 7.7 x 10

-8 (a)

(a)

Co-60 5.2y 2.98 x 10

-4 2.95 x 10

-6 (a)

(a) 1.1 x 10

-5 (a)

(a)

Zr-95 65d 4.96 x 10

-6 3.61 x 10

-8 (a)

(a) 1.9 x 10

-7 (a)

(a)

(a) Less Than 10

-8

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-8 RADIATION PROTECTION Revision 26 Page 2 of 2 LIQUID RADWASTE Assumptions:

Factor of 10 reductionin each demineralizer for all isotopes except tritium.

10 3 reduction for iodine in evaporator.

10 4 reduction for all other isotopes except tritium.

19% of clean waste is direct from primary system.

81% of clean waste is from Chemical and Volume JControl System and passes through one ion exchanger prior to entering clean waste receiver tanks.

No holdup period assumed in Miscellaneous Waste Holdup Tank.

1% defective fuel.

Dirty waste activity is 1% of primary coolant activity.

The above information pertaining to isotopic activities are based on decontamination factors (DF) which were provided as part of the initial safety analysis or added as changes to the systems were made. Operating experience has demonstrated that the reactor coolant activity levels are much lower than the activity levels assumed in the radwaste system design. The ODCM provides information pertaining to the monitoring of waste streams and ensures the resultant offsite doses are in compliance with current regulatory requirements. The above information is considered historical.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-9 RADIATION PROTECTION Revision 21 Page 1 of 1 MAXIMUM CALCULATED TRITIUM RELEASE DUE TO EVAPORATION FROM REFUELING CAVITY AND SPENT FUEL POOL Conc in Release From Conc in Release From Spent Fuel Spent Fuel Total Yr of Contain Bldg Contain Bldg Bldg Bldg Release Oper (Ci/cm3)

(Ci/Yr)

(Ci/cm3)

(Ci/Yr)

(Ci/Yr) 5 1.1 x 10-13 18 8.5 x 10-14 13 31 10 2.1 x 10-13 35 2.2 x 10-13 33 68 15 3.0 x 10-13 50 3.6 x 10-13 53 103 20 3.8 x 10-13 63 4.9 x 10-13 72 135 25 4.5 x 10-13 75 6.1 x 10-13 90 165 30 5.1 x 10-13 85 7.1 x 10-13 105 190 35 5.6 x 10-13 93 8.0 x 10-13 118 211 40 6.0 x 10-13 100 8.6 x 10-13 127 227

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-10 RADIATION PROTECTION Revision 21 Page 1 of 1 LADTAP INPUT DATA AND RESULTS MAXIMUM INDIVIDUAL DOSE CALCULATIONS Usage Rates (kg/yr or h/yr)

Exposure Pathway Dilution Factor Transit Time (h)

Adult Teen Child Infant Fish Ingestion 15 12 21.0 16.0 6.9 0.0 Water Ingestion 1,000 24 730.0 510.0 510.0 510.0 Shoreline Use 1

0 12.0 67.0 14.0 0.0 Swimming 1

0 12.0 67.0 14.0 0.0 Boating 15 0

52.0 52.0 29.0 0.0 Dose Results (mrem/yr)(a)

Adults Teenager Exposure Pathway T Body Liver Skin T Body Liver Skin Fish Ingestion 5.25(-1)(b) 6.96(-1) 2.97(-1) 6.91(-1)

Water Ingestion 5.66(-4) 6.13(-4) 3.10(-4) 4.06(-4)

Shoreline Use 7.96(-3) 7.96(-3) 9.3(-3) 4.45(-2) 4.45(-2) 5.19(-2)

Swimming 8.24(-5) 8.24(-5) 4.6 (-4) 4.6 (-4)

Boating 1.19(-5) 1.19(-5) 1.19(-5) 1.19(-5)

Totals 5.34(-1) 7.04(-1) 9.3(-3) 3.43(-1) 7.36(-1) 5.19(-2)

(a) Doses to other individuals and organs are smaller than those presented.

(b) 5.25(-1) = 5.25 x 10

-1

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-11 RADIATION PROTECTION Revision 21 Page 1 of 1 ACTIVITY IN COOLANT AND GASEOUS WASTE Activity Activity in Surge Tank Fraction of 10 CFR 20 Ci/cm 3

Ci/cm 3 H2 10 CFR 20 Limit at Boundary Isotope Half-Life Coolant As Received 60-Day Hold Ci/cm 3

No Hold 60-Day Hold Kr-85(m) 4.4h 1.50 42.9 (a) 1 x 10

-7

.0065 (a)

Kr-85 10.4y 2.34 66.9 65.6 3 x 10

-7

.0034

.0034 Kr-87 78m 0.81 23.1 (a) 2 x 10

-8

.017 (a)

Kr-88 2.8h 2.48 70.9 (a)

(b)

Xe-133 5.27d 225 6,430 2.48 3 x 10

-7 0.32

.00012 Xe-135 9.2h 6.75 193 (a) 1 x 10

-7

.029 (a)

Xe-138 17m 0.36 10.3 (a)

(b)

(a)Less than 10

-8 (b)Unlisted in 10 CFR 20

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-12 RADIATION PROTECTION Revision 21 Page 1 of 1 SPECIAL LOCATION GASPAR INPUT DATA Distance Normal Depleted Deposition Number (Miles)

Direction Description X/Q(s/m

3)

X/Q(s/m

3)

D/Q(1/m

2) 1 0.63 S

Residence 5.56(-6) 4.66(-6) 3.08(-8) 2 0.88 ENE Garden 2.06(-6) 1.67(-6) 2.31(-8) 3 1.00 ESE Meat Animal 2.13(-6) 1.69(-6) 1.49(-8) 4 2.50 NE Goat Milk 2.60(-7) 1.85(-7) 8.14(-10) 5 2.75 ENE Milk Cow 1.81(-7) 1.26(-7) 1.59(-9)

Value for Parameter Appropriate Locations Fraction fresh leafy vegetables grown locally 1.0 Fraction of year cows, cattle, goats on pasture 0.5 Fraction of vegetable intake grown in garden 0.76 Fraction of feed from pasture while on pasture 1.0 Air water content, g/m 3

8.0

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-13 RADIATION PROTECTION Revision 21 Page 1 of 1 DOSE RESULTS FOR SPECIAL LOCATIONS MAXIMUM INDIVIDUAL DOSES BY AGE GROUP AND ORGAN mrem/yr(a)

Adults Teenagers Children Infants Location(a)

Description T Body Skin Thyroid T Body Skin Thyroid T Body Skin Thyroid T Body Skin Thyroid 1

Plume 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1)

Ground 1.43(-1) 1.68(-2) 1.43(-2) 1.43(-2) 1.68(-2) 1.43(-2) 1.43(-2) 1.60(-2) 1.43(-2) 1.43(-2) 1.68(-2) 1.43(-2)

Inhalation 9.25(-2) 9.20(-2) 3.40(-1) 5.13(-2) 5.09(-2) 2.58(-1) 5.22(-2) 5.16(-2) 3.25(-1) 5.57(-2) 5.49(-2) 5.23(-1) 2 Garden 2.05(-1) 1.99(-1) 1.71(0) 2.43(-1) 2.37(-1) 1.43(0) 5.02(-1) 4.95(-1) 2.30(0) 3 Meat 5.09(-2) 5.06(-2) 1.10(-1) 3.52(-2) 3.50(-2) 7.62(-2) 6.16(-2) 6.14(-2) 1.24(-2) 4 Goat Milk 1.45(-2) 1.36(-2) 2.58(-1) 1.84(-2) 1.72(-2) 3.84(-1) 3.66(-2) 3.46(-2) 7.60(-1) 6.84(-2) 6.49(-2) 1.81(0) 5 Cow Milk 6.79(-3) 6.33(-3) 1.84(-1) 9.47(-3) 8.77(-3) 2.76(-1) 2.03(-2) 1.90(-2) 5.48(-1) 3.89(-2) 3.74(-2) 1.31(0)

(a) See Table 11-12 for location data

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 1 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control Service Water, RE0833 Scintillation detector/detector well in service water line to discharge structure.

Digital indicator 10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Steam Generator Blowdown, RE0707 Scintillation detector/external to blowdown tank, drain to P98A/B suction.

Digital rate meter 10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation signal; isolates blowdown tank.

Radwaste Liquid Discharge, RE1049 Scintillation detector on radwaste liquid line to discharge structure.

Digital rate meter 10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, cirtuit failure. Isolates radwaste release.

Component Cooling Water, RE0915 Scintillation detector/piping, valves, and detector housing.

CC pump dP for flow.

Digital indicator 10-107 CPM.

5 x 10-5 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure; isolates component cooling water surge tank vent.

Circ Water Discharge, RE1323 Scintillation detector/piping, valves, sample pump and detector housing; circulating from mixing basin prior to discharge.

Digital indicator 10-107 CPM.

4 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Off-Gas Monitoring, RE0631 Scintillation detector/piping, valves and detector housing; main condenser steam jet air ejector noncondensibles to stack.

Digital rate meter analyzer 10-107 CPM.

1 x 10-5 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 2 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control Radwaste Area Ventilation, RE1809 Geiger-Mueller tube/piping, valves, sample pump and detector housing; air monitoring prior to discharge to stack.

Linear rate meter 0-106 CPM.

4 x 10-5 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure; isolates radwaste vent system.

Engineered Safeguards Pump Rooms Vent, RE1810, 1811 Geiger-Mueller tube; piping, valves, sample pump and detector housing; to stack, 2 systems, East and West rooms.

Digital rate meter 10-107 CPM.

1 x 10-4 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure; isolates pump room vent supply and exhausts.

Waste Gas Radiation, RE1113 Geiger-Mueller tube/piping, valves and detector housing; from the waste gas surge tank and waste gas decay tanks to stack.

Digital rate meter 10-107 CPM.

1 x 10-4 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure; isolation waste gas surge tank and decay tanks.

Containment Building Gas Monitoring System, RE1817 Geiger-Mueller tube/piping solenoid valves and detector housing; from 5 sample locations on (4) cooler fan discharges.

Linear rate meter 10-107 CPM.

1 x 10-4 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation and circuit failure.

Failed Fuel, RE0202 Scintillation detector/detector housing in letdown line.

Linear rate meter, 0-106 CPM, local.

N/A Alarm on high radiation, circuit failure.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 3 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control Steam Generator Blowdown Vent, RE2320 Scintillation detector/in well on blowdown vent line.

Digital rate meter,10-107 CPM.

2 x 10-5 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Turbine Building Sump, RE5211 Scintillation detector/piping, valves, and detector housing, sump pump discharge to drain.

Digital rate meter,10-107 CPM.

5 x 10-6 Ci/cm3 of Cs-137 equivalent.

Alarm on high radiation, circuit failure.

Radwaste Addition Vent, RE5711 Beta scintillation/dP across roughing filter used for flow.

Digital rate meter,10-107 CPM.

5 x 10-6 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation circuit failure; high radiation isolates radwaste addition vent.

Fuel Building Addition Vent, RE5712 Beta scintillation/dP across roughing filter used for flow.

Digital rate meter,10-107 CPM.

5 x 10-6 Ci/cm3 of Xe-133 equivalent.

Alarm on high radiation circuit failure; high radiation isolates fuel building vent.

RGEMS 2327 Scintillation detectors for beta, gamma, ionization chamber/piping, valves, filters, sample collection bottle; discharge to stack inlet.

Log count rate meter, recorded; stack flow, recorded; sample flow recorded;10-106 CPM beta (log),10-107 CPM (log),

gamma 1-107 mr/h (ion chamber) or 4 x 106 Ci/s digital.

1 x 10-6 Ci/cm3 of Xe-133 equivalent.

Alarm, set recorder speed, isolate samples on alert level. Alarm transfer flow to upper range on high radiation.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 4 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Monitoring Systems Detection Equipment/

Sampling Equipment Readout Equipment Sensitivity Alarm and Control RGEMS RE2325, RE2326 Scintillation detectors for beta, gamma, ionization chamber/piping, valves, filters, sample collection bottle; discharge to stack inlet.

Digital rate meter RIA-2325: 10-106 CPM RIA-2326: 10-107 CPM 3.9 x 10-7 Ci/cm3 of Xe-133 equivalent.

Alarm, set recorder speed, isolate samples on alert level. Alarm transfer flow to upper range on high radiation.

Main Steam, RE2323, 2324 Geiger-Mueller tube/in lead collimator adjacent to main steam lines.

Digital rate meter 10-107 CPM.

5 x 10-2 Ci/cm3 of dose equivalent I-131 Alarm on high radiation.

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-16 RADIATION PROTECTION Revision 21 Page 1 of 2 AREA RADIATION DETECTORS (a) Sensitivity for all instruments except containment detectors has energy dependence of +/-20% of the actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV (b) Sensitivity for containment detector instruments has an energy dependence of

+/-15% of actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV.

(c) Sensitivity for the radwaste monitor is +/-30% of the actual intensity over a photon energy spectrum from 80 keV to 1.33 MeV.

Instrument(a), (b)

Range Containment 590' Elev NW Side (b) 10 10 4 Rem/hr Containment 590' Elev SW Side (b) 10 10 4 Rem/hr Containment 590' Elev NE Side (b) 10 10 4 Rem/hr Containment 590' Elev SE Side (b) 10 10 4 Rem/hr East Engineering Safeguards Room 0.1-10 7 mrem/hr Radwaste Service Corridor 0.1-10 7 mRem/hr Radwaste Control Area (C-40 Panel) 0.1-10 7 mrem/hr 2.4 kV Switchgear Room (1C) 0.1-10 7 mRem/hr Control Lab Corridor 0.1-10 7 mrem/hr Access Control Station 0.1-10 7 mrem/hr Outside Cont Personnel Air Lock 607' Elev 0.1-10 7 mrem/hr Containment Purge Unit Room-North 0.1-10 7 mrem/hr Radwaste Demineralizer Room Roof 0.1-10 7 mrem/hr Control Room/Turbine Bldg Corridor 0.1-10 7 mrem/hr Control Room Entrance 0.1-10 7 mrem/hr Turbine Floor East Side 0.1-10 7 mrem/hr Health Physics Offices 0.1-10 7 mrem/hr Spent Fuel Pool-South 0.1-10 7 mrem/hr Air Room 590' Elev 0.1-10 7 mrem/hr Inside of Cont Personnel Air Lock 1.0-10 7 mrem/hr Containment 649' Elev Rx Cavity 1.0-10 7 mRem/hr Containment 649' Elev Rx Cavity 1.0-10 7 mRem/hr Containment Hi range-left channel 1-10 7 Rem/hr Containment Hi range-right channel 1-10 7 Rem/hr Decontamination Room 0.1-10 7 mrem/hr Evaporator "A" 0.1-10 7 mrem/hr Evaporator "B" 0.1-10 7 mrem/hr Evaporator Control Panel C-105 0.1-10 7 mrem/hr Waste Gas Decay Tank T-101, A, B & C 0.1-10 7 mrem/hr

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-16 RADIATION PROTECTION Revision 21 Page 2 of 2 AREA RADIATION DETECTORS (a) Sensitivity for all instruments except containment detectors has energy dependence of +/-20% of the actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV (b) Sensitivity for containment detector instruments has an energy dependence of

+/-15% of actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV.

(c) Sensitivity for the radwaste monitor is +/-30% of the actual intensity over a photon energy spectrum from 80 keV to 1.33 MeV.

Environmental Lab Entrance 0.1-10 7 mrem/hr Radwaste Packaging Area-East 0.1-10 7 mrem/hr Radwaste Packaging Area-West 0.1-10 7 mrem/hr Radwaste Demineralizer 649' Elev 0.1-10 7 mrem/hr Steam Dumps Area 0.1-10 7 mrem/hr Radwaste Monitors (c) Local Readout East Processing Building 1.0-10 5 mRem/hr East Storage Building 1.0-10 5 mRem/hr South Storage Building 1.0-10 5 mRem/hr (Not Used for Radwaste Storage at this time)

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-17 RADIATION PROTECTION Revision 28 Page 1 of 2 Primary Coolant Fission and Corrosion Product Activities for AST Dose Analyses Nuclide Activity*

Nuclide Activity*

(PCi/g)

Co-58 7.0E-03 Np-239 Co-60 8.0E-04 Pu-238 Cr-51 4.7E-03 Pu-239 Fe-55 1.8E-03 Pu-240 Fe-59 4.5E-04 Pu-241 Mn-54 2.4E-03 Am-241 Kr-85 5.3E-01 Cm-242 Kr-85m 1.2E+00 Cm-244 Kr-87 7.5E-01 I-130 1.1E-01 Kr-88 2.2E+00 Kr-83m 3.2E-01 Rb-86 1.5E-02 Xe-138 4.7E-01 Sr-89 5.4E-03 Xe-131m 4.5E-01 Sr-90 4.9E-04 Xe-133m 1.7E+00 Sr-91 1.5E-03 Xe-135m 4.8E-01 Sr-92 5.9E-04 Cs-138 7.0E-01 Y-90 6.4E-04 Cs-134m 4.6E-02 Y-91 1.8E-02 Rb-88 2.3E+00 Y-92 7.2E-04 Rb-89 5.8E-02 Y-93 4.4E-04 Sb-124 1.1E-03 Zr-95 1.2E-03 Sb-125 9.2E-03 Zr-97 4.9E-04 Sb-126 6.2E-04 Nb-95 1.2E-03 Te-131 1.5E-02 Mo-99 4.2E+00 Te-133 6.1E-03 Tc-99m 3.2E+00 Te-134 2.1E-02 Ru-103 1.2E-03 Te-125m 2.0E-03 Ru-105 1.4E-04 Te-133m 1.2E-02 Ru-106 5.3E-04 Ba-141 9.1E-05 Rh-105 5.5E-04 Ba-137m 2.5E+01 Sb-127 4.3E-02 Pd-109 Sb-129 2.4E-02 Rh-106 5.3E-04 Te-127 4.6E-02 Rh-103m 1.2E-03 Te-127m 7.2E-03 Tc-101 1.5E-02 Te-129 3.8E-02 Eu-154 Te-129m 2.2E-02 Eu-155 Te-131m 3.7E-02 Eu-156 Te-132 4.8E-01 La-143 1.1E-05 I-131 5.2E+00 Nb-97 8.1E-05 I-132 1.2E+00 Nb-95m 8.5E-06

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-17 RADIATION PROTECTION Revision 28 Page 2 of 2 Primary Coolant Fission and Corrosion Product Activities for AST Dose Analyses Nuclide Activity*

Nuclide Activity*

(PCi/g)

I-133 5.4E+00 Pm-147 1.2E-04 I-134 4.7E-01 Pm-148 1.7E-04 I-135 2.3E+00 Pm-149 3.0E-04 Xe-133 7.0E+01 Pm-151 8.3E-05 Xe-135 7.4E+00 Pm-148m 2.6E-05 Cs-134 4.9E+01 Pr-144 9.3E-04 Cs-136 4.3E+00 Pr-144m 1.6E-05 Cs-137 2.6E+01 Sm-153 Ba-139 4.3E-04 Y-94 1.4E-05 Ba-140 7.1E-03 Y-95 8.6E-06 La-140 3.4E-03 Y-91m 8.9E-04 La-141 2.4E-04 Br-82 2.5E-02 La-142 6.8E-05 Br-83 6.6E-02 Ce-141 1.1E-03 Br-84 2.7E-02 Ce-143 6.3E-04 Am-242 Ce-144 9.3E-04 Np-238 Pr-143 1.0E-03 Pu-243 Nd-147 4.3E-04

Activities based on 1% failed fuel. Listed activities are adjusted to Technical Specification limits for performance of AST dose calculations.

ML16120A610

Text

Navigation menu

Search