ML17226A097
Text
RBS USAR TABLE 1.3-7 COMPARISON OF INSTRUMENTATION AND ELECTRICAL SYSTEMS DESIGN CHARACTERISTICS 1 1 o o f f 1 1 A A u u g g u u s s t t 1 1 9 9 8 8 7 7 River Bend 2 Units Grand Gulf 2 Units Clinton 2 Units Perry 2 Units Zimmer 1 Unit Number of
offsite circuits 6 First unit-3 Both units-4 4 5 4 Number of
auxiliary power
sources 4 unit auxiliary
transformers; 4
reserve auxiliary
transformers 3 service
transformers [1
exclusively for
Engineered
Safety Features(ESF)]
4 unit auxiliary
transformers; 2
reserve auxiliary
transformers; 1
emergency
reserve auxiliary
transformer 4 - 1 unit
auxiliary
transformer per
unit; 1 startup
transformer per
unit 1 unit auxiliary
transformer; 2
startup transformers Number of
preferred power
circuits to ESF
ac buses 2 3 2 (third available on
manual transfer) 2 2 Number of ac ESF
buses per unit 3 3 3 3 3 Number of
standby ac power
supplies 6 (1/ESF bus) 6 (1/ESF bus) 6 (1/ESF bus) 6 (1/ESF bus) 3 (1/ESF bus)
Number of 125-V
dc systems
supplying ac ESF
buses 6 (1/ESF bus) 6 (1/ESF bus) 6 (1/ESF bus) 6 (1/ESF bus) 3 (1/ESF bus)
Sharing of
standby power
supplies and
interconnections
between safety
buses None None None None None
1 of 2 August 1987 COMMERCIAL NUCLEAR REACTORS COMPLETED, UNDER CONSTRUCTION, OR IN DESIGN BY GENERAL ELECTRIC AS OF APRIL 1981 Station Utility Rating (MWe) Year of Order Year of Startup Dresden 1 Commonwealth Edison 207 1955 1960 Humboldt Bay Pacific G&E 63 1958 1963 Kahl Germany 15 1958 1961 Garigliano Italy 150 1959 1964 Big Rock Point Consumers Power 71 1959 1965 JPDR Japan 11 1960 1963 KRB Germany 237 1962 1967 Tarapur 1 India 190 1962 1969 Tarapur 2 India 190 1962 1969 GKN Holland 52 1963 1968 Oyster Creek JCP&L 620 1963 1969 Nine Mile Point 1 Niagara Mohawk 610 1963 1969 Dresden 2 Commonwealth Edison 794 1965 1970 Pilgrim Boston Edison 655 1965 1972 Millstone 1 NUSCO 652 1965 1970 Tsuruga Japan 340 1965 1970 Nuclenor Spain 440 1965 1971 Fukushima 1 Japan 439 1966 1971 BKW KKM Switzerland 306 1966 1972 Dresden 3 Commonwealth Edison 794 1966 1971 Monticello Northern States Power 536 1966 1971 Quad Cities 1 Commonwealth Edison 789 1966 1972 Browns Ferry 1 TVA 1,067 1966 1974 Browns Ferry 2 TVA 1,067 1966 1975 Quad Cities 2 Commonwealth Edison 789 1966 1972 Vermont Yankee Vermont Yankee 514 1966 1972 Peach Bottom 2 Philadelphia Electric 1,065 1966 1974 Peach Bottom 3 Philadelphia Electric 1,065 1966 1974 James A. Fitzpatrick PASNY 821 1968 1975 Bailly NIPSCO 660 1966 1987 Shoreham LILCO 819 1967 1981 Cooper Nebraska PPD 778 1967 1974 Browns Ferry 3 TVA 1,067 1967 1977 Limerick 1 Philadelphia Electric 1,055 1969 1985 Hatch 1 Georgia 786 1967 1975 Fukushima 2 Japan 762 1967 1974 Brunswick 1 Carolina P&L 790 1968 1977 Brunswick 2 Carolina P&L 790 1968 1975 Arnold Iowa ELP 545 1968 1975 Fermi 2 Detroit Edison 1,056 1968 1980 Limerick 2 Philadelphia Electric 1,055 1969 1987 Hope Creek 1 PSE&G 1,067 1969 1985 Hope Creek 2 PSE&G 1,067 1969 1987
________________________
(1) Currently not scheduled (2) Indefinitely delayed 2 of 2 August 1987 Station Utility Rating (MWe) Year of Order Year of Startup Wm. H. Zimmer Cincinnati G&E 810 1969 1981 Chinshan 1 Taiwan 610 1969 1978 Caorso 1 Italy 822 1969 1977 Hatch 2 Georgia Power 795 1970 1979 La Salle 1 Commonwealth Edison 1,078 1970 1980 La Salle 2 Commonwealth Edison 1,078 1970 1981 Susquehanna 1 Pennsylvania P&L 1,050 1968 1982 Susquehanna 2 Pennsylvania P&L 1,050 1968 1983 Chinshan 2 Taiwan 610 1970 1979 WNP 2 WPPSS 1,103 1971 1981 Nine Mile Point 2 Niagara Mohawk 1,100 1971 1984 Grand Gulf 1 MSEI/MP&L 1,250 1972 1981 Grand Gulf 2 MSEI/MP&L 1,250 1973 1984 Kaiseraugst Switzerland 915 1971 1982 Fukushima 6 Japan 1,135 1971 1979 Tokai 2 Japan 1,135 1971 1977 River Bend 1 Gulf States Utilities 940 1972 1984 River Bend 2 Gulf States Utilities 940 1972 (1) Perry 1 Cleveland Electric Illum. 1,205 1971 1983 Perry 2 Cleveland Electric Illum. 1,205 1971 1985 Douglas Point 1 PEPCO 1,146 1972 (2) Douglas Point 2 PEPCO 1,146 1972 (2) Hartsville A-1 TVA 1,233 1972 1986 Hartsville B-1 TVA 1,233 1972 1988 Hartsville A-2 TVA 1,233 1972 1987 Hartsville B-2 TVA 1,233 1972 1990 Laguna Verde 1 Mexico 660 1972 1980 Leibstadt Switzerland 940 1972 1980 Kuosheng 1 Taiwan 992 1972 1980 Kuosheng 2 Taiwan 992 1972 1981 Clinton 1 Illinois Power 950 1972 1982 Clinton 2 Illinois Power 950 1972 1988 Montague 1 NUSCO 1,150 1973 (2) Allens Creek 1 Houston L&P 1,200 1972 1987 Skagit 1 Puget Sound P&L 1,290 1973 1987 Skagit 2 Puget Sound P&L 1,290 1974 1989 Black Fox 1 Public Service of Okla. 1,150 1973 1985 Black Fox 2 Public Service of Okla. 1,150 1973 1988 Laguna Verde 2 Mexico 660 1973 1981 Enel 6 Italy 982 1974 1983 Enel 8 Italy 982 1974 1984 Zimmer 2 CCDPP 1,220 1973 1984 Cofrentes Spain 975 1973 1980
1 of 2 August 1987 RBS USAR TABLE 1.5-1
SUMMARY
OF PSTF TESTS Test Series Number of Blowdowns Venturi Range (in) Top Vent Submergence Range (ft)
Initial Pressure (psia) Blowdown Type Number of Vents Area Pool/Vent Scaling Primary Objectives* 5701 21 2 1/8-3 5/8 2.0-15.5 1,050 Saturated steam 1 Full 1. Vent clearing
- 2. Full-scale Condensation demo
- 3. Drywell pressure 5702 17 2 1/8-3 5/8 1.93-11.97 1,050 Saturated steam 2 Full Vent clearing 5703 3 2 1/2-3 5/8 6.77-11.05 1,050 Saturated steam 3 Full Vent clearing 5705 4 1-4 1/4 6.0-8.0 1,065 Air 2 Full Pool swell scoping 5076 7 4 1/4 6.0-10.0 1,065 Air 2 Full 1. Pool swell
- 2. Impact loading 5707 22 2 1/8-3 7.5 1,050 Air and steam 3 Full Chugging 5801 19 2 1/8-3 5.0-10.0 1,050 Saturated steam 3 1/3 1. 1/3-scale demo
- 2. Pool swell
- 3. Roof density and P 5802 3 2 1/8-3 6.0 1,050 Saturated steam 3 1/3 Pool swell 5803 2 2 1/8-3 5.0-7.5 1.050 Saturated liquid 3 1/3 1. 1/3-scale demo
- 2. Liquid blowdown
RBS USAR TABLE 1.5-1 (Cont) 2 of 2 August 1987 Test Series Number of Blowdowns Venturi Range (in) Top Vent Submergence Range (ft)
Initial Pressure (psia) Blowdown Type Number of Vents Area Pool/Vent Scaling Primary Objectives 5804 5 2 1/8-3 5.0 1,050 Saturated steam 3 1/3 Roof density and P repeatability 5805 52 1-3 5.0-10.0 1,050 Saturated steam 3 1/3 Pool swell impact 5806 12 2 1/2-4 1/4 5.0-7.5 1,065 Air 3 1/3 Pool swell 5807 20 1-3 7.5 1,050 Saturated steam and liquid 3 1/3 Steam condensation 6002 13 2 1/8-3 5.0-10.0 1,050 Saturated steam 9 1/9 Multivent effect on pool swell load 6003 12 2 1/2 7.5 1,050 Saturated steam 9 1/9 Multivent effect on condensation loads
RBS USAR TABLE 1.5-2 1 of 4 August 1987 COMMITMENT ITEMS Additional Technical Information Reference Where Item Discussed
- 1. Preop Piping Vibration Test Program Section 3.9.2
- 2. Reactor Internals Preop Vibration Test Program Results Section 3.9.2 3. Dynamic Analysis of Reactor Internals and Piping Section 3.9
- 4. Seismic Qualification of Class IE Electrical Equipment Section 3.9.2.2
& 3.10 5. Environmental Qualification of Class IE Electrical Equipment Section 3.11
- 6. Electrical Isolation Devices Test Program Results Chapter 7 7. Fuel Experience Update - NEDO-10505 See Note A 8. Fuel Surveillance Program Results See Note B
- 9. Fuel Assembly Components Stress Report See Note C
- 10. Fuel Assembly Pressure and Temperature Capability See Note D 11. Fuel Assembly Dynamic Analysis See Note C 12. Fuel Assembly Analysis Method for Creep-Rupture See Note E
- 13. Fuel Assembly Design Limit for Instability See Note D
- 14. Fuel Channel Deformation Analysis Methods See Note F
- 15. Fuel Assembly Stress Limits See Note D
- 16. Fuel Rod 0.060 Inch Deflection Justification See Note D
- 17. Gadolinia Rods Performance Experience See Note G
- 18. Process Computer Performance Evaluation Accuracy Update See Note H 19. Lattice Physics Methods Verification See Note I 20. Boiling Water Reactor Simulator Verification See Note J
- 21. Void and Doppler Reactivity Coefficients See Note K
- 22. Full Power Scram Reactivity Function See Note L
- 23. Feedwater Flow Rate Uncertainty Justification See Note M
- 24. Resolution of Feedwater Nozzle Design and Verification See Note N
- 25. Description of WHAM Code and Loads on Internals During LOCA See Note O
RBS USAR TABLE 1.5-2 (Cont) 2 of 4 August 1987 Additional Technical Information Reference Where Item Discussed
- 26. Safety/Relief Valve Surveillance Program Details (Later)
- 27. Update PGCC LTR NEDO-10466 See Note P
- 28. Analytical Methods of Plant Transient Evaluation Chapter 15
- 29. ATWS See Note Q
- 30. Test Program for Safety/Relief Valve Solenoids See Note R
- 31. Fire Protection for PGCC See Note P, Appendix 9A
- 32. Primary Coolant Pump Seals Leakage Characteristics See Note S 33. Large Scale Mark III Test Appendix 6A
- 34. Environmental Design of Isolation Valves and Safety Related Equipment See Note T 35. Post LOCA Manual Operator Actions See Note U *36. Instrument and Control Systems Chapter 7
- 37. HPCS Onsite Electrical Systems Chapter 8
- 38. Fire Protection for Nuclear Island Conformance Appendix 9A
Development and Verification Test Programs
- 1. Fuel Surveillance Program See Note B
- 2. Safety Relief Valve Surveillance Program Section 5.2.2
- 3. Core Spray Distribution See Note V
- 4. Fast Scram Design Verification See Note W
- 5. Feedwater Nozzle Design Verification See Note N
- 6. Long Term Pipe Replacement Program Chapter 5
- 7. Instrumentation for Vibration and Loose Parts Detection X 8. Pressure Suppression Design Verification Y 9. Suppression Pool Dynamics Appendix 6A
- 10. Evaluate Effects of Relief Valve Blowdown Appendix 6A and Chapter 15
RBS USAR TABLE 1.5-2 (Cont) 3 of 4 August 1987 NOTES A. (1) Information Report, NEDO-20922-P, Experience with BWR Fuel through September 1974, 7/17/75 (2) Information Report, NEDO-21660-P, Experience with BWR Fuel through December 1976, 12/14/77
B. (1) Letter R. Engel to D. Ross, dated 7/11/77 (2) Letter G. G. Sherwood to D. Ross, dated 4/7/78
C. Licensing Topical Report, NEDO-21175, BWR/6 Fuel Assembly Evaluation of Combined Safe Shutdown Earthquake and Loss-
Of-Coolant Accident Loadings
D. Licensing Topical Report, NEDO-20948, BWR/6 Fuel Design, 2/20/76 E. Licensing Topical Report, NEDO-20606-A, Creep Collapse Analysis at BWR Fuel Using Safe-Colaps Model, Approved
by NRC 8/76
F. Licensing Topical Report, NEDO-21354, BWR Fuel Channel Mechanical Design and Deflections
G. Licensing Topical Report, NEDO-20943, Urania-Gadolinia Nuclear Fuel Physical and Irradiation Characteristics and
Material Properties
H. Licensing Topical Report, NEDO-20340, Process Computer Performance Evaluation Accuracy, 7/17/74
I. Licensing Topical Report, NEDO-20939-A, Lattice Physics Methods Verification, Approved by NRC 9/22/76
J. Licensing Topical Report, NEDO-20946-A, BWR Simulator Methods Verification, Approved by NRC 9/22/76
K. Licensing Topical Report, NEDO-20964, Generation of Void and Doppler Reactivity Feedback for Application to
BWR Design, 2/13/76
L. Appendix A of the ODYN Report
M. Letter G. G. Sherwood to E. Case, dated 5/1/78
N. Information Report NEDO-21821 Boiling Water Reactor Feedwater Nozzle/Sparger Final Report
RBS USAR TABLE 1.5-2 (Cont) 4 of 4 August 1987 NOTES (Cont)
O. Licensing Topical Report, NEDO-24048, Evaluation of Acoustic Pressure Loads on BWR/6 Internal Components, 12/1/77 P. Licensing Topical Report, NEDO-10466-A, Power Generation Control Complex Design Criteria and Safety Evaluation, Approved by NRC 7/31/78
Q. This topic to be addressed in a future amendment.
R. (1) Letter G. G. Sherwood to E. Case, dated 2/18/78 (2) Letter S. Varga to G. G. Sherwood, MFN-183-78
(3) Information Report NEDO-23978, ADS Solenoid Valve Reliability Demonstration
S. Licensing Topical Report, NEDO-24083, Recirculation Pump Shaft Seal Leakage Analysis, 12/12/78
T. Letter G. G. Sherwood to N. Denton, dated 10/11/78
U. Letter G. G. Sherwood to H. Denton, dated 3/22/79
V. (1) NEDO-10846, Boiling Water Reactor Core Spray Distribution (2) NEDO-20566-3 Effect of Steam Environment on BWR Core Spray Distribution
W. NEDO-24142, Fast Scram Control Rod Drive Qualification Program X. Letter, G. G. Sherwood to E. Case, dated 3/8/78
Y. Licensing Topical Report, NEDO-20533, The GE Mark III Pressure Suppression Containment System Analytical Model, approved by NRC 8/14/75 (Amended 6/30/78)
Revision 7 1 of 45 January 1995 RBS USAR TABLE 1.7-1 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS A. General Electric Drawings GE MPL No.
Drawing No. Title Rev. Date 7 C71-1060 944E981 Sh. 1 7 Reactor Protection System Motor Generator Set Control
Elementary Diagram 1 3/14/80 E33-1050 793E922 Sh. 1 through 13 Main Steam Positive Leak
Control System Elementary Diagram 2 6/14/79 C41-1050 828E234AA
Sh. 1 through 5 Standby Liquid Control
System Elementary Diagram 1 7/18/78 C61-1050 828E239AA
Sh. 1 through 10 Remote Shutdown System
Elementary Diagram 2 12/3/79 D17-1050 Sh. 1 through 17 Process Radiation Monitoring
System Elementary Diagram 1 5/9/78 B21-1090 828E445AA
Sh. 1 through 18 Nuclear Steam Supply Shutoff
System Elementary Diagram 2 12/14/79 C71-1050 828E531AA
Sh. 1 through 22 Reactor Protection System
Elementary Diagram 2 12/8/79 E12-1050 828E534AA
Sh. 1 through 24 Residual Heat Removal System
Elementary Diagram 2 12/14/79 E21-1050 828E535AA
Sh. 1 through 10 Low Pressure Core Spray
System Elementary Diagram 1 3/24/80 E22-1050 828E536AA
Sh. 1 through 9 High Pressure Core Spray
System Elementary Diagram 2 12/3/79
2 of 45 August 1987 RBS USAR TABLE 1.7-1 (cont)
A. General Electric Drawings (cont)
GE MPL No.
Drawing No. Title Rev. Date E22-1070 828E537AA
Sh. 1 through 12 High Pressure Core Spray
Power Supply System
Elementary Diagram 2 12/3/79 E51-1050 828E539AA
Sh. 1 through 15 Reactor Core Isolation
Cooling System Elementary
Diagram 1 3/12/80 B21-1060 851E225AA
Sh. 1 through 19 Automatic Depressurization
System Elementary Diagram 2 12/14/79 C51-1080 851E230AA
Sh. 1 through 59 (Info only)
Power Range Neutron
Monitoring System Elementary
Diagram 3 10/1/79 C11-1050 851E478AA
Sh. 1 through 12 Rod Control and Information
System Elementary Diagram 1 6/17/78 E31-1050 851E602AA
Sh. 1 through 5
and Sh. 7
through 12 Leakage Control System
Elementary Diagram 2 12/7/79 C51-1070 851E884AA
Sh. 1 through 32 Startup Range Neutron
Monitoring System Elementary
Diagram 3 1/10/80
B. Vendor Drawings Drawing No. Drawing Title Sh. Rev. Date D09003 (1) Stby Diesel Generator Outline 110 1/6/80 D67515 (1) Diesel Gen ac Term Box
Ass. -6 1/4/80 B72-07900-710 (1) Power Driven Potentiometer Schem -B 12/19/74 R-3917 (2)Installation Drawing - F 1/8/80 52459 (2) Eng Cont Pnl 1EGS*PNL 3A
& 3B Cable Routing -A 6/20/79 09-805-74039 (2) Exhaust Intake and CC Piping - Schem --12/19/79 09-810-74039 (2) Jacket Water Piping -
Schem. --12/20/79 00-500-74039 (2) Control Panel Installation -D 6/6/79 09-500-74039 (2) Control Panel Schematic 1 D 7/30/76 09-500-74039 (2) Control Panel Schematic 2 D 7/30/76 09-500-74039 (2) Control Panel Schematic 3 D 6/2/77 09-500-74039 (2) Control Panel Schematic 4 D 6/2/77 09-500-74039 (2) Control Panel Schematic 5 D 7/30/76
B. Vendor Drawings (cont)
Drawing No. Drawing Title Sh. Rev. Date 09-500-74039 (2) Control Panel Schematic 6 D 7/30/76 09-500-74039 (2) Control Panel Schematic 7 D 7/30/76 09-500-74039 (2) Control Panel Schematic 8 D 7/30/76 09-500-74039 (2) Control Panel Schematic 9 D 7/30/76 09-688-74039 (2) Eng and Aux Skid Wiring -
Schematic 1D 7/30/76 09-688-74039 (2) Eng and Aux Skid Wiring -
Schematic 2D 11/12/79 09-688-74039 (2) Eng and Aux Skid Wiring -
Schematic 3D 11/12/79 09-695-74093 (2) Eng Pneumatic Control -
Schematic -D 7/30/76 62-500-74039 (2) Panel - Wiring Connections 1B 11/12/79 62-500-74039 (2) Panel - Wiring Connections 2B 11/12/79 62-500-74039 (2) Panel - Wiring Connections 3B 11/12/79 62-500-74039 (2) Panel - Wiring Connections 4B 11/12/79 62-500-74039 (2) Panel - Wiring Connections 5B 11/12/79 09-820-74039 (2) Lube Oil Piping Schematic - -
12/27/74
B. Vendor Drawings (cont)
Drawing No. Drawing Title Sh. Rev. Date 09-825-74039 (2) Fuel Oil Piping Schematic - -
12/20/74 09-835-74039 (2) Starting Air Piping Schematic - - 12/17/79 64-500-74039 (2) Engine Generator Interconnection 1 C 11/14/79 64-500-74039 (2) Engine Generator Interconnection 2 C 11/14/79 D52986 (3) Schematic - Wiring
Diagram 1 6 8/13/80 D52986 (3) Diagram 2 6 8/14/80 D52986 (3) Schematic - Wiring
Diagram 3 6 8/13/80 D52986 (3) Schematic - Wiring
Diagram 4 6 8/12/80 8760D62 (4) Model B - Elec Hz Rbnr -
Bill of Mat 1 5 3/22/78 8760D62 (4) Model B - Elec Hz Rbnr -
Power Supply Panel 2 4 3/22/78 8760D62 (4) Model B - Elec Hz Rbnr -
Power Cont Schem 3 2 3/4/77 8760D62 (4) Model B - Elec Hz Rbnr -
Control Panel 4 3 3/22/78
B. Vendor Drawings (cont)
Drawing No. Drawing Title Sh. Rev. Date 8760D62 (4) Model B - Elec Hz Rbnr -
Encl. Arr. 5 4 3/22/78
______________________
(1) EP Portec
(2) Transamerica Delaval, Inc.
(3) Delta Switchboard Company
(4) Westinghouse Electrical Corporation
C. Stone & Webster Drawings 1.(Analog Wiring Diagrams)
Drawing No.
12210-AWD Title Rev.Date 0-0.1 AWD Notes 3 06-18-791-1.2 Sh. 1 Div I Analog Instr PNL 1H13*P841 Power Supply & Distribution 3 06-18-791-1.2 Sh. 2 Div I Analog Instr PNL 1H13*P841 Power Supply & Distribution 3 06-18-791-1.2 Sh. 3 Div I Analog Instr PNL 1H13*P841 Power Supply & Distribution 2 06-18-791-1.3 Sh. 1 Analog Instr PNL 1H13*P842 Power Supply
& Distribution 3 06-18-791-1.3 Sh. 2 Analog Instr PNL 1H13*P842 Power Supply
& Distribution 3 06-18-791-1.3 Sh. 3 Analog Instr PNL 1H13*P842 Power Supply
& Distribution 2 06-18-79 1-1.4 PNL 1H13*P601 Div III B.O.P. Instrument Power Supply & Distribution 3 06-18-79 1-1.17 B.O.P. Analo g Instr PN L 1H13*P84 1 Signal Proc
& Conv-Wi ring & Ass
'y (Unit IA) 3 06-18-79 1-1.18 B.O.P. Analog Instr PNL 1H13*P841
Signal Proc & Conv-Wiring & Ass'y (Unit
IB) 3 06-18-79 1-1.19 B.O.P. Analog Instr PNL 1H13*P841
Signal Proc & Conv-Wiring & Ass'y (Unit IC) 3 06-18-79 1-1.20 B.O.P. Analog Instr PNL 1H13*P841 Signal Proc & Conv-Wiring & Ass'y (Unit
ID) 3 06-18-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 1-1.21 B.O.P. Analog Instr PNL 1H13*P841
Signal Proc & Conv-Wiring & Ass'y (Unit
IE) 3 06-18-79 1-1.22 B.O.P. Analog Instr PNL 1H13*P841
Signal Proc & Conv-Wiring & Ass'y (Unit
IF) 3 06-18-79 1-1.24 B.O.P. Analog Instr PNL 1H13*P841
Signal Proc & Conv-Wiring & Ass'y (Unit
IJ) 2 06-18-79 1-1.25 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIA) 3 06-18-79 1-1.26 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIB) 3 06-18-79 1-1.27 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIC) 3 06-18-79 1-1.28 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IID) 3 06-18-79 1-1.29 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIE) 3 06-18-79 1-1.30 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIF) 3 06-18-79 1-1.32 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIJ) 2 06-18-79 1-1.33 B.O.P. Analog Instr PNL 1H13*P841
Signal Proc & Conv-Wiring & Ass'y (Unit
IG) 2 06-18-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 1-1.34 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIG) 2 06-18-79 1-1.40 B.O.P. Analog Instr PNL 1H13*P841 &
P819 Signal Resistor Units (SRU) 3 06-18-79 1-1.42 B.O.P. Analog Instr PNL 1H13*P842 &
P820 Signal Resistor Units (SRU) 3 06-18-79 1-1.46 Sh. 1 Safety-Related Instr Panel Div I 1H13*P841 Outline Dwg 3 06-18-79 1-1.46 Sh. 2 Safety-Related Instr Panel Div I 1H13*P841 Outline Dwg 3 06-18-79 1-1.46 Sh. 3 Safety-Related Instr Panel Div I 1H13*P841 Outline Dwg 3 06-18-79 1-1.46 Sh. 4 Safety-Related Instr Panel Div I 1H13*P841 Outline Dwg 2 06-18-79 1-1.46 Sh. 5 B.O.P. Instr Panel - Div I 1H13*P841 Outline Dwg 1 06-18-79 1-1.46 Sh. 6 B.O.P. Instr Panel - Div I 1H13*P841 Outline Dwg 1 06-18-79 1-1.46 Sh. 7 B.O.P. Instr Panel - Div I 1H13*P841 Outline Dwg 1 06-18-79 1-1.47 Sh. 1 Safety-Related Instr Panel Div II 1H13*P842 Outline Dwg 3 06-18-79 1-1.47 Sh. 2 Safety-Related Instr Panel Div II 1H13*P842 Outline Dwg 3 06-18-79 1-1.47 Sh. 3 Safety-Related Instr Panel Div II 1H13*P842 Outline Dwg 3 06-18-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 1-1.47 Sh. 4 Safety-Related Instr Panel Div II 1H13*P842 Outline Dwg 2 06-18-79 1-1.47 Sh. 5 B.O.P. Instr Panel - Div II 1H13*P842 Outline Dwg 1 06-18-79 1-1.47 Sh. 6 B.O.P. Instr Panel - Div II 1H13*P842 Outline Dwg 1 06-18-79 1-1.47 Sh. 7 B.O.P. Instr Panel - Div II 1H13*P842 Outline Dwg 1 06-18-79 1-1.54 B.O.P. Analog Instr PNL 1H13*P842
Signal Proc & Conv-Wiring & Ass'y (Unit
IIK) 2 06-18-79 1-1.55 B.O.P. Analog Instr PNL 1H13*P841
Signal Proc & Conv-Wiring & Ass'y (Unit
IK) 2 06-18-79 1-1.60 Panel 1H13*P601 Div III Trip & Calib
Unit-Wiring & Ass'y (Unit IIIA) 3 06-18-79 1-1.65 Panels 1H13*P808 & P870 Instr Pwr
Supply & Distribution 3 06-18-79 1-1.66 Panel 1H13*P808 Instr Pwr Supply &
Distribution 2 06-18-79 1-1.67 Panels 1H13*P863 & P870 Instr Pwr
Supply & Distribution 2 06-18-79 1-1.75 Sh. 1 Analog Instr Panel 1H13*P819 Div I Pwr Supply & Distribution 1 06-18-79 1-1.75 Sh. 2 Analog Instr Panel 1H13*P819 Div I Pwr Supply & Distribution 1 06-18-79 1-1.76 Sh. 1 Analog Instr Panel 1H13*P820 Div II Pwr Supply & Distribution 1 06-18-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 1-1.76 Sh. 2 Analog Instr Panel 1H13*P820 Div II Pwr Supply & Distribution 1 06-18-79 1-1.77 B.O.P. Analog Instr PNL 1H13*P819
Signal Proc & Conv - Wiring & Assy 1 06-18-79 1-1.78 B.O.P. Analog Instr PNL 1H13*P820 Div
II Signal Proc & Conv - Wiring & Assy 1 06-18-79 1-1.79 B.O.P. Analog Instr PNL 1H13*P819 Div.
I Trip & Calib Unit - Wiring & Assy 1 06-18-79 1-1.80 B.O.P. Analog Instr PNL 1H13*P820 Div
II Trip & Calib Unit - Wiring & Assy 1 06-18-79 1-1.81 B.O.P. Analog Instr PNL 1H13*P819 Div I
Trip & Calib Unit-Wiring & Assy 1 06-18-79 1-1.82 B.O.P. Analog Instr PNL 1H13*P820
Div II Trip & Calib Unit - Wiring &
Assy 1 06-18-79 1-1.85 Sh. 1 B.O.P. Instr Panel - Div I 1H13*P819 Outline Dwg 1 06-18-79 1-1.85 Sh. 2 B.O.P. Instr Panel - Div I 1H13*P819 Outline Dwg 1 06-18-79 1-1.85 Sh. 3 B.O.P. Instr Panel - Div I 1H13*P819 Outline Dwg 1 06-18-79 1-1.86 Sh. 1 B.O.P. Instr Panel - Div II 1H13*P820 Outline Dwg 1 06-18-79 1-1.86 Sh. 2 B.O.P. Instr Panel - Div II 1H13*P820 Outline Dwg 1 06-18-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 1-1.86 Sh. 3 B.O.P. Instr Panel - Div II 1H13*P820 Outline Dwg 1 06-18-79 8-9.4 Standby Generator Fuel 3 05-30-79 8-9.5 Standby Generator Fuel 3 05-30-79 8-9.6 Standby Generator Fuel 3 06-14-79 9-1.1 Reac Plant Component Cool Wtr 3 05-30-79 9-1.2 Reac Plant Component Cool Wtr 3 06-14-79 9-1.3 Reac Plant Component Cool Wtr 3 06-06-79 9-1.4 Reac Plant Component Cool Wtr 3 06-14-79 9-1.5 Reac Plant Component Cool Wtr 3 06-06-79 9-1.6 Reac Plant Component Cool Wtr 3 06-14-79 9-1.7 Reac Plant Component Cool Wtr 3 06-06-79 9-1.8 Reac Plant Component Cool Wtr 3 06-14-79 9-10.5 Service Water 4 06-14-79 9-10.6 Service Water 4 05-30-79 9-10.7 Service Water 4 06-14-79 9-10.8 Service Water 4 05-30-79 9-10.9 Service Water 4 06-14-79 9-10.10 Service Water 4 05-30-79 9-10.11 Service Water 4 06-14-79 9-10.12 Service Water 4 05-30-79 9-10.13 Service Water 6 06-14-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 9-10.14 Service Water 6 05-30-79 9-10.15 Service Water 4 06-14-79 9-10.16 Service Water 4 05-30-79 9-10.17 Service Water 5 06-06-79 9-10.18 Service Water 5 05-30-79 9-10.19 Service Water 4 06-06-79 9-10.20 Service Water 4 05-31-79 9-10.21 Service Water 4 06-06-79 9-10.22 Service Water 4 05-31-79 9-10.27 Service Water 5 05-30-79 9-10.28 Service Water 5 06-06-79 9-10.29 Service Water 4 06-06-79 9-10.30 Service Water 4 05-30-79 9-10.35 Service Water 3 05-30-79 9-10.36 Service Water 3 05-30-79 9-10.37 Service Water 3 05-30-79 9-10.38 Service Water 3 05-30-79 9-10.43 Radiation Monitoring System 2 06-06-79 9-10.44 Radiation Monitoring System 2 06-06-79 9-10.45 Service Water 2 05-30-79 9-10.46 Service Water 2 06-06-79 22-1.3 Reactor Plant Ventilation 3 06-14-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 22-1.4 Reactor Plant Ventilation 3 06-14-79 22-1.5 Reactor Plant Ventilation 3 06-14-79 22-1.6 Reactor Plant Ventilation 3 06-14-79 22-1.7 Reactor Plant Ventilation 3 06-14-79 22-1.8 Reactor Plant Ventilation 3 06-14-79 22-1.15 Radiation Monitoring System 3 06-06-79 22-1.16 Radiation Monitoring System 2 06-06-79 22-1.17 Radiation Monitoring System 2 06-06-79 22-1.18 Radiation Monitoring System 2 06-06-79 22-1.19 Radiation Monitoring System 2 06-06-79 22-1.20 Radiation Monitoring System 2 06-06-79 22-1.21 Radiation Monitoring System 2 06-06-79 22-6.3 Fuel Building Ventilation 3 05-30-79 22-6.4 Fuel Building Ventilation 3 06-14-79 22-6.7 Fuel Building Ventilation 2 05-30-79 22-6.8 Fuel Building Ventilation 2 06-14-79 22-6.9 Radiation Monitoring System 2 06-14-79 22-6.10 Radiation Monitoring System 2 06-14-79 22-6.11 Radiation Monitoring System 2 06-14-79 22-6.12 Radiation Monitoring System 2 06-14-79 22-9.1 Sh. 1 Control Building Ventilation 3 06-06-79 22-9.1 Sh. 2 Control Building Ventilation 3 06-06-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 22-9.2 Sh. 1 Control Building Ventilation 3 06-06-79 22-9.2 Sh. 2 Control Building Ventilation 3 06-06-79 22-9.3 Control Building Ventilation 3 06-06-79 22-9.4 Control Building Ventilation 3 06-06-79 22-9.5 Control Building Ventilation 3 06-06-79 22-9.6 Control Building Ventilation 3 06-06-79 22-9.13 Radiation Monitoring System 2 06-06-79 22-9.14 Radiation Monitoring System 2 06-06-79 22-9.15 Radiation Monitoring System 2 06-06-79 22-9.16 Radiation Monitoring System 2 06-06-79 22-12.1 Control Bldg - Chilled Water 3 06-06-79 22-12.2 Control Bldg - Chilled Water 3 06-06-79 22-12.3 Control Bldg - Chilled Water 3 06-06-79 22-12.4 Control Bldg - Chilled Water 3 06-06-79 22-12.5 Control Bldg - Chilled Water 3 06-06-79 22-12.6 Control Bldg - Chilled Water 3 06-06-79 22-12.7 Control Bldg - Chilled Water 3 06-06-79 22-12.8 Control Bldg - Chilled Water 3 06-14-79 22-12.9 Control Bldg - Chilled Water 3 06-14-79 22-12.10 Control Bldg - Chilled Water 3 06-06-79 27-15.3 Standby Gas Treatment 2 05-30-79 27-15.4 Standby Gas Treatment 2 05-30-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 27-15.5 Standby Gas Treatment 2 05-30-79 27-15.6 Standby Gas Treatment 2 05-30-79 27-15.7 Radiation Monitoring System 2 06-06-79 27-15.8 Radiation Monitoring System 2 06-06-79 27-29.1 Isolation Valve Seal Sys 1 06-06-79 27-29.2 Isolation Valve Seal Sys 1 06-06-79 27-29.3 Isolation Valve Seal Sys 1 06-06-79 27-29.4 Isolation Valve Seal Sys 1 06-06-79 27-29.5 Isolation Valve Seal Sys 1 06-06-79 27-29.6 Isolation Valve Seal Sys 1 06-06-79 27-29.7 Isolation Valve Seal Sys 1 06-06-79 27-29.8 Isolation Valve Seal Sys 1 06-06-79 27-29.9 Isolation Valve Seal Sys 1 06-06-79 27-29.10 Isolation Valve Seal Sys 1 06-06-79 27-29.11 Isolation Valve Seal Sys 1 06-06-79 27-29.12 Isolation Valve Seal Sys 1 06-06-79 33-2.1 Contmt Atmosphere Mon System 2 05-30-79 33-2.2 Contmt Atmosphere Mon System 2 06-06-79 33-2.3 Contmt Atmosphere Mon System 2 06-06-79 33-2.4 Contmt Atmosphere Mon System 2 06-06-79 33-2.5 Contmt Atmosphere Mon System 2 06-06-79 33-2.6 Contmt Atmosphere Mon System 2 06-06-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 33-2.7 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.7 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.7 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.8 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.8 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.9 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.9 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.10 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.10 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.11 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.11 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.12 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.12 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.13 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.13 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.14 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.14 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.15 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.15 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.16 Sh. 1 Contmt Atmosphere Mon System 2 06-06-79 33-2.16 Sh. 2 Contmt Atmosphere Mon System 1 06-06-79 33-2.23 Contmt Atmosphere Mon System 2 06-06-79 33-2.24 Contmt Atmosphere Mon System 2 06-06-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 33-2.25 Contmt Atmosphere Mon System 2 06-06-79 33-2.26 Contmt Atmosphere Mon System 2 06-06-79 33-2.27 Contmt Atmosphere Mon System 2 06-06-79 33-2.28 Contmt Atmosphere Mon System 2 06-06-79 33-2.29 Contmt Atmosphere Mon System 2 06-14-79 33-2.30 Contmt Atmosphere Mon System 2 06-11-79 33-2.31 Contmt Atmosphere Mon System 2 06-14-79 33-2.32 Contmt Atmosphere Mon System 2 06-11-79 33-2.33 Contmt Atmosphere Mon System 2 06-14-79 33-2.34 Contmt Atmosphere Mon System 2 06-11-79 33-2.35 Contmt Atmosphere Mon System 2 06-14-79 33-2.36 Contmt Atmosphere Mon System 2 06-11-79 33-2.37 Contmt Atmosphere Mon System 2 06-14-79 33-2.38 Contmt Atmosphere Mon System 2 06-11-79 33-2.39 Contmt Atmosphere Mon System 2 06-11-79 33-2.40 Contmt Atmosphere Mon System 2 06-11-79 33-2.41 Contmt Atmosphere Mon System 2 06-11-79 33-2.42 Contmt Atmosphere Mon System 2 06-11-79 33-2.43 Contmt Atmosphere Mon System 2 06-11-79 33-2.44 Contmt Atmosphere Mon System 2 06-11-79 33-2.45 Contmt Atmosphere Mon System 2 06-11-79 33-2.46 Contmt Atmosphere Mon System 2 06-11-79
C.1 (Analog Wiring Diagrams) (cont)
Drawing No.
12210-AWD Title Rev. Date 33-2.47 Contmt Atmosphere Mon System 2 06-11-79 33-2.48 Contmt Atmosphere Mon System 2 06-11-79 33-2.49 Radiation Monitoring System 2 06-06-79 33-2.50 Radiation Monitoring System 2 06-06-79 33-2.51 Contmt Atmosphere Mon System 3 06-06-79 33-2.52 Contmt Atmosphere Mon System 3 06-06-79 33-2.53 Contmt Atmosphere Mon System 3 06-06-79 33-2.54 Contmt Atmosphere Mon System 3 06-06-79 33-2.55 Radiation Monitoring System 2 06-06-79 33-2.56 Radiation Monitoring System 2 06-06-79 34-2.1 Fuel Pool Cool & Cleanup 5 06-14-79 34-2.2 Fuel Pool Cool & Cleanup 5 06-14-79 34-2.5 Fuel Pool Cool & Cleanup 5 06-14-79 34-2.6 Fuel Pool Cool & Cleanup 5 06-14-79 34-2.15 Fuel Pool Cool & Cleanup 4 06-14-79 34-2.16 Fuel Pool Cool & Cleanup 4 06-14-79
C. Stone & Webster Drawings(cont)
- 2. (Elementary Diagrams)
Drawing No.
12210-ESK Title Rev. Date 2A Instruction Drawing (ESK) Ident. Sys. 4 6-27-79 2B Wire No. Ident. Sys.
5 6-27-79 2C Wire No. Ident. Sys.
6 01-11-80 2D Wire No. Ident. Sys.
4 6-27-79 2E 480-V Swgr. Details 3 6-27-79 2F 13.8-kV Swgr. Details 5 01-11-80 2G Location Symbols 8 01-11-80 2H Equip. Location Symbols 8 4-29-80 2J 4.16-kV Swgr. Details 3 6-27-79 2K General Notes, Symbols & Abbreviations 4 6-20-79 2L Typ. MOV Circuits - Nuc. Sfty.-Related
Nonthrottling w/sl-in 1 3-15-77 2M Typ. MOV Circuits - Nuc. Sfty.-Related
Auto Throttling w/sl-in 1 3-15-77 2N Typ. MOV Circuits - Nuc. Sfty.-Related
Non-Auto Throt w/o sl-in 1 3-15-77 2P Typ. MOV Circuits - Non-Nuc. Sfty.
Nonthrottling Type 1 3-15-77 2Q Typ. MOV Circuits - Non-Nuc. Sfty.
Throttling Type 1 3-15-77 2R Typ. Pump Circuits 1 3-15-77 2S Typ. dc MOV Circuit Nonthrottling Types 1 3-15-77
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 2T Typ. MOV Circuits - Nuc. Sfty.-Related
Throttling Type w/o sl-in 1 3-15-77 2U Typ. dc MOV Circuit Throt & Nonthrot.
Types 1 3-15-77 2V Typ. Digital Isolator Circuits 2 6-20-79 2W Typ. Analog Isolator Circuits 2 6-20-79 3A Cont. Sw. Contact Diagrams 4 6-20-79 3B Cont. Sw. Contact Diagrams 6 6-20-79 3C Cont. Sw. Contact Diagrams 4 6-25-79 3D Cont. Sw. Contact Diagrams 4 6-20-79 3E Cont. Sw. Contact Diagrams 4 6-25-79 3F Cont. Sw. Contact Diagrams 5 6-25-79 3G Cont. Sw. Contact Diagrams 4 6-25-79 3H Cont. Sw. Contact Diagrams 5 6-25-79 3J Cont. Sw. Contact Diagrams 5 6-25-79 3K Cont. Sw. Contact Diagrams 4 6-25-79 3L Cont. Sw. Contact Diagrams 4 6-25-79 3M Cont. Sw. Contact Diagrams 5 6-25-79 3N Cont. Sw. Contact Diagrams 4 6-20-79 3P Cont. Sw. Contact Diagrams 2 6-20-79 3R Cont. Sw. Contact Diagrams 1 6-20-79 4A Nameplates Details 5 6-27-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 4CES 04 Outline - P680 - Feedwater Bench
Section 6 6-18-79 4CES 07 Key Plan - H13*680 - Principal Plant
Control Console 1 6-22-79 4CES 22 Outline - P851 - BOP Aux. Rly. Pnl.
Div. I 3 6-15-79 4CES 23 Outline - P852 - BOP Aux. Rly Pnl. Div.
II 3 6-15-79 4CES 39 Key Plan - Electrical Distribution
Board H13*P808 1 6-22-79 4CES 41 Outline - P808 - Elec. Dist. Bnch Bd.
Ins 86B & C, 87B & C, 88B & C (Elec.
Dist.) 4 6-22-79 4CES 43 Outline - P808 - Elec. Dist. Bnch Bd
Ins 83B & C, 84B & C (CMS H 2 Recombiner) 2 6-22-79 4CES 49 MIMIC 225 VDC H13*P808 - Elec. Dist.
Bench BD 2 6-22-79 4CES 50 Keyplan - P870 - Long Response Bd. 5 6-15-79 4CES 51 Outline - P870 - Long Response
Benchboard Ins. 51B & C, 52B & C (Mn &
Aux St Vents & Dr) 5 6-15-79 4CES 54 Outline - P870 - Long Response
Benchboard Ins. 55A, B & C (Stby Svce
WTR Div I) 6 6-26-79 4CES 55 Outline - P870 - Long Response
Benchboard Ins. 56A, B, & C (Stby Svce
Wtr Div II) 6 6-26-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 4CES 70 Keyplan - HVAC Board H13*P863 2 4-21-80 4CES 71 Outline - P863 - HVAC Benchboard
Inserts 71B & C, 72B & C, 73B & C 4 4-11-80 4CES 72 Outline - P863 - HVAC Benchboard
Inserts 74B & C, 75B & C 4 4-11-80 4CES 104 Equipt. List - P680 - Fd. Wtr. Bench
Section 6 6-18-79 4CES 122 Equipt. List - P851 - Aux. Rly. Pnl.
Div. I 3 6-15-79 4CES 123 Equipt. List - P852 - Aux. Rly. Pnl.
Div. II 3 6-15-79 4CES 141 Equip. List - P808 - Elec. Dist. Panel 5 6-22-79 4CES 151 Equipt. List - P870 - Mn. & Aux St
Vents & Drains 5 6-15-79 4CES 154 Equipt. List - P870 - Stdby. Serv Wtr.
Sect Div I 5 6-26-79 4CES 155 Equipt. List - P870 - Stdby Svce Wtr
Sect Div II 5 6-26-79 4CES 171 Equipt. List - P863 - HVAC Benchbd 3 6-27-79 4CES 204 Nameplate List - P680 - FDWTR Bench Sec 6 3-29-80 4CES 222 Nameplate List - P851 - Aux Rly PNL
Div. I 3 6-26-79 4CES 223 Nameplate List - P852 - Aux Rly PNL
Div. II 3 6-26-79 4CES 241 Nameplate List - P808 - Elec. Dist.
Panel 6 3-31-80
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 4CES 251 Nameplate List - P870 - Mn & Aux St
Vent & DRNNS 6 3-29-80 4CES 254 Nameplate List - P870 - STBY SERV WTR
SEC Div I 6 3-29-80 4CES 255 Nameplate List - P870 - STBY SERV WTR
SEC Div II 6 3-29-80 4CES 271 Nameplate List - P863 - HVAC Bench BD 4 4-10-80 4CES 601 Equipment List - P601 - Misc. BOP
Equip. for Mtg. on P601 3 6-26-79 4CES 625 Equipment List - P625 - Misc. BOP
Equip. for Mtg. on P625 1 4-25-78 4CPP01 Outline - Contmt 1&2 Purge Cont PNL
1CPP*PNL102 1 5-20-80 4CPP101 Equip. List - Contmt 1&2 Purge Cont PNL
1CPP*PNL102 1 5-20-80 4CPP 201 Nameplate List - Contmt 1&2 Purge
Control - PNL 1CPP*PNL102 1 5-20-80 4EGF 01 Outline - Div III Dsl Gen Cont PNL
1EGF*PNL101 1 5-22-80 4EGF 201 Nameplate List - DIV III Dsl Gen Cont
Pnl 1EGF*PNL101 1 5-22-80 4EGS 01 Outline - Standby Generators 1EGS*EG1B
Relay Panels 1EGS*PNL2A & PNL2B 2 6-03-80 4EGS 11 Outline - H13*P877 Inserts 31B & C, 32B
& C Stby Gen Cont & Distr Pnl 5 6-20-79 4EGS 101 Equip. List - Stby. Gen. EG1A & EG1B
Rly Pnls 1EGS
- Pnl 2A & 2B 2 6-03-80
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 4EGS 111 Eqpt. List - P877 Stby Dsl. Gen. EG1A, EG1B Pnl. (Div 1, 2) 5 6-18-79 4EGS 201 Nameplate List - STBY GEN EG1A & EG1B
RLY PNLS 1EGS*PNL2A & 2B 2 6-3-80 4EGS 211 Nameplate List - P877 Stby Gen EG14 &
15G1B PNL 1 (Div 1 & 2) EG1A & EG1B 5 6-26-79 5CSL 01 Low Press Core Spray Pump 6 7-09-79 5ENS 01 Standby Bus 1A Norm. Supply ACB 8 5-6-80 5ENS 02 Standby Bus 1B Norm. Supply ACB 8 5-06-80 5ENS 04 Standby Bus 1A Alt. Supply ACB 7 5-06-80 5ENS 05 Standby Bus 1B Alt. Supply ACB 8 5-06-80 5ENS 06 Standby Bus 1A Generator ACB 8 6-04-80 5ENS 07 Standby Bus 1B Generator ACB 8 6-04-80 5ENS 08 Standby XFMR 1EJS*X 1A FDR ACB 8 5-06-80 5ENS 09 Standby XFMR 1EJS*X2A FDR ACB 9 5-06-80 5ENS 10 Standby XFMR 1EJS*X1B FDR ACB 8 5-06-80 5ENS 11 Standby XFMR 1EJS*X2B FDR ACB 9 5-06-80 5ENS 12 Standby Gen 1A Neut BRKR 6 5-30-79 5ENS 13 Standby Gen 1B Neut ACB 6 6-14-79 5ENS 14 Standby Bus 1A Norm. Supply ACB 5 7-20-79 5ENS 15 Standby Bus 1B Norm Supply ACB 5 7-20-79 5ENS 16 Standby Bus 1A Alt. Supply ACB 5 7-20-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 5ENS 17 Standby Bus 1B Alt. Supply ACB 5 7-20-79 5ENS 18 Stby XFMR 1EJS*3A FDR ACB 5 5-06-80 5ENS 19 4.16-kV Swgr Stby XFMR 1EJS*3B FDR ACB 5 5-06-80 5RCS 03 Reac. Wtr. Recirc. Pump BRKR 1ENS*ACB
35 (3A) 1 8-14-79 5RCS 05 Reac. Wtr. Recirc. Pump BRKR 1ENS*ACB
37 (3B) 1 8-14-79 5RCS 07 Reac. Wtr. Recirc. Pump BRKR 1NNS*ACB
36 (4A) 1 8-1 5RCS 08 Reac. Wtr. Recirc. Pump BRKR 1ENS*ACB
38 (4B) 1 8-14-79 5RHS 01 Resid. Ht. Removal Pump 1E12-C002A 6 7-11-79 5RHS 02 Resid. Ht. Removal Pump 1E12-C002B 6 7-11-79 5RHS 03 Resid. Ht. Removal Pump 1E12-C002C 6 7-11-79 5SWP 04 Standby Svce. Wtr. Pump P2A 9 7-09-79 5SWP 05 Standby Svce. Wtr. Pump P2B 9 7-09-79 5SWP 06 Standby Svce. Wtr. Pump P2C 8 7-09-79 5SWP 07 Standby Svce. Wtr. Pump P2D 8 7-09-79 6CCP 04 Reac. Plant Cmpnt. Clg. Wtr. Isol.
Vlvs. 6 5-24-79 6CCP 05 Reac. Plant Cmpnt. Clg. Wtr. Isol.
Vlvs. 6 5-24-79 6CCP 07 Reac. Plant Cmpnt. Clg. Wtr. Isol.
Vlvs. 6 5-24-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6CCP 09 Reac. Plant Cmpnt. Clg. Wtr. Isol.
Vlvs. 5 6-18-79 6CCP 10 Reac. Plant Cmpt. Clg. Wtr. Isol. Vlvs. 5 5-24-79 6CCP 11 Reac. Plant Cmpnt. Clg. Wtr. Isol.
Vlvs. 5 5-24-79 6CCP 12 Reac. Plant Cmpnt. Clg. Wtr. Isol.
Vlvs. 6 5-24-79 6CNS 03 Cnds Mkup Contmt Isol. V's 7 5-30-79 6CPM 01 H2 Mixing Fans 5 5-30-79 6CPM 02 H2 Mixing Inlet Isol. Vlvs.
5 5-24-79 6CPM 03 H2 Mixing Inlet Isol. Vlvs.
5 5-24-79 6CPM 04 H2 Mixing Outlet Isol. Vlvs.
5 5-24-79 6CPM 05 H2 Mixing Outlet Isol. Vlvs.
5 5-24-79 6CPP 01 H2 Purge Disc. Valves 4 6-14-79 6DTM 16 Turb Plant Misc. Dr. V's 4 6-18-79 6EGA 01 Stby Gen. Air Starting Compressor 2 3-29-78 6EGA 02 Stby Gen. Air Starting Compressor 2 3-29-78 6EGF 01 Standby Dsl Gen. Fuel Oil Transfer Pump
1A 4 6-18-79 6EGF 02 Standby Dsl Gen. Fuel Oil Transfer Pump
1B 4 6-18-79 6EGF 03 Standby Gen. Fuel Oil Transfer Pump 1C 5 9-11-80
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6EGO 01 Standby Dsl Gen. Lube Oil Pump 2 3-20-78 6EGO 02 Standby Dsl Gen. Lube Oil Heater 2 3-20-78 6EGT 01 Standby Dsl Gen. Jacket Wtr. Circ.
Pumps 1 5-28-78 6EGT 02 Standby Dsl Gen. Jacket Wtr. Heaters 1 5-28-78 6EJS 01 Standby Bus 1A & 2A Supply ACBS 6 5-24-79 6EJS6 02 Standby Bus 1B & 2B Supply ACB 6 5-24-79 6EJS 03 Standby Bus Distr ACBS 5 5-24-79 6EJS 04 Standby Bus Distr ACBS 5 5-24-79 6EJS 05 Standby Bus Distr ACBS 6 5-24-79 6EJS 07 Standby Bus Distr ACBS 3 5-24-79 6FPW 03 Fire Prot Wtr. to Contmt Isol Valves 2 10-17-80 6FWS 09 Fdw. to Reac. Isol Valves 3 5-24-79 6GTS 01 Standby Gas Treatment Exhaust Fan A 5 5-24-79 6GTS 02 Standby Gas Treatment Exhaust Fan B 5 5-30-79 6GTS 03 Standby Gas Treatment Heater A 4 5-30-79 6GTS 04 Stdby Gas Trtmt Decay Ht Rem Fans A & B 4 5-24-79 6GTS 05 Standby Gas Treatment Heater H1B 5 5-24-79 6HCS 01 Hydrogen Recombiner 1HCS*RBNR 1A 3 10-17-80 6HCS 02 Hydrogen Recombiner 1HCS*RBNR 1B 3 10-17-80 6HVC 01 Cont. Room Air Handling Unit ACUIA 4 5-24-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6HVC 02 Standby Swgr. Air Handling Unit ACU2A 4 5-30-79 6HVC 03 Fltr. Train Bstr. Fans 5 11-13-79 6HVC 04 Standby Swgr. Return Fans 4 5-24-79 6HVC 05 Batt. Rm 1A Exhaust Fans 5 11-13-79 6HVC 06 Batt. Rm 1B Exhaust Fans 5 11-13-79 6HVC 07 Batt. Rm 1C Exhaust Fans 4 5-24-79 6HVC 08 Chiller Equipment Rm Air Handling Units 5 11-13-79 6HVC 12 Filter Train Decay Ht Removal Fans 8A, B 4 5-24-79 6HVC 13 Air Handling Units Inlet Isol V's 4 5-30-79 6HVC 14 Cont Rm Air Handling Unit Htr CH1A 2 5-24-79 6HVC 15 Cont Rm Air Handling Unit Htr CH1B 2 5-24-79 6HVC 17 Charcoal Filter Train Air Heaters 3 4-25-78 6HVC 18 Cont Rm Air Handling Unit ACU 1B 4 5-24-79 6HVC 19 Stdby Swgr Air Handling Unit ACU2B 3 5-30-79 6HVF 05 Fuel Bldg Exhaust Air Fans FN 3A, 3B 6 5-24-79 6HVF 12 Fuel Bldg Decay Heat Removal Fans 7A &
7B 3 5-24-79 6HVF 13 Fuel Bldg Filter Train Heater 2 5-30-79 6HVF 14 Fuel Bldg Filter Train Heater 2 6-14-79 6HVK 01 Cont Bldg Ch Wtr Compressor*CHL1A 3 5-24-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6HVK 02 Cont Bldg Ch Wtr Compressor*CHL1B 3 5-30-79 6HVK 03 Cont Bldg Ch Wtr Compressor*CHL1C 3 5-30-79 6HVK 04 Cont Bldg Ch Wtr Compressor*CHL1D 3 5-30-79 6HVK 05 Cont Bldg Chilled Wtr Pump P1A 4 5-30-79 6HVK 06 Cont Bldg Chilled Wtr Pump P1B 4 5-30-79 6HVK 07 Cont Bldg Chilled Wtr Pumps Disch V's 4 5-24-79 6HVK 08 Cont Bldg Ch Wtr Pmps Disch V's 4 5-24-79 6HVK 09 Cont Bldg Ch Wtr Cmpr Lube Oil Pumps 4 5-24-79 6HVK 10 Cont Bldg Ch Cmpsr Lube Oil Pumps 4 5-24-79 6HVK 11 Cont Bldg Ch Wtr CPRSN Tank MU. V's 5 5-24-79 6HVK 12 Cont Bldg Ch Wtr CPRSN Tank Altn MU.
V's 4 5-24-79 6HVK 13 Cont Bldg Backup Ch Wtr Pmps 4 5-24-79 6HVK 14 Cont Bldg Ch Wtr Sys Aux Control 3 5-30-79 6HVK 15 Cont Bldg Ch Wtr Sys Aux Control 3 5-30-79 6HVN 09 Contmt Unit Cooler Disch V 3 5-24-79 6HVN 10 Contmt Unit Cooler Isol V's 3 5-24-79 6HVN 11 Contmt Unit Cooler Isol V 3 5-24-79 6HVN 12 Contmt Unit Cooler Isol V 3 5-24-79 6HVP 01 Diesel RM "A" Emer Vent Exh Fan 2 6-11-79 6HVP 02 Diesel RM "B" Emer Vent Exh Fan 2 6-14-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6HVP 03 Diesel RM "A" Stdby Vent Exh Fan 2 6-18-79 6HVP 04 Diesel RM "B" Stdby Vent Exh Fan 2 6-18-79 6HVP 06 DG RMC Emergency Vent Exhaust Fan 2 6-18-79 6HVR 09 Cntmt Unit Clrs UC1A 6 6-14-79 6HVR 10 Cntmt Unit Cooler UC1B 6 5-30-79 6HVR 11 Aux Bldg Unit Clrs. UC2, UC3 3 5-24-79 6HVR 12 Aux Bldg Unit Clrs. UC4, UC6 4 9-24-80 6HVR 13 Aux Bldg Unit Clr UC5 3 5-24-79 6HVR 14 Aux Bldg Unit Clrs UC7 & UC8 3 5-24-79 6HVR 15 Aux Bldg Unit Clrs UC9 & UC10 3 5-24-79 6HVR 21 Annulus Mixing Fan 1HVR*FN11A 4 5-30-79 6HVR 22 Annulus Mixing Fan 1HVR*FN11B 4 5-30-79 6HVR 23 Cntmt Unit Clr UC1C 5 5-30-79 6HVR 28 480-V Swgr Aux Building Unit Cooler
UC11A 2 6-18-79 6HVR 29 480-V Swgr Aux Building Unit Cooler
UC11B 2 6-14-79 6IAS 04 Inst Air To Contmt Isol Valves 7 5-24-79 6LSV 01 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 02 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 03 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 04 Penetration Valve Leakage Cont.
1 6-18-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6LSV 05 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 06 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 07 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 08 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 09 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 10 Penetration Valve Leakage Cont.
1 6-18-79 6LSV 11 Penetration Valve Leakage Cont.
1 6-18-79 6RCS 03 Recirc Hydr Pwr Unit Isol Vlvs 1 10-17-80 6RCS 04 Recirc Hydr Pwr Unit Isol Vlvs 1 10-17-80 6RCS 05 Recirc Hydr Pwr Unit Isol Vlvs 1 10-17-80 6RCS 06 Recirc Hydr Pwr Unit Isol Vlvs 1 10-17-80 6SAS 01 Service Air To Contmt Isol Valves 8 10-17-80 6SFC 01 Fuel Pool Cooling Pump 1A 5 5-24-79 6SFC 02 Fuel Pool Cooling Pump 1B 5 6-6-79 6SFC 03 Fuel Pool Isol VV's 6 5-24-79 6SFC 04 Fuel Pool Isol VV's 6 5-24-79 6SFC 05 Fuel Pool Isol VV's 6 5-30-79 6SVV 01 Main St Saf & Relief Valve Sys - Contmt
Isol 1 6-14-79 6SWP 06 Serv Wtr System MOV's 5 5-24-79 6SWP 07 Serv Wtr System MOV's 5 5-24-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6SWP 08 Serv Wtr System MOV's 5 5-24-79 6SWP 09 Serv Wtr System MOV's 5 5-24-79 6SWP 10 Serv Wtr System MOV's 5 5-24-79 6SWP 11 Serv Wtr System MOV's 5 5-24-79 6SWP 12 Serv Wtr System MOV's 5 5-24-79 6SWP 13 Serv Wtr System MOV's 5 5-24-79 6SWP 14 Serv Wtr System MOV's 5 5-24-79 6SWP 15 Serv Wtr System MOV's 5 5-30-79 6SWP 16 Serv Wtr System MOV's 5 5-30-79 6SWP 17 Serv Wtr System MOV's 5 5-24-79 6SWP 18 Serv Wtr System MOV's 5 5-24-79 6SWP 19 Serv Wtr System MOV's Sh.15 5 5-24-79 6SWP 20 Serv Wtr System MOV's 5 5-24-79 6SWP 22 Serv Wtr System MOV's 5 5-24-79 6SWP 23 Serv Wtr System MOV's 5 5-24-79 6SWP 24 Serv Wtr System MOV's 6 5-24-79 6SWP 25 Serv Wtr System MOV's 6 5-24-79 6SWP 27 Cont Bldg Chiller Cond Recirc Pumps 3 5-24-79 6SWP 28 Cont Bldg Chiller Cond Recirc Pumps 3 5-24-79 6SWP 35 Service Water System MOV's 4 5-24-79 6SWP 36 Service Water System MOV's 4 5-24-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 6SWP 38 HX Service Water Disch. Valves 2 5-30-79 6SWP 39 Cond Swt Recirc Pump Inl V's 2 5-24-79 6SWP 40 Cond Swt Recirc Pump Inl V's 2 5-24-79 6SWP 45 Service Water System MOV's 1 6-14-79 6SWP 46 Service Water System MOV's 1 6-14-79 6WCS 02 Backwash Tk Dr Cntmt Isol Valves 5 5-30-79 6WCS 03 Backwash Tk Dr Cntmt Isol Valves 4 5-30-79 7CMS 01 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 02 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 03 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 04 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 05 Cntmt Atmosphere Monitoring Sys 4 6-18-79 7CMS 06 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 07 Cntmt Atmosphere Monitoring Sys 2 6-18-79 7CMS 08 Cntmt Atmosphere Monitoring Sys 2 6-18-79 7CMS 09 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 10 Cntmt Atmosphere Monitoring Sys 2 6-18-79 7CMS 11 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 12 Cntmt Atmosphere Monitoring Sys 2 6-18-79 7CMS 13 Cntmt Atmosphere Monitoring Sys 4 6-14-79 7CMS 14 Cntmt Atmosphere Monitoring Sys 3 6-18-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 7CMS 15 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 16 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 17 Cntmt Atmosphere Monitoring Sys 3 6-18-79 7CMS 18 Cntmt Atmosphere Monitoring System
Control 2 5-24-79 7CPP 01 H2 Purge Fan & Supply Valve 5 8-08-80 7DER 04 Reac Building Eqpt Dr Sump Isol Vlvs 7 5-24-79 7DFR 01 Reactor Bldg Fl Dr Sump Isol Valves 5 5-30-79 7GTS 01 Stdby Gas Trtmt Decay Heat Removal
AOD's 4 5-30-79 7GTS 02 Stdby Gas Trtmt Fan A AOD's & Aux
Control 4 5-30-79 7GTS 03 Stdby Gas Trtmt Fan B AOD's & Aux
Control 4 5-30-79 7GTS 05 Stdby Gas Trtmt Recirc AOD's Cont 2 5-24-79 7HVC 01 Cont Building Air-Cond Damper 5 5-24-79 7HVC 02 Cont Building Air-Cond Dampers 4 5-24-79 7HVC 03 Cont Building Air-Cond Damper 4 5-24-79 7HVC 04 Cont Building Air-Cond Dampers 4 5-24-79 7HVC 05 Cont Building Air-Cond Damper 4 5-24-79 7HVC 06 Cont Building Air-Cond Damper 4 5-24-79 7HVC 07 Cont Building Air-Cond Damper 5 5-24-79 7HVC 08 Cont Building Air-Cond Damper 4 5-24-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 7HVC 09 Cont Building Air-Cond Damper 4 5-24-79 7HVC 10 Cont Building Air-Cond MOD 4 5-24-79 7HVC 11 Cont Building Air-Cond Damper 4 5-24-79 7HVC 12 Cont Building Air-Cond Damper 4 5-24-79 7HVC 14 Cont Building Air-Cond Dampers 3 5-24-79 7HVC 15 Cont Rm Air-Cond Sys Dmpr Sig 2 5-30-79 7HVC 16 Cont Rm Air-Cond Sys Dmpr Sig 2 5-30-79 7HVF 01 Fuel Building Vent System Aux Cont 6 5-24-79 7HVF 02 Fuel Building Vent Systems Aux Cont 5 5-24-79 7HVF 03 Fuel Building Vent Systems Aux Cont 6 5-24-79 7HVF 04 Fuel Building Vent Systems Aux Cont 5 5-24-79 7HVF 07 Filter Train Dmpr Signals 2 5-30-79 7HVN 01 Contmt Unit Clr Temp Control V 3 6-18-79 7HVR 01 Reactor Plant Vent Dampers 4 5-24-79 7HVR 02 Reactor Plant Vent Dampers 4 5-30-79 7HVR 03 Reactor Plant Vent Dampers 4 5-30-79 7HVR 04 Reactor Plant Vent Dampers 4 5-30-79 7HVR 05 Reactor Plant Vent Dampers 3 5-30-79 7HVR 06 Reactor Plant Vent Dampers 4 5-30-79 7HVR 07 Reactor Plant Vent Dampers 4 5-30-79 7HVR 08 Reactor Plant Vent Systems 4 5-30-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 7HVR 09 Reactor Plant Vent Dampers 4 5-30-79 7HVR 10 Reactor Plant Vent Dampers 4 5-30-79 7HVR 16 Rx Plant Vent Dampers Aux Ckt 3 6-14-79 7ISCO1 BOP LOCA Initiation Contacts 2 6-18-79 7ISCO2 BOP LOCA Initiation Contacts 2 6-18-79 7ISCO3 BOP LOCA Initiation Contacts 2 5-30-79 7ISCO4 BOP LOCA Initiation Contacts 2 5-30-79 7ISCO5 BOP LOCA Isolation Contacts 2 6-18-79 7ISCO6 BOP LOCA Isolation Contacts 2 6-18-79 7ISCO7 BOP LOCA Isolation Contacts 2 6-18-79 7ISCO8 BOP LOCA Isolation Contacts 2 6-18-79 7ISCO9 BOP LOCA Isolation Contacts 2 5-30-79 7ISC10 BOP LOCA Isolation Contacts 2 5-30-79 7ISC11 BOP LOCA Isolation Contacts 2 5-30-79 7ISC12 BOP LOCA Isolation Contacts 2 5-30-79 7LSV01 Leakage Control System 1 5-30-79 7SCC 01 SWP Inoperability Indication 4 5-30-79 7SCC 02 SWP Inoperability Indication 4 5-30-79 7SCC 03 Standby DG System Inoperability
Indication 3 5-30-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 7SCC 04 Standby DG Sys Inoperability Indication 3 5-30-79 7SCC 05 Aux System Inoperability Indication 3 5-30-79 7SCC 06 Aux System Inoperability Indication 3 5-30-79 7SCC 07 Inoperability Indication P863 2 6-18-79 7SCC 08 Inoperability Indication P863 2 6-18-79 7SCC 09 Standby Bus Dist System Inop Ind 3 5-30-79 7SCC 10 Standby Bus Dist System Inop Ind 3 5-30-79 7SCC 11 120-V Control Ckt Inop Ind PNL863 2 6-18-79 7SCC 12 120-V Control Ckt Inop Ind PNL863 2 6-18-79 7SCC 13 HPCS PWR SUP 601 Inop Ind 2 6-18-79 7SCC 14 120-V Control Ckt Inop Ind 2 6-18-79 7SCC 15 120-V Control Ckt Inop Ind PNL863 2 6-18-79 7SCC 16 120-V Control Ckt Inop Ind PNL863 2 6-18-79 7SCC 17 120-V Control Ckt Inop Ind 2 6-18-79 7SCC 18 120-V Control Ckt Inop Ind 1 6-18-79 7SCC 19 SWP Inoperability Indication 1 6-27-80 7SCC 20 SWP Inoperability Indication 1 6-27-80 7SWP 05 Stdby Cooling Tower Aux Ckt Sh 1 4 6-6-79 7SWP 06 Stdby Cooling Tower Aux Ckt Sh 2 4 6-6-79 8EGS 01 Stdby Diesel Gen 1EGS*EG1A Prot & Mtr 5 4-25-80
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev.Date 8EGS 02 Stdby Diesel Gen 1EGS*EG1B Prot & Mtr 5 4-25-80 8EGS 03 Stdby Diesel Gen 1EGS*EG1A Prot & Mtr 8 4-25-80 8EGS 04 Stdby Diesel Gen 1EGS*EG1B Prot & Mtr 8 4-25-80 8EGS 05 Stdby Gen 1EGS*EG1A Fault Protection Trip 6 9-11-80 8EGS 06 Stdby Gen 1EGS*EG1B Fault Protection
Trip 6 9-11-80 8EGS 07 Stdby Gen 1EGS*EG1A Diff Protection
Trip 6 9-11-80 8EGS 08 Stdby Gen 1EGS*EG1B Diff Protection
Trip 6 9-11-80 8EGS 09 Stdby Gen 1EGS*EG1A & Swgr Bus Undv 9 9-30-80 8EGS 10 Stdby Gen 1EGS*EG1B & Swgr Bus Undv 9 9-30-80 8EGS 11 Stdby Gen 1EGS*EG1A Excitation 2 6-6-79 8EGS 12 Stdby Gen 1EGS*EG1A Excitation 2 6-6-79 8EGS 13 Stdby Bus 1ENS*SWG18 Undv. Prot. 2 9-30-80 8EGS 14 Stdby Bus 1ENS*SWG18 Undv. Prot. 2 9-30-80 8SPR 12 Pfd Sta Service XFMR Protection 2 7-25-79 8SYD01 Stby Bus 1ENS*SWG1A Synchronizing 6 5-6-80 8SYD 02 Stby Bus 1ENS*SWG1B Synchronizing 6 5-6-80 11BYS 06 125V Cont CKT Cont Rm Wiring Dc TST Bus 3 9-24-80 11CCP 01 Reac Plant Cmpnt Clg Wtr Aux Control 6 6-11-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 11CCP 02 Reac Plant Cmpnt Clg Wtr Aux Control 6 6-18-79 11CCP 04 Reac Plant Cmpnt Clg Wtr Aux Control 4 6-18-79 11CMS 01 24-V dc Cont Ckt Cntmt Atm Mon Sys Cont 2 6-18-79 11CMS 02 24-V dc Cont Ckt Cntmt Atm Mon Sys Cont 3 6-18-79 11CMS 03 24-V dc Cont Ckt Cntmt Atm Mon Sys Cont 2 6-18-79 11CMS 04 24-V dc Cont Ckt Cntmt Atm Mon Sys Cont 3 6-18-79 11CMS 05 24-V dc Control Ckt 2 6-11-79 11CMS 06 24-V dc Control Ckt Cntmt Atm Mon Sys
Cont 1 6-11-79 11DFR 03 24-V Cont Ckt Reactor Plant Floor
Drains 1 6-11-79 11EGA 01 Stdby Dsl 1A Rear Start Ckt 5 6-11-79 11EGA 02 Stdby Dsl 1A Fwd Start & Eng Stop Ckt 5 6-11-79 11EGA 03 Stdby Dsl 1B Rear Start Ckt 3 6-11-79 11EGA 04 Stdby Dsl 1B Fwd Start & Eng Stop Ckt 3 6-11-79 11EGA 05 Stdby Dsl Gen 1A Start, Stop & Aux Cont 2 6-18-79 11EGA 06 Stdby Dsl Gen 1B Start, Stop & Aux Cont 2 6-18-79 11EGF 01 Stdby Dsl Gen (dc) Fuel Oil Booster
Pmps 2 3-20-78
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 11EGF 03 Stdby Dsl Gen Fuel XFR Sys Aux Control 3 9-11-80 11EGF 04 Stdby Dsl Gen Fuel XFR Sys Aux Control 2 6-11-79 11EGS 02 Stdby Gen 1EGS*EG1A Excitation Circuit 2 6-11-79 11EGS 03 Stdby Gen 1EGS*EG1B Excitation Circuit 2 6-11-79 11EGS 06 Stdby Dsl Gen 1EGS*1EG1A 2 6-11-79 11EGS 07 Stdby Dsl Gen 1EGS*EG1B 2 6-11-79 11EJS 01 Stdby Bus Undv Trip Relays 4 6-11-79 11EJS 02 Stdby Bus Undv Trip Relays 3 6-11-79 11ENB 01 125-V dc Standby Swgr Battery Systems 3 9-19-80 11ENB 02 125-V dc Standby Swgr Battery Systems 3 9-19-80 11ENB 06 125-V dc Standby SWGR Battery System 2 9-19-80 11GTS 01 Stdby Gas Treatment Sys Control 2 6-11-79 11HVC 03 Cont Bldg A.C. Auxiliary Control 2 6-18-79 11HVC 04 Cont Bldg A.C. Auxiliary Control 2 6-18-79 11HVF 01 Fuel Bldg Ventilation Aux Cont 3 6-11-79 11HVK 01 Cont Bldg Ch Wtr Auxiliary Control 3 6-11-79 11HVK 02 Cont Bldg Ch Wtr Auxiliary Control 3 6-18-79 11HVR 01 24-V Cont Ckt Reac Plnt Vent Aux Ckt 3 6-11-79 11HVR 02 24-V Cont Ckt Reac Plnt Vent Aux Ckt 3 6-11-79 11HVR 03 125-V Cont Ckt Reac Plnt Vent Aux Ckt 3 6-11-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 11HVR 04 24-V Cont Ckt Reactor Plant Vent Aux
Ckt 2 6-11-79 11IAS 01 Instrument Air System 1 9-11-80 11IAS 02 Instrument Air System 1 9-11-80 11LSV 01 24-V Cont Ckt Leakage Control Sys - Aux
Ckt 1 6-11-79 11LSV 02 24-V Cont Ckt Leakage Control Sys - Aux
Ckt 1 6-11-79 11SFC 02 24-V dc Cont Ckt Fuel Pool Cool Sys Aux
Cont 5 6-18-79 11SFC 03 24-V dc Cont Ckt Fuel Pool Cool Sys Aux
Cont 3 6-18-79 11SWP 01 24-V Cont Ckt Stdby Serv Wtr Aux
Control 5 6-18-79 11SWP 02 125-V Cont Ckt Stdby Serv Wtr Aux
Control 6 6-18-79 11SWP 03 24-V Cont Ckt Stdby Serv Aux Control 5 6-18-79 11SWP 04 125-V Cont Ckt Stdby Serv Water Aux
Control 6 6-18-79 11SWP 05 125-V Cont Ckt Stdby Serv Wtr Aux
Control 4 6-18-79 11SWP 06 120-V Cont Ckt Stdby Serv Wtr Recorder
Ckt 4 6-18-79 11SWP 07 24-V Cont Ckt Stdby Serv Wtr Aux
Controls 3 6-18-79
C.2 (Elementary Diagrams)(cont)
Drawing No.
12210-ESK Title Rev. Date 11SWP 08 24-V Cont Ckt Stdby Serv Wtr Aux
Controls 3 6-18-79
C. Stone & Webster Drawings (cont)
- 3. (Instrument Location Drawings)
Drawing No.
12210-ESK Title Rev. Date 3E Instrument Piping - Turbine Building 2 3-1-80 3F Instrument Piping - Turbine Building 2 3-1-80 3G Instrument Piping - Turbine Building 2 3-1-80 310A Instrument Piping - Control Building 0 11/3/80 310B Instrument Piping - Control Building 0 11/3/80 310C Instrument Piping - Control Building 0 11/3/80 310D Instrument Piping - Control Building 1 11/3/80 RBS USAR TABLE 1.7-1 (cont)
C. Stone & Webster Drawings (cont)
- 4. (One Line Diagrams)
Drawing No.
12210-ESK Title Rev. Date 1A Main One-Line Diag-Key Dwg Pwr Destn 5 2/23/79 1C Main One-Line Diag - Sta Service
Relaying 6 9/09/80 1K 4160V Standby Bus 1ENS*SWG1A 8 6/23/80 1L 4160V Standby Bus 1ENS*SWG1B 8 6/23/80 1M 4160V Standby Bus 1E22*5004 1 12/7/76 1N Reac Recir Sys 1ENS*SWG3A,B;4AB 3 6/27/80 1AA 480V Standby Bus 1EJS*LDC1A & 2A 3 9/25/79 1AB 480V Standby Bus 1EJS*LDC1B & 2B 3 9/25/79 1ZD 125V DC Standby Bus A-1ENB*MCC1 1 9/23/76 1ZZG 125V DC Standby Bus A-1ENB*SWG01A 4 7/15/80 1ZZH 125V DC Standby Bus B-1ENB*SWG01B 4 7/15/80 1ZJ 125V DC Normal & Stdby Back-up Batt
Charger 4 7/15/80 RBS USAR TABLE 1.7-2 PIPING AND INSTRUMENTATION DIAGRAMS Revision 12 1 of 6 December 1999 USAR Figure No. Title 4.6-5a Control Rod Drive Hydraulic P&ID 4.6-5b Control Rod Drive Hydraulic P&ID 4.6-5c Control Rod Drive Hydraulic P&ID 4.6-5d Control Rod Drive Hydraulic P&ID 10 4.6-6 10 DELETED 5.1-3a Nuclear Boiler Instrumentation P&ID 5.1-3b Nuclear Boiler Instrumentation P&ID 12 5.1-3c Reference Leg Backfill System P&ID 5.4-2a Reactor Recirculation P&ID 5.4-2b Reactor Recirculation P&ID 5.4-8 Reactor Core Isolation Cooling P&ID 5.4-12a Residual Heat Removal - LPCI P&ID 5.4-12b Residual Heat Removal - LPCI P&ID 5.4-12c Residual Heat Removal - LPCI P&ID 5.4-15a Reactor Water Cleanup and Filter P&ID 5.4-15b Reactor Water Cleanup and Filter P&ID
5.4-17 DELETED 6.2-58 Standby Gas Treatment System P&ID 6.2-66 Hydrogen Mixing Purge and Recombiner System P&ID
6.2-67 DELETED 6.2-73a Containment Atmosphere and Leakage Monitoring P&ID 6.2-73b Containment Atmosphere and Leakage Monitoring P&ID
6.2-73c DELETED 6.3-1 HPCS System P&ID 6.3-4 LPCS P&ID 6.7-1a MSIV Positive Leakage Control P&ID 6.7-1b MSIV Positive Leakage Control P&ID 6.7-1c LSV-C3A Compressor Skid P&ID 6.7-1d LSV-C3B Compressor Skid P&ID 9.1-23a Fuel Pool Cooling System P&ID 9.1-23b Fuel Pool Cooling and Cleanup System P&ID 9.2-1a Service Water - Normal System P&ID 9.2-1b Service Water - Normal System P&ID 9.2-1c Service Water - Normal System P&ID 9.2-1d Service Water - Normal System P&ID 9.2-1e Service Water - Standby System P&ID 9.2-1f 4 Service Water - Normal System P&ID 9.2-1g 4 SWP Corrosion Coupon & Mounting Rack "c" Tunnel El. 67'-6" 9.2-1h Service Water-Normal P&ID 9.2-1j Service Water-Cooling P&ID 9.2-1k Service Water-Cooling P&ID 12 RBS USAR TABLE 1.7-2 (cont)
Revision 12 2 of 6 December 1999 USAR Figure No. Title 9.2-2a Closed Cooling Water - Reactor Plant System P&ID 9.2-2b Closed Cooling Water - Reactor Plant System P&ID 9.2-3a Makeup Water System P&ID 9.2-3b Makeup Water System P&ID 9.2-4a Makeup Demineralizer Water Treatment System P&ID 9.2-4b Makeup Demineralizer Water Treatment System P&ID 9.2-4c Makeup Demineralizer Water Treatment System P&ID 9.2-5 Waste Water Treatment System P&ID 9.2-6 Domestic Water 9.2-7a Closed Cooling Water Turbine Plant System P&ID 9.2-7b Closed Cooling Water Turbine Plant System P&ID 9.2-7c Closed Cooling Water Turbine Plant System P&ID 9.2-7d Closed Cooling Water Turbine Plant System P&ID 9.2-8a HVAC - Chilled Water Turbine Plant System P&ID 9.2-8b Plant and Control Building Chilled Water System P&ID 9.2-8c HVAC - Chilled Water System P&ID 9.2-8d HVAC - Chilled Water System P&ID 9.2-8e HVAC - Chilled Water System P&ID 9.2-8f HVAC - Chilled Water System P&ID 9.2-8g HVAC - Chilled Water System P&ID 9.2-8h HVAC - Chilled Water System P&ID 9.2-8j HVAC - Chilled Water System P&ID
9.2-9a DELETED
9.2-9b DELETED 9.2-10 Sanitary Sewage Treatment System P&ID 9.2-21a Condensate Makeup Storage and Transfer System P&ID 9.2-21b Condensate Makeup Storage and Transfer System P&ID 9.2-21c Condensate Makeup Storage and Transfer System P&ID 9.2-24a Cooling Tower Makeup Water, Cooler and Vacuum Priming System P&ID 9.2-24b Cooling Tower Makeup Water, Cooler and Vacuum Priming System P&ID 12 9.2-24c 12 Cooling Tower Makeup Water, Cooler and Vacuum Priming P&ID 9.3-1a Air-Instrument System P&ID 9.3-1b Air-Instrument System P&ID
9.3-1c 3 Air-Instrument System P&ID 9.3-1d Air-Instrument System P&ID 9.3-1e 3 Air-Instrument System P&ID
Revision 23 3 of 6 USAR Figure No. Title 12 9.3-1f Air-Instrument System P&ID 9.3-1g Air-Instrument System P&ID 9.3-1h Air-Instrument System P&ID 9.3-2a Air-Service and Breathing System P&ID 9.3-2b Air-Service and Breathing System P&ID 9.3-2c Air-Service and Breathing System P&ID 9.3-2d Air-Service and Breathing System P&ID 9.3-2e Air-Service and Breathing System P&ID 9.3-2f 12 Air-Service and Breathing System P&ID 9.3-3a Sampling-Turbine System P&ID 9.3-3b Turbine Plant Sampling System P&ID 9.3-3c Sampling Turbine Plant System P&ID 9.3-3d Turbine Plant Sampling System P&ID 9.3-3e Sampling Turbine System P&ID 9.3-3f Turbine Plant Sampling System P&ID
9.3-3g Turbine Plant Sampling P&ID 9.3-4a Sampling Reactor Plant System P&ID 9.3-4b Sampling Reactor Plant System P&ID 9.3-5a Sampling Radwaste System P&ID 9.3-5b Sampling Radwaste System P&ID 9.3-6a Drains - Floor and Equipment P&ID 9.3-6b Turbine Building Drains - Floor and Equipment P&ID 9.3-6c Drains - Floor and Equipment P&ID 9.3-6d Drains - Floor and Equipment P&ID 9.3-6e Turbine Building Drains - Floor and Equipment P&ID 9.3-6f Drains - Floor and Equipment System P&ID 9.3-6g Drains - Floor and Equipment System P&ID 9.3-6h Drains - Floor and Equipment System P&ID 9.3-6j Drains - Floor and Equipment System P&ID 9.3-7a Drains - Floor and Equipment P&ID 9.3-7b Drains - Floor and Equipment P&ID 9.3-7c Drains - Floor and Equipment P&ID 9.3-7d Drains - Floor and Equipment P&ID 9.3-7e Drains - Floor and Equipment P&ID 9.3-7f Drains - Floor and Equipment P&ID 9.3-7g Drains - Floor and Equipment P&ID 9.3-7h Drains - Floor and Equipment P&ID 9.3-7j Drains - Floor and Equipment P&ID 9.3-7k Drains - Floor and Equipment P&ID 9.3-7l Drains - Floor and Equipment P&ID 9.3-7m Drains - Floor and Equipment P&ID 9.3-7n Drains - Floor and Equipment P&ID 9.3-7p Drains - Floor and Equipment P&ID 9.3-8a Drains - Floor and Equipment P&ID 9.3-8b Drains - Floor and Equipment P&ID 9.3-8c Drains - Floor and Equipment P&ID
Revision 23 4 of 6 USAR Figure No. Title 9.3-8d Drains - Floor and Equipment P&ID 9.3-8e Drains - Floor and Equipment P&ID 9.3-9 Standby Liquid Control System P&ID 9.3-10a Drains - Floor and Equipment P&ID 9.3-10b Drains - Floor and Equipment P&ID 9.3-10c Drains - Floor and Equipment P&ID 9.3-11 Drains - Floor and Equipment P&ID 9.3-12a Drains - Floor and Equipment P&ID 9.3-12b Drains - Floor and Equipment P&ID 9.3-12c Drains - Floor and Equipment P&ID 9.3-12d Drains - Floor and Equipment P&ID 9.3-12e Drains - Floor and Equipment P&ID 9.3-12f Drains - Floor and Equipment P&ID
9.3-13a DELETED
9.3-13b DELETED 12 9.3-14 DELETED
9.3-15 DELETED 9.3-16a Drains - Floor and Equipment P&ID 9.3-16b Drains - Floor and Equipment P&ID 9.3-16c Drains - Floor and Equipment P&ID 9.3-16d Drains - Floor and Equipment P&ID
9.3-16e 12 Drains - Floor and Equipment P&ID 9.3-17 DELETED
9.3-18 DELETED
9.3-19 DELETED
9.3-20 DELETED
9.3.24a Suppression Pool Cleanup / Alt Decay Heat Removal P&ID 9.3.24b Suppression Pool Cleanup / Filter-Demin Skid P&ID 9.4-1a HVAC Control Building System P&ID 9.4-1b HVAC Control Building System P&ID 9.4-1c HVAC Control Building System P&ID 9.4-2a HVAC Fuel Building System P&ID 9.4-2b HVAC Fuel Building P&ID 9.4-3a HVAC Radwaste Building P&ID 9.4-3b HVAC Radwaste Building P&ID 9.4-4a HVAC Turbine Building P&ID 9.4-4b HVAC Turbine Building P&ID 9.4-4c HVAC Turbine Building P&ID 9.4-4d HVAC Turbine Building P&ID 9.4-5 HVAC Diesel Generator P&ID 9.4-6a HVAC Yard Structure P&ID 9.4-6b HVAC Yard Structure P&ID 9.4-6c HVAC Yard Structure P&ID 9.4-6d HVAC Yard Structure P&ID 9.4-7a HVAC - Containment Building P&ID RBS USAR TABLE 1.7-2 (cont)
Revision 23 5 of 6 USAR Figure No. Title 9.4-7b HVAC - Containment Building P&ID 9.4-7c HVAC - Containment Building P&ID 9.4-7d HVAC Auxiliary Building P&ID 9.4-7e HVAC Auxiliary Building P&ID 9.4-8 HVAC Drywell Cooling P&ID 1 9.4-9a HVAC Auxiliary Control Building 9.4-9b 1 HVAC Auxiliary Control Building 9.5-1a Fire Protection-Water and Engine Pump P&ID 9.5-1b Fire Protection-Water and Engine Pump P&ID 9.5-1c Fire Protection-Water and Engine Pump P&ID 9.5-1d Fire Protection-Water and Engine Pump P&ID 9.5-1e Fire Protection Water P&ID 9.5-2a Diesel Generator P&ID 9.5-2b Diesel Generator P&ID 9.5-2c Diesel Generator P&ID 9.5-2d Diesel Generator P&ID 9.5-4aDELETED
9.5-11 12 Hydrogen and CO 2 Generator P&ID 9.5-12 Fire Protection CO 2- P&ID 9.5-13 Fire Protection Halon P&ID
9.5-16a Hydrogen Injection 9.5-16b Oxygen Injection 10.1-2aDELETED 10.1-2bDELETED 10.3-1a Main Steam System P&ID 10.3-1b Main Steam System P&ID 10.3-1c Main Steam System P&ID
10.3-1d 12 SVV Compressor/Dryers P&ID 10.4-1 Air Removal - Condenser P&ID 10.4-2 Gland Seal and Exhaust P&ID 10.4-3a Circulating Water, Cooling Tower and Vacuum Priming Chilled Water P&ID 10.4-3b Circulating Water, Cooling Tower and Vacuum Priming Chilled Water P&ID 10.4-3c Circulating Water, Cooling Tower and Vacuum Priming Chilled Water P&ID 10.4-4 Hypochlorination and Chemical Feed System P&ID 10.4.4b Hypochlorination and Chemical Feed System P&ID 10.4-5a Condensate Demineralizer System P&ID 10.4-5b Condensate Demineralizer System P&ID 10.4-5c Condensate Demineralizer System P&ID 10.4-5d Condensate Demineralizer System P&ID 10.4-5e Condensate Demineralizer System P&ID 10.4-5f Condensate Demineralizer System P&ID
10.4-5g Condensate Demin System P&ID 10.4-6a Condensate System P&ID RBS USAR TABLE 1.7-2 (cont)
Revision 23 6 of 6 USAR Figure No. Title 10.4-6b Condensate System P&ID 10.4-6c Condensate Prefilter P&ID 10.4-6d Condensate System P&ID 10.4-7a Feedwater System P&ID 10.4-7b Feedwater System P&ID 10.4-7c Heater Feedwater P&ID 10.4-7d Heater Feedwater P&ID 10.4-7e Heater Feedwater P&ID 10.4-7f Heater Feedwater P&ID 10.4-7g Heater Feedwater P&ID 10.4-7h Heater Feedwater P&ID 10.4-7j Heater Feedwater P&ID 10.4-7k Heater Feedwater P&ID
10.4-7m Feedwater System OLNC Injection Skid P&ID 10.4-8 DELETED 11.2-1a Radwaste-Liquid P&ID 11.2-1b Radwaste-Liquid P&ID 11.2-1c Radwaste-Liquid P&ID 11.2-1d Radwaste-Liquid P&ID 11.2-1e Radwaste-Liquid P&ID 11.2-1f Radwaste-Liquid P&ID 11.2-1g Radwaste-Liquid P&ID 11.2-1h Radwaste-Liquid P&ID 11.2-1j Radwaste-Liquid P&ID
11.2-1k 1 1 Radwaste-Liquid P&ID 11.3-2a Offgas P&ID 11.3-2b Offgas P&ID 11.3-2c Offgas P&ID 11.3.2d Offgas P&ID 11.4-1 Radwaste-Solid P&ID
Revision 17 3 of 238 Regulatory Guide 1.3, Rev. 2 (June 1974)
Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors Project PositionRiver Bend has implemented Alternate Source Term (AST), per Regulatory Guide 1.183. Assumptions regarding the evaluation of radiological consequences of design basis loss-of-cooling accident were revised to comply with Regulatory Guide 1.183. 10 1014 USAR Sections - 3.1.2.16, 15.6.5 14
Revision 17 5 of 238 Regulatory Guide 1.5 (March 1971)
Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors Project PositionRiver Bend has implemented Alternate Source Term (AST), per Regulatory Guide 1.183. Assumptions regarding the evaluation of radiological consequences of a main steam line break were revised to comply with Regulatory Guide 1.183.
USAR Section - 15.6.4
RBSUSARTABLE1.8-1(Cont)Revision1415of238September2001RegulatoryGuide1.11(March1971)InstrumentLinesPenetratingPrimaryReactorContainmentProjectPosition-Comply,exceptforcontainmentanddrywellpressureanddifferentialpressuremonitoringpipelineswhicharedesignedasfollows:Thesepressureandpressuredifferentialtransmitters, valves,andassociatedpipingaresafety-related(QACategory I),SafetyClass2,andSeismicCategoryI.Eachlinehasonenormallylockedopenmanualvalvebetweenthetransmitterandthecontainment,andonenormallylocked closedmanualvalvewithcappedenddownstreamofthe transmitter.Whilethisarrangementdoesnotconformexactly toparagraphC.1.CofRegulatoryGuide1.11,itdoesfollow thephilosophyputforthinpartBoftheregulatoryguidein thatthefunctionthelineperformstakesprecedenceoverthe needtomaintaincontainmentleaktightintegrity.The transmitteroutputsignalsperformsafety-relatedfunctions orarepartofthepost-accidentmonitoringsystemwith indicationonthemaincontrolboard.Thesingleisolation valveineachlinemustremainopenunderallconditionsup toandincludingDBA.Thesimplestandmostreliablewayto ensurethatthisrequirementismetistofurnishanormally lockedopenvalvewithnoremotecontrolwhichwouldpossibly malfunction.TheentiresystemisSeismicCategoryI.These isolationvalvesareasclosetothecontainmentaspractical andareaccessible.14USARSections-6.2.4,7.1.2 14 RBSUSARTABLE1.8-1(Cont)Revision1416of238September2001RegulatoryGuide1.12,Rev.1(April1974)InstrumentationforEarthquakesProjectPosition-Comply,withthefollowingclarification:Responsespectrumrecordershaveafrequencyrangefrom1to32Hz.AlthoughParagraphC.4.bofthisregulatoryguide indicatesthatresponsespectrumrecordersshouldhavea frequencyrangefrom1Hzto30Hz,theNRChasrequesteda rangefrom1Hzto33Hz.Thisisduetothefactthatthe designresponsespectraforseismicdesignofnuclearpower plants(referenceRegulatoryGuide1.60)providesfora designresponsespectracoveringtherangefrom0.1Hzto 33Hz.AlthoughresponsespectrumrecordersonRBShavea frequencyrangefrom1Hzto32Hz,thedifferencebetween 32Hzand33Hzisalmostindistinguishable,andtherefore doesnotadverselyaffecttheintendedfunctional characteristicsoftheinstrumentation.Toprovidecoverage asrequiredbyRegulatoryGuide1.60,accelerometers(i.e.,
accelerationsensors)onRBSaresensitivetofrequenciesin therangeof0Hzto50Hz,andpeakshockrecorders(i.e.,
peakaccelerographs)aresensitivetofrequenciesinthe rangeof0Hzto52Hz.Theseprovisionsexceedthe requirementsofRegulatoryGuide1.12.14USARSections-3.7.4A,3.8.4 14
Revision 19 20 of 238 Regulatory Guide 1.16, Rev. 4 (August 1975) (For Comment)8 Reporting of Operating Information - Appendix A Technical Specifications and Technical Requirements Manual Project Position - With the approval of Operating License Amendment No. 145, effective 5/25/05, which deleted the Monthly Operating Report from Technical Specifications, this Reg. Guide is no longer applicable to River Bend Station.
8USAR Chapter - 16
Revision 17 29 of 238 Regulatory Guide 1.25 (March 1972)
Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors Project PositionRiver Bend has implemented Alternate Source Term (AST), per Regulatory Guide 1.183. Assumptions regarding the evaluation of radiological consequences of fuel handling accidents were revised to comply with Regulatory Guide 1.183. 1010USAR Section - 15.7.4
RBSUSARTABLE1.8-1(Cont)Revision1437of238September2001144.ParagraphC.1(o)-ThesecondarycontainmentisinterpretedtomeantheReactorShieldBuildingandtheAuxiliaryBuilding.
14Thestructures,systems,andcomponentsimportantto safetythatarerequiredtowithstandtheeffectsofan SSEandremainfunctionalhavebeenclassifiedas SeismicCategoryIitems.Allotherstructures, systems,andcomponents(thatarenotrequiredto performaccidentpreventionormitigationfunctions) aredesignedtootherthanSeismicCategoryI
requirements.14USARSections-3.2,3.7,5.4.8,7.1.2,8.3.1,9.1.1,9.1.2,9.1.3,9.2.1,9.3.5,9.4.5 14
Revision 22 41 of 238 Regulatory Guide 1.32, Rev. 2 (February 1977)
Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants
Project Assessment - Comply with the following clarification:
- 1. Regulatory Guides 1.9, 1.75, and 1.81, as referenced by Paragraphs C.1.f, C.1.d and C.1.e, and C.2.a, respectively, are addressed in separate compliance
statements.
- 2. Paragraph C.1.c
- The specified maximum interval of 18 months between battery service tests has been extended to 30 months.
USAR Sections - 8.2.1, 8.3.1, 8.3.2
RBSUSARTABLE1.8-1(Cont)Revision1443of238September2001RegulatoryGuide1.34(December1972)ControlofElect roslagWeldPropertiesProjectPosition-Comply.14USARSections-4.5.2,5.2.3,5.3.1 14
Revision 12 46 of 238 December 1999 Regulatory Guide 1.37 (March 1973)
Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants
12 Construction Position (Historical) - Comply, with the following modifications:
- 1. Paragraph C.3 - The water quality for final flushes of fluid systems and associated components is at least equivalent to the quality of the operating system
water, except for the oxygen content. Dissolved oxygen content of water cannot be maintained at reactor
quality during flushing of open systems.
- 2. Paragraph C.4 - Expendable materials, such as inks and related products, temperature-indicating sticks, tapes, gummed labels, wrapping materials (other than
polyethylene), water soluble dam materials, lubricants, NDT penetrant materials, and couplants, which contact
stainless steel or nickel alloy surfaces are in accordance with the RBS project position for Regulatory Guide 1.38. Contamination levels in expendable products are based upon safe practices and industrial availability. Contaminant levels are controlled such that subsequent removal by standard cleaning methods results in the achievement of final acceptable levels
which are not detrimental to the materials.
12
Revision 12 48 of 238 December 1999 Regulatory Guide 1.38, Rev. 2 (May 1977)
Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants
12 Construction Position (Historical) - Comply through the implementation of the following alternates to ANSI N45.2.2-1972, which is referenced by the regulatory guide:
- 1. Section 3.7.1(1) - Cleated, sheathed boxes up to 1,000 lb (rather than 500 lb) may be used. This type of box is safe for and has been tested for loads up to 1,000 lb. Other national standards allow this (Federal
Specification PPP-B-601). Special qualification testing
may be required for loads above 1,000 lb.
- 2. Section 3.7.2 - Skids or runners are used on containers with a gross weight of 100 lb or more. Skids or runners
are fabricated from 3x4-in-nominal lumber size minimum and laid flat except where this is impractical because
of the small dimensions of the container.
- 3. Section 4.3.4 - Since title to equipment generally changes hands at the time it is moved off the supplier dock into the carrier, inspections of packages and/or
preservative coatings are made immediately prior to loading rather than after loading, as presently indicated. To have this inspection and possible repair
performed after loading presents legal complications, as once the equipment enters the transport vehicle, the carrier has some responsibility and the customer has
ownership.
- 4. Appendix Section A3.4.1(4) and (5) - During printing of the standard, a transposition occurred between the last sentence of (4) and (5). The correct requirements are
as follows:
(4) "However, preservatives for inaccessible inside surface of pumps, valves, and pipe for systems
containing reactor coolant water shall be the
water flushable type." 12 12
12
12 12 12 12 RBSUSARTABLE1.8-1(Cont)Revision1453of238September2001RegulatoryGuide1.40(March1973)QualificationTestsofContinuous-DutyMotorsInstalledInsidetheContainmentofWater-CooledNuclearPowerPlantsProjectPosition-Comply.14USARSections-3.11,7.3.2 14 RBSUSARTABLE1.8-1(Cont)Revision1454of238September2001RegulatoryGuide1.41(March1973)PreoperationalTestingofRedundantOnsiteElectricPowerSystemstoVerifyProperLoadGroupAssignments14ProjectPosition(Historical)-Comply,withthefollowing clarification:
14RegulatoryGuide1.32isaddressedinaseparatecompliance statement.14USARSections(Historical)-8.2.1,14.2.12 14
RBSUSARTABLE1.8-1(Cont)Revision1462of238September2001c.IfEquation10resultsinS>3.0S mforferriticorausteniticsteels,thenthestressvalueinEquations12and13ofNB-3653.6mustnotbe
>2.4S m.14USARSections-3.6.1A,3.6.2A,3.6.2B,3.11.1 14 RBSUSARTABLE1.8-1(Cont)Revision1463of238September2001RegulatoryGuide1.47(May1973)BypassedandInoperableStatusIndicationforNuclearPowerPlantSafetySystemsProjectPosition-Complywiththefollowingclarifications:1.Anindicatorofbypass/inoperability,locatedinthemaincontrolroom,isprovidedforredundantordiverseportionsofeachautomaticallyactuatedsafetysystem.
Bypassindicationisprovidedforoperatoractionsthat renderthesysteminoperable.2.Bypassofredundantportionsofautomaticallyactuatedengineeredsafetyfeaturesupportsystemswarrants indicatorsthatmustbedifferentiatedfromsafety systembypassindicators.Toreflecttheimpactonthe safetysystem,bypassofthesupportsystemalso actuatesthesafetysystembypassindicatorsas indicatedinTable7.5-3.14USARSections-7.1.2,7.2.2,7.3.2,7.4.2,7.5.1,7.6.2,8.3.1 14 RBS USAR TABLE 1.8-1 (Cont)
64 of 238 August 1987 Regulatory Guide 1.48 (May 1973)
Design Limits and Loading Combinations for
Seismic Category I Fluid System Components
Project Position - Comply with the following modifications pertinent to non-NSSS components:
- 1. The analytical and testing procedures utilized in designing River Bend Station provide an acceptable basis to ensure the structural integrity of fluid system components and the structural integrity and operability of active components within fluid systems.
Criteria outlined in USAR Section 3.9.3 are consistent with the applicable provisions of Section III of the ASME Boiler and Pressure Vessel Code. Supplemental
criteria relating to design limits, loading
combinations, and component operability are drawn from
developing industry code activities, including the efforts of the ANSI N-45 Committees and the ASME Task Group on Design Criteria for Class 2 and 3 components.
The requirements thus developed and implemented presently provide an acceptable basis for the design of
ASME III Class 1, 2, and 3 components.
- 2. The criteria and procedures utilized in designing River Bend Station meet the intent of Regulatory Guide 1.48 and are intended to provide an alternate acceptable
basis for demonstrating compliance.
- a. ASME Code Class 1 Components Paragraphs C.4 (Active Pumps and Valves, Designed by Analysis) and C.5 (Active Valves, Designed by Standard or Alternate Design Rules)
Pumps are designed in accordance with the requirements of ASME III for normal, upset, emergency, and faulted plant conditions.
Maintenance of normal condition limits for upset, emergency, and faulted plant conditions, as suggested in Footnote 7 for emergency and faulted
plant conditions, are supplemental to Code requirements and are not consistent with industry
practice.
RBSUSARTABLE1.8-1(Cont)Revision1467of238September2001provideadequateassuranceofoperability.ThecriteriaoutlinedinthispositionareingeneralagreementwithCoderequirementsandcurrentindustrypractice.Specifications currentlyexistforimposingthecriteria
outlined.ThefollowingmodificationspertaintoNSSScomponentsgoverned byASMECodeClasses2and3:1.ParagraphC.6-(Vessels,DesignedtoSectionVIII,Division2)DesigncriteriaarebasedonASMECodeCase1607,acceptabletotheNRCinaccordancewithRegulatory Guide1.84.ASMEIII,SubsectionsNCandNDrules apply,ratherthanSectionVIII.2.ParagraphC.8-(Piping)DesigncriteriaarebaseduponASMECodeCase1606, acceptabletotheNRCinaccordancewithRegulatory Guide1.843.ParagraphsC.11andC.12(InactiveandActiveValves)DesigncriteriaarebaseduponASMECodeCase1635 (approvedbyRegulatoryGuide1.84)andNC/ND-3521.14USARSections-3.9.3A,3.9.3B 14 RBSUSARTABLE1.8-1(Cont)Revision1468of238September2001RegulatoryGuide1.49,Rev.1(December1973)PowerLevelsofNuclearPowerPlantsProjectPosition-Thepowerlevels,analyses,andevaluationsfornormal,transient,andaccidentconditionscomplywithRegulatoryGuide1.49withthefollowinginterpretation:TheassumedcorepowerlevelspecifiedinParagraphC.2isequalto1.02timestheproposedlicensedpowerlevel,which compensatesforpossibleinstrumenterrorsindeterminingthe powerlevel.Thewords"...equalto1.02..."areinterpretedto mean"...equaltoatleast1.02..."Thisinterpretationallows theanalysesandevaluationsdescribedinParagraphC.2tobe made,atanapplicant'sdiscretion,atasomewhathigherpower leveltoaccountforthemarginwhichmaybeprovidedinturbine generatordesignsaboveratedcapacity.Thisrationaleis discussedinParagraphC.3andis,therefore,alsoconsidered applicabletoParagraphC.2.14USARSections-5A.1,15.0.5,15B.3.1 14
Revision 17 71 of 238 Regulatory Guide 1.52, Rev. 2 (March 1978)
Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants Project Position: Comply, with the following clarifications and exceptions:1. Paragraph C.2.g - Abnormal pressure drops across all critical components of the SGTS, fuel building charcoal filter system, and the control room emergency filter system units activate an alarm in the main control
room. Flow through the units is indicated in the main control room, however no facilities to record these readings are provided. Computer input is provided to
record high-pressure alarms across critical components
and flow at the discharge from the system fans. The instrumentation provided is adequate for proper functioning of the system.2. Paragraph C.2.h - The following exceptions are taken to the requirement that "all instrumentation and equipment
controls should be designed to IEEE 279." a. All instruments and equipment controls that sense or process one or more variables and that act to accomplish the protective function are designed in
accordance with IEEE 279. These include sensors, signal conditioners, logic, and actuation device
control circuitry. (The protective function with which the subject guide is concerned is atmospheric cleanup to mitigate accident doses.) b. In addition, a very limited class of analog indicators is designed in accordance with selected
applicable paragraphs of IEEE 279. The basis for selecting specific indicators to be so designed is their significance to safety.
RBSUSARTABLE1.8-1(Cont)Revision1476of238September2001Systemsandcomponentsaredesignedandtestedtoensurethatuncontrolledreleaseofradioactivityis precludedand,therefore,satisfiestheintentofthis item.Manufacturer'sstandardsarefollowedforshaft sizesofsmalldampers.10.ParagraphC.4.a-ExceptionistakentofullcompliancewithSection2.3.8ofERDA76-21,i.e.,RBSdoesnot useanycommunicationsystem,decontaminationareasand showersarenotnearby,filtersarenotusedatduct inlets,andductinspectionhatchesarenotprovided.Thedesignofatmosphericcleanupsystemsminimizesthetimethatpersonnelareexposedtocontaminated components.Theguidelinesspecifiedinthisparagraph areconsideredtobegeneralguidesandfullcompliance isnotnecessary.11.ParagraphC.4.d-ESFatmosphericcleanupsystemsarerunaminimumof10hrpermonth.However,iffield dataconfirmthatitisunnecessarytorunthetrains 10hrpermonthtoreducetheamountofmoisture presentonthefilters,thisdecisionwillbe
reconsidered.StandbyESFatmospherecleanupsystemsaretestedonceeachmonthtoassurethatalloperatingcomponentsare functioningasrequired.Localheaterswithinthe filtersystemrunduringthetesttomaintain temperaturestoreducethebuildupofmoistureon adsorberandHEPAfilters.Ifmoistureisreducedto levelsequivalenttolevelsobservedwhenoperatingfor 10hours,andallcomponentsareobservedtofunction asrequired,thetestdurationmaybereducedfrom 10hours.12.ParagraphC.6.a-Thefollowingexceptionistakentotherequirementthat"newactivatedcarbonmeetsthe physicalpropertyspecificationsgiveninTable5.1of ANSIN509-1976(Ref.1)."Thecharcoaladsorbentnow commerciallyavailabledoesnotmeettherequirements ofANSIN509-1976butdoesmeetthoserequirementsof ANSIN509-1980.1413.ParagraphC.6.b-Thefollowingexceptionistakentotherequirementofconductinglaboratorytestsof representativesamplesasindicatedinTable2of RegulatoryGuide1.52.Representativesampleswillbe testedinaccordancewithASTMD3803-1989.
14 RBSUSARTABLE1.8-1(Cont)Revision1477of238September20011414.ParagraphsC.2.landC.3.n-ThefollowingexceptionsaretakentoSection4.12ofANSIN-509-1980formaximumallowableleakageforaircleaning effectivenessandductandhousingquality
requirements.
14HVACduct/filtersystemairleakageinexcessofthe allowableleakageforaparticularsectionofductwork couldoccuratequipment(e.g.,dampers,shafts,and fanshaftsthroughtheirhousingpenetration,etc).InareasorsectionsofsystemswhereleakageisinexcessofSection4.12requirements,ananalysisor testsareperformedtodemonstratethatsystem functionalcriteriaandradiationprotectionconcerns aremet.However,thetotalallowableleakageforthe entiresystemwillnotbeexceeded.HVACsystemswithinthecontrolroompressureboundary(CRPB)areleaktestedtominimizeairleakageto reasonablyachievablelevels.Aircleaning effectiveness,ductandhousingqualityrequirements, andhealthphysicsrequirementsleakratesarenot applicabletoHVACsystemswithintheCRPBasdiscussed
below.TheCRPBismaintainedatapositivepressurerelativetoitssurroundings,thusprecludinginfiltrationof potentiallycontaminatedair.Airinductworkupstream ofthefiltrationunitsisatanegativepressure relativetotheCRPBthusensuringinleakageand filtrationofair.Airleavingthefiltrationunitsis cleanandwillbeultimatelydischargedintothe controlroomenvironmentviaregisters.Thus,leakage ofairfromductworkdownstreamofthefilterswillbe cleanair.TheCRPBventilationsystemwillsatisfytheintentofaircleaningeffectiveness,ductandhousingquality, andhealthphysicsrequirementsbyverifyingthrough teststhattheflowsarebalanced,CRPBpositive pressureisachieved,andfiltereffectivenessis
maintained.1415.ParagraphsC.2.1andC.3.n-ThefollowingexceptionistakentoSection5.10.8.2ofANSIN509-1980,Fan PressureTest:
14 RBSUSARTABLE1.8-1(Cont)Revision1478of238September2001CertainisolatableportionsofHVACductworkassociatedwiththefuelbuilding(HVF),controlbuilding(HVC),
andthestandbygastreatment(GTS)charcoalfiltration systemswerefieldpressuretestedatpressuresless thantheirfanpeakpressure.TheHVFwastestedat15.5inW.G.,butthesystemfanpeakis19.4inW.G.TheHVCwastestedat20.0in W.G.,butthesystemfanpeakis23.5inW.G.TheGTS wastestedat15.5inW.G.,butthesystemfanpeakis 22.6inW.G.Theductworkfabricationcharacteristics(i.e.,sheetmetalgauge,reinforcementangles,andwelding)arethe sameforthesepressurerangesandencompassboththe actualtestedpressuresandthefanpeakpressure.Aprototypesampleductsectionrepresentingtheweakestductspoolwithinthethreesystems(i.e.,
longestductsectionwithminimumreinforcement)was fieldshoptestedatapressuregreaterthan23.5in W.G.Thisadditionaltest,conductedatapressure greaterthanthehighestpressureofallthreesystems willensurethatthestructuralintegrityofthose portionsoftheHVF,HVC,andGTSductsectionscanbe maintainediftheirfanpeakpressureoccurs.1416.ParagraphsC.2.1andC.3.n-ThefollowingexceptionistakentoSection5.10.8.1ofANSIN509-1980,Air LeakageTest:
14Airleakagetestswereconductedinthefieldto determinetheallowableairleakageontheisolatable portionsofductworkforthefuelbuilding(HVF),
controlbuilding(HVC),andthestandbygastreatment (GTS)charcoalfiltrationsystems.Thisquantitative leaktestingwasperformedatpressureslessthantheir fanpeakpressure.SomeportionsoftheHVFductswerepressuretestedat2.3inW.G.andotherportionsat15.5inW.G.,butthe systemfanpeakpressureis19.4inW.G.Someportions oftheHVCductswerepressuretested RBSUSARTABLE1.8-1(Cont)Revision1479of238September2001at2.0inW.G.andotherportionsat20.0inW.G.,butthesystemfanpeakpressureis23.5inW.G.Onesmall portionoftheGTSductswerepressuretestedat0.1in W.G.andotherportionsat18.1inW.G.,butthesystem fanpeakpressureis22.6inW.G.Ananalysiswasperformedusingtheactualfieldtestresults(i.e.,thevolumeofairleakedandthe pressurestheyweretestedat)inconjunctionwitheach systems'fanpeakpressure.Thismathematicalanalysis establishedwhatthevolumeofairleakagewouldhave beenhadthesystemsbeentestedattheirrespective fanpeakpressure.Acomparisonbetweentheactualtestedleakageandthecalculatedleakagewasperformedandanalyzedwith regardtoradiationprotectionconcerns.Ithasbeen determinedthatthecalculatedleakagesarebelowthe leakagenecessarytoensuresafeoperationofequipment andpersonnelasrequiredbySections4.12,Pressure BoundaryLeakage,and4.12.2,HealthPhysics Requirements,ofANSIN509-1980.1417.RegulatoryGuide1.25,asreferencedbyParagraphsC.1.bandC.1.c,andRegulatoryGuides1.32, 1.89,1.100,and1.118,asreferencedby ParagraphC.2.h,areaddressedinseparatecompliance
statements.USARSections-6.2.3,6.4.2,6.4.4,6.4.5,6.5.1,6.5.5,9.4.1,9.4.2,9.4.3,9.4.5,9A.3.5,12.3.3,Table3.2-1,Table6.5-1 14
RBSUSARTABLE1.8-1(Cont)Revision1482of238September20017Acertificateofcompliance(ProductQualityCertificationtoProcurementSpecification)isacceptedfromvendorsof manufacturedequipment.Activevendor'sfilesareaudited periodicallytoverifythatcompletedocumentationisbeing
maintained.
7Becauseoftheimpracticabilityofimposingtheregulatoryguiderequirementsonthestandardshopprocessusedinpaintingvalve bodies,handwheels,electricalcabinetryandcontrolpanels, loudspeakers,emergencylightcases,faceplates,solenoidvalve covers,valvehandles,smallsizepipewhiprestraints,andlike components,theregulatoryguideisnotinvokedfortheseitems sincethetotalsurfaceareaofsuchitemsisrelativelysmall whencomparedtothetotalsurfaceareaforwhichthe requirementsareimposed.InthecaseofaLOCA,thepaintdebris fromtheseitemsisinsignificantintermsofvolumeanddoesnot notadverselyaffectthefunctioningofsafety-relatedequipment.
Mostoftheseequipmentitemswithmiscellaneouscoatingsare locatedoutsidethedrywellwhereLOCAconditionsarenotsevere and,therefore,theyarenotlikelytobreakdown.Thetotal surfaceareaandestimatedvolumecoveredbypaintwhichisnot appliedinaccordancewiththerequirementsoftheregulatory guideisrecordedinFSARSection6.1.2.OperationPosition-Comply,withthefollowingclarification:7RBSshallcomplywiththeregulatorypositionestablishedinthisregulatoryguideinthatQAprogrammatic/administrative requirementsincludedthereinshallapplytomaintenanceand modificationactivitieseventhoughsuchrequirementswerenotin effectoriginally.Technicalrequirementsassociatedwith maintenanceandmodificationsshallbetheoriginalrequirements orbetter(e.g.,coderequirements,materialproperties,design margins,manufacturingprocesses,andinspectionrequirements).
714USARSections-3.8.4,6.1.2,9.1.414 RBS USAR TABLE 1.8-1 (Cont)
83 of 238 August 1987 Regulatory Guide 1.55 (June 1973)
Concrete Placement in Category I Structures
Project Position - Comply, with the following clarification:
The codes and standards used to control the quality of concrete placement are listed in Section 3.8.4.2. The pertinent portions of these documents are appropriately
selected in developing the specification requirements for mixing, delivering, testing, and placement of
concrete. The exceptions to or deviations from these codes and standards are listed in Section 3.8.4.6.
Exceptions to or deviations from the codes and standards listed in Section 3.8.4.2 are based on either current industry practices or adaptability to the
specific plant site conditions.
USAR Sections - 3.8.3, 3.8.4, 3.8.5
RBSUSARTABLE1.8-1(Cont)Revision1486of238September2001appropriateweldends,however,mustbeincluded.TherequirementsofNE-3365allowseveralmethodsof demonstratingcodecompliance.Bellowsanalysisper NE-3200shouldincludeconcurrentdesigndeflections andloadingsalongwithpressureinordertoreflect combineddesignconditions.3.Thetemperatureloadingsarenotincludedinthe"concurrentlyapplieddesignloadings."Stressescaused bytemperatureloadsaredefinedassecondarystresses.Thedefinitiongivenintheregulatoryguidefor"designloadings"includestemperatureloading.This producesonlysecondarystresses.Stressescausedby temperaturearenotusedwhereprimarystresslimits arespecified.Thisalsocomplieswithnote1of Table3.8.2-1ofSRP3.8.2.4.ThebucklingstresslimitsmeetthevaluesspecifiedinNE-3222,1977whenrigorousanalysiswhichconsiders theeffectsofgrossandlocalbucklingisused.For otherbucklingcriteriaNE-3133,1974isused.Thedesignlimitsspecifiedintheregulatoryguideforthebucklingstressareforshellswithcircumferential stiffeningringsonly.The1974editionofASMEIII didnotprovidecriteriaforcompressivestresses obtainedbyanalysis.The1977editiondoesprovide thecriteriaforthetypeofanalysisperformed.5.RegulatoryGuide1.48,asreferencedbyNote3,isaddressedinaseparatecompliancestatement.14USARSections-3.8.2,3D.2.3,Table1.3-814
THIS PAGE INTENTIONALLY LEFT BLANK
RBSUSARTABLE1.8-1(Cont)Revision1491of238September2001RegulatoryGuide1.60,Rev.1(December1973)DesignResponseSpectraforSeismicDesignofNuclearPowerPlantsProjectPosition-Comply.14USARSections-3.7,Table3.9B-3 14 RBSUSARTABLE1.8-1(Cont)Revision1492of238September2001RegulatoryGuide1.61(October1973)DampingValuesforSeismicDesignofNuclearPowerPlantsProjectPosition-Comply,withthefollowingclarification:PursuanttoparagraphC.3,dampingvalueslowerthanthosespecifiedinTable1oftheregulatoryguideareusedinsome instancestoensurethattheincreasedamplitudesof vibrationsanddynamicstressesarenotunderestimated.
Wherevibrationsanddynamicstressesareexpectedtoaffect theperformanceandsafetyoftheequipment,adetailed analysisisperformedtocomplywiththerequirementsof ParagraphC.3oftheregulatoryguide.14USARSections-3.7,6A.17.2,Table3.9A-3,Table3.9B-3,Table 3.10A-1 14
RBSUSARTABLE1.8-1(Cont)Revision1494of238September2001similar,innature,forallprotectionsystems.c.Thisdesignisincompliancewiththeapplica-blesectionofIEEE279(Paragraph4.16).d.Inaddition,manualinitiationisprovidedtoallowtheoperatortotakeearlyactionbasedonobservationofplantparameters.Itisnot treatedasabackuptoautomaticfeatures.
Operatoractionsarenotrequiredtocompen-sate forsinglefailures.14USARSections-7.1.2,7.3.2,7.4.2,7.6.2,8.3.1 14
Revision 19 98 of 238 Regulatory Guide 1.65 (October 1973)
Materials and Inspections for Reactor Vessel Closure Studs Project Position - Comply with the following clarification: Ultrasonic examination methods of ASME Code,Section XI, Appendix VIII Supplement 8 shall be used in lieu of the surface examination methods specified in Part C.4
.USAR Section - 5.3.2.1
RBSUSARTABLE1.8-1(Cont)Revision14101of238September2001RegulatoryGuide1.68,Rev.2(August1978)InitialTestProgramsforWater-CooledReactorPowerPlants14ProjectPosition(Historical)-Comply,withthefollowingclarificationsandexceptions:
14I.Clarifications1.ParagraphC.9(p.1.68-4)-RegulatoryGuide1.16isaddressedinaseparatecompliancestatement.2.AppendixA,paragraph1.0(p.1.68-6)Allsystemsarevisuallycheckedforexcessive vibrationduringthenormalcourseofthe preoperationaltestprogram.Specificattentionis directedtowardthesystemshereinlisted,onwhich portablevibrationmetersareused:a.ReactorRecirculationSystem b.ResidualHeatRemovalSystem c.HighPressureCoreSpraySystem d.LowPressureCoreSpraySystem e.ReactorCoreIsolationCoolingSystem.3.AppendixA,paragraph1.a(1)(p.1.68-6)Historically,GeneralElectricBWRshaveperformedhotfunctionaltestsduringinitialheatupfollowingfuel load.Systemexpansion,hanger,seismic,andrestraint checksareperformedatthistime.4.AppendixA,paragraph1.a(3)(p.1.68-6)Vibrationmonitoringofreactorinternalsisnot required.RiverBendStationisclassifiedas Non-Prototype,CategoryI,asdefinedby paragraphC.1.4ofRegulatoryGuide1.20(Kuo-ShengI isthedesignatedValidPrototype).Therefore,the inspectionprogramcorrespondingto RBS USAR TABLE 1.8-1 (Cont)
102 of 238 August 1987 paragraph C.3.1.3 of Regulatory Guide 1.20 is conducted at River Bend Station.
- 5. Appendix A, paragraph 1.b(3) (p.1.68-7)
Verification of proper mixing of the solution is not performed as part of the preoperational test program.
Just prior to fuel load, the solution is mixed and sampled using RBS Operating Procedures. At this time
the Standby Liquid Control System tank temperature, level, and concentration are verified per Technical
Specifications.
- 6. Appendix A, paragraph 1.c (p.1.68-7)
Regulatory Guide 1.118 is addressed in a separate compliance statement. There are no hardware items such as flow-limiting devices and snubbers associated with
reactor protection systems supplied by General Electric. With regard to sensors for vessel pressure, vessel level, containment pressure, and turbine control valve position, response time testing begins at the
source side of the primary sensor using a calibration rig and a response time measuring instrument.
Regarding position switches for main steam isolation
valves and turbine stop valves, response time measurements begin at the position switch. For neutron monitoring, response time measurements begin with an electronic input signal such that the average power range monitor or intermediate range monitor output
signal drives through the RPS scram setpoint.
- 7. Appendix A, paragraph 1.e. (p.1.68-8)
Regulatory Guide 1.68.1 is addressed in a separate compliance statement.
- 8. Appendix A, paragraph 1.g (3) (p.1.68-9)
Regulatory Guide 1.9 is addressed in a separate compliance statement.
RBSUSARTABLE1.8-1(Cont)Revision14104of238September200114.AppendixA,paragraphs4.s(p.1.68-15)and5.p (p.1.68-17)Seeclarification13.15.AppendixA,paragraphs5.aand5.b(p.1.68-16);5.r,5.s,5.v,and5.y(p.1.68-17);5.a.aand5.h.h.(p.1.68-18)14RiverBendStationisaBWRand,assuch,testconditionsarenotsetatprecisely25%,50%,75%,
100%,asforPWRs(seeparagraphC.8,p.1.68-4).
Figure14.2-4ofChapter14ofthisUSARdepicts"test conditions1through6,"thusfollowingthislineof
thought.14 16.AppendixA,paragraph5.k(p.1.68-17)RBSdoesnothaveaHPCIsystem.Furthermore,no scheduledstartuptestofHPCSinjectionisper-formed atRiverBendStation.HPCSinjectiontest-ingis performedduringthepreoperationaltestprogramunder simulatedaccidentconditions.Fullflowspraytests areconductedatflow,pumphead,systemresistance, elevation,anddesignreactorbackpressuretoverify thattheHighPressureCoreSpraySystemoperatesper GEdesigncriteria.SinceHPCSdoesnotrequiresteam asitsmotiveforce,itstestconditionrequirements aresimilartotheLPCSandRHRsystems.17.AppendixA,paragraph5.q(p.1.68-17)Individualradiationmonitoringsystemsmonitorthe mainsteamandoff-gasprocessesandactasfailedfuel detectorsonlyforisolationofgrossfissionproduct releases.Therearenostartuptestsoffailedfuel detectionsystems.Preoperationaltestingandperiodic surveillancetestsafterfuelloadensuretheproper operationoftheradiationmonitoringsystems.There arestartuptestswhichrequiredatacollectionfrom theradiationmonitoringsystemfortheoff-gassystem atvariouspowerlevels.Thisdataisusedtoset baselineconditions.
RBSUSARTABLE1.8-1(Cont)Revision14108of238September2001RegulatoryGuide1.68.1,Rev.1(January1977)PreoperationalandInitialStartupTestingofFeedwaterandCondensateSystemsforBoilingWaterReactorPowerPlantsProjectPosition(Historical)-Comply,withthefollowing clarification:ParagraphC.1.f-Planttransientsaresimulatedthroughstepchangesinfeedflow,steamflow,andlevel.Simulatedstepchangesinfeedflow,steamflow,andlevelareconsideredto adequatelysimulatethecontrolsystemtransientsforthe preoperationaltestprogram.ParagraphC.3-RegulatoryGuide1.16isaddressedinaseparatecompliancestatement.14USARSections(Historical)-10.4.7,14.214 RBSUSARTABLE1.8-1(Cont)Revision14109of238September2001RegulatoryGuide1.68.2,Rev1(July1978)InitialStartupTestProgramtoDemonstrateRemoteShutdownCapabilityforWater-CooledNuclearPowerPlants14ProjectPosition(Historical)-Comply,withthefollowing clarification:
14ParagraphC.5-RegulatoryGuide1.16isaddressedinaseparatecompliancestatement.14USARSection(Historical)-14.2.12 14
RBSUSARTABLE1.8-1(Cont)Revision14112of238September2001RegulatoryGuide1.70,Rev.3(November1978)StandardFormatandContentofSafetyAnalysisReportsforNuclearPowerPlants-LWREditionProjectPosition-TheRBSUSARhasbeenpreparedpursuanttotheformatsetforthinRegulatoryGuide1.70.AllregulatoryguidesreferencedbyRegulatoryGuide1.70areaddressedinseparate compliancestatements.14USARSection-2.1.3,3.5,7.1.1,7.1.2,8.1.7,15.0,Table1A-1 14
RBSUSARTABLE1.8-1(Cont)Revision14115of238September200114USARSections-4.5.2.4,5.2.3.3,5.2.3.4,5.3.1.4,10.3.6 14
12
o"the breaker or fuse that is automaticallyopened by fault current may be used as an isolationdevice provided that (a) the fault current underbolted and arcing faults conditions (assuming multiplefaults of all non-safety load and load current of all safety related circuits) will cause the nearestcircuit breaker or fuse to interrupt the fault currentprior to initiation of a trip of any upstreamprotection device, and (b) periodic testing of thecircuit breakers (visual inspection of fused and fuseholders) during every refueling must demonstrate thatthe overall coordination scheme under multiple faultsof non-safety related loads remains with the limitsspecified in the design criteria for the nuclear power plant."
RBSUSARTABLE1.8-1(Cont)Revision14121of238September2001RegulatoryGuide1.76(April1974)DesignBasisTornadoforNuclearPowerPlantsProjectPosition-Comply.14USARSection-3.3.2,3.8.4 14
Revision 14 125 of 238 September 2001 Regulatory Guide 1.80 (June 1974)
Preoperational Testing of Instrument Air Systems 14 Project Position (Historical) - Comply, with the following clarifications:
14 1. Paragraph C.1 - Regulatory Guide 1.68 is addressed in a separate compliance statement.
- 2. Paragraphs C.8, C.9, and C.10
An integrated loss of air test is impractical for two reasons:
- a. The large number of air operated components contained within a nuclear power plant precludes monitoring every one of them as they fail (e.g.,
BWRs would required monitoring 280-360 scram
valves alone); and
- b. An integrated loss of air test would not quantify the interaction between systems because the initial plant conditions during preoperational testing do not approximate, nor could they be made to approximate, normal operating conditions of an operating power plant. For example, it would be impossible to approximate operating conditions
such as condensate flow, feedwater flow (particularly on plants with steam driven feed
pumps), radwaste loads, feedwater heaters and
drains, etc.
Thus, with regard to simultaneous testing of the instrument air system at RBS, the "largest number of branches that can be adequately managed" would be a system (e.g., Control Rod Drive Hydraulic, Condensate Demineralizer, etc.) at most and in some cases a single
component (e.g., ventilation dampers). Therefore, the loss of instrument air test is conducted on a system basis as included in the instrument air system
preoperational testing.
- 3. Paragraph C.11 - Regulatory Guide 1.16 is discussed in a separate compliance statement.
RBSUSARTABLE1.8-1(Cont)Revision14126of238September200114USARSections(Historical)-9.3.1,14.2.12 14 RBS USAR TABLE 1.8-1 (Cont) 127 of 238 August 1987 Regulatory Guide 1.81, Rev. 1 (January 1975)
Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants
Project Position - Not applicable to RBS.
Revision 10 128 of 238 April 1998 Regulatory Guide 1.82 (June 1974)
Sumps for Emergency Core Cooling and Containment Spray Systems 10 Project Position - June 1974 Issue not applicable to RBS.
Revision 2, May, 1996:
Project Position - Compliance to Criteria C.2.2 and C.2.3 was incorporated into the ECCS Suction Strainer modifications that
address NRC Bulletin 96-03. (See subsection 6.3.2.2).
10 RBS USAR TABLE 1.8-1 (Cont) 129 of 238 August 1987 Regulatory Guide 1.83, Rev. 1 (July 1975)
Inservice Inspection of PWR Steam Generator Tubes
Project Position - Not applicable to BWRs.
Revision 14 130 of 238 September 2001 Regulatory Guide 1.84 Design and Fabrication Code Case Acceptability ASME Section III Division I Project Position - Comply with the following understandings:
- 1. Application to the commission for acceptance of selected code cases issued after the latest revision of the guide
may be made.
- 2. Acceptable code cases annulled by action of the ASME Council, but specified in procurement of components prior to annulment, remain valid for the duration of that
purchase order.
- 3. Code cases revised by action of the ASME Council, but specified in procurement of components prior to revision, remain valid for the duration of that purchase order.
Commitment to meet a specific revision of this guide has little
significance since the guide is revised as new code cases are
issued by the ASME and approved by the NRC. 14 USAR Sections - 3.8.2, 5.2.1, Table 3.2-8 14 RBS USAR TABLE 1.8-1 (Cont)
Revision 25 131 of 238 Regulatory Guide 1.85 Materials Code Case Acceptability ASME Section III Division I
Project Position - Comply with the following understandings:
- 1. Application to the commission for acceptance of selected code cases issued after the latest revision of the guide
may be made.
- 2. Acceptable code cases annulled by action of the ASME Council, but specified in procurement of components prior to annulment, remain valid for the duration of that
purchase order.
- 3. Code cases revised by action of the ASME Council, but specified in procurement of components prior to revision, remain valid for the duration of that purchase order.
Commitment to meet a specific revision of this guide has little
significance since the guide is revised as new code cases are
issued by the ASME and approved by the NRC.
USAR Section - 5.2.1
Note, this Regulatory Guide was withdrawn and the content combined with Regulatory Guide 1.84.
RBS USAR TABLE 1.8-1 (Cont) 132 of 238 August 1987 Regulatory Guide 1.86 (June 1974)
Termination of Operating Licenses for Nuclear Reactors
Project Position - The termination of the Operating License for River Bend Station will meet the intent of Regulatory Guide 1.86, dated June 1974. Although the method of decommissioning the station has not been selected from any of the alternatives discussed in this guidance, it is felt that these alternatives
provide viable means for decommissioning.
Reference - License Application
RBS USAR TABLE 1.8-1 (Cont) 133 of 238 August 1987 Regulatory Guide 1.87, Rev. 1 (June 1975)
Guidance for Construction of Class 1 Components in Elevated-Temperature Reactors (Supplement to ASME Section III Code Cases 1592, 1593, 1594, 1595, and 1596)
Project Position - Not applicable to BWRs.
Revision 12 134 of 238 December 1999 Regulatory Guide 1.88, Rev. 2 (October 1976)
Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records
12 1 Construction Assessment (Historical) - Comply, except with respect to Section 5.6, "Facility," in the referenced ANSI N45.2.9-1974, "Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power
Plants." The project complies with the requirements of ANSI N45.2.9-1979, Sections 5.6, "Facility," and 5.6.1, "Single Facility." After a trial-use period by the industry, the American National Standards Committee N45 revised and modified the facility requirements of ANSI N45.2.9-1974. The use of ANSI N45.2.9-1979, Sections 5.6 and 5.6.1 is consistent with
industry practice.
Operations Assessment
- Refer to Quality Assurance Program Manual.
1 12 RBSUSARTABLE1.8-1(Cont)Revision12135of238December199912811812USARSection-RefertoQualityAssuranceProgramManual.
RBS USAR TABLE 1.8-1 (Cont) 136 of 238 August 1987 Regulatory Guide 1.89 (November 1974)
Qualification of Class 1E Equipment for Nuclear Power Plants
Project Position - Comply, with the following clarifications:
Determination of the radiation dose used for qualification of Class 1E plant equipment takes into account design features such as the location of equipment within or outside the containment, local shielding, the time period required for
equipment operation, and spatial location.
These design features are applied in a conservative manner to realistically determine the radiation doses to which the devices must be qualified in addition to the other
environmental factors.
USAR Sections - 3.11, 7.1.2
RBS USAR TABLE 1.8-1 (Cont) 137 of 238 August 1987 Regulatory Guide 1.90, Rev. 1 (August 1977)
Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons
Project Position - Not applicable to River Bend Station.
RBS USAR TABLE 1.8-1 (Cont) 138 of 238 August 1987 Regulatory Guide 1.91, Rev. 1 (February 1978) (For Comment)
Evaluation of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plant Sites
Project Assessment - Comply.
USAR Section - 2.2.3.1
RBS USAR TABLE 1.8-1 (Cont) 139 of 238 August 1987 Regulatory Guide 1.92, Rev. 1 (February 1976)
Combining Modal Responses and Spatial Components in Seismic Response Analysis
Project Assessment - Comply with the following clarification:
Both the time-history and the response-spectrum methods are used. When the time-history method is used for combining the effects of three-dimensional earthquakes, the vector sum at
every step is used to calculate the maximum response. This
method precludes the consideration of modal spacing.
When response-spectrum method of modal analysis is used, all modes except the closely spaced modes are combined by the square-root-of-the-sum-of-the-squares (SRSS) method. However, for closely spaced modes, all piping and equipment in the
NSSS scope are evaluated to the requirements of the guide by
using the double sum method. In the non-NSSS scope the piping
and equipment are evaluated using the ten percent method.
USAR Sections - 3.7, 9.1.2
________________________
- NRC approved per Amendment 125 to Operating License (NPF-47).
Revision 18 140 of 238 Regulatory Guide 1.93 (December 1974)
Availability of Electric Power Sources Project Position
- Comply with the following exception*: The allowed outage time (AOT) for an inoperable Division I or Division II Emergency Diesel Generator (EDG) is 14 days rather than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
USAR Section/Chapter - 8.3, Chapter 16 RBS USAR TABLE 1.8-1 (Cont)
Revision 12 141 of 238 December 1999 Regulatory Guide 1.94, Rev. 1 (April 1976)
Quality Assurance Requirements For Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
12 Construction Assessment (Historical) - Comply, with the following clarification:
Maintenance and modification activities comparable in nature and extent to similar activities conducted during the construction
phase are controlled under the Operational QA program or an NRC
accepted construction QA program, as applicable.
Operational Assessment - Refer to Quality Assurance Program Manual. 12 RBS USAR TABLE 1.8-1 (Cont) 142 of 238 August 1987 Regulatory Guide 1.95, Rev. 1 (January 1977)
Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release
Project Assessment - Comply.
USAR Sections - 2.2.3, 6.4
RBS USAR TABLE 1.8-1 (Cont) 143 of 238 August 1987 Regulatory Guide 1.96, Rev. 1 (June 1976)
Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants
Project Position - Comply.
USAR Sections - 6.2.3, 6.7.1, 7.3.2, 9.3.6
Revision 17 144 of 238 1 Regulatory Guide 1.97, Rev. 3 (May 1983) 1Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident Project Position - River Bend Station concurs with the intent of the Regulatory Guide, which is to ensure that necessary and sufficient instrumentation exists at each nuclear power station for assessing plant and environmental conditions during and following an accident, as required by 10CFR50, Appendix A, and General Design Criteria 13, 19, and 64 and 10CFR50.67
.Implementation is performed except in those instances in which deviations from the letter of the guide are technically justified, when these deviations can be implemented without
disrupting the general intent, or when they are not applicable to
the River Bend Station. 128Additionally, one exception involves the containment and drywell hydrogen concentration range. River Bend Station's hydrogen analyzers have both a 0-10% scale and a 0-30% scale. However, because operator action to control hydrogen concentration only requires a 0 to 10% analyzer scale and the instrument accuracy is greatest on the 0 to 10% scale, calibration of the analyzers on
the 0 to 30% scale is not required for Emergency Operating Procedure (EOP) or Severe Accident Procedure (SAP) implementation
or to satisfy Technical Specification requirements.
Even though there are conditions that may allow hydrogen concentrations to exceed 10 vol-%, the required operator manual
action, as required for a TYPE A variable, such as hydrogen concentration, can not be accomplished, per the EOPs and SAPs, until hydrogen concentration is reduced to below 9 vol-% in the drywell, or below the hydrogen deflagration overpressure limit (HDOL) which ranges from 5.5 to 8.5 vol-% depending on containment pressure. Consequently, the 0 to 30 vol-% range
serves no function in guiding operator action. (See Table 7.5-2 Note 1 and correspondence RBG-34737 dated 3/28/91 and RBC-43182
dated 12/16/92.) 812The design basis accidents listed in Chapter 15 have been analyzed, and bounding and limiting conditions have been established. Instrumentation is included in the design to provide information about the effects of a transient or accident such as pressure increase, decreases in reactor coolant
inventory, and release of radioactivity.
RBSUSARTABLE1.8-1(Cont)Revision8144aof238August1996Section7.5addresseseachvariableintheRegulatoryGuideandpresentsRiverBendStation'sspecificposition.Thegeneral compliancewiththisRegulatoryGuideisdiscussedbelow.(The paragraphnumberscitedcorrespondtothoseintheRegulatory
Guide.)1.Accident-MonitoringInstrumentation1Paragraph1.4 1Instrumentsusedforaccidentmonitoringhavethepropersensitivity,range,transientresponse,andaccuracyto ensurethatthecontrolroomoperatorisabletoperformhis roleinbringingtheplantto,andmaintainingitin,asafe shutdownconditionandinassessingactualorpossible releasesofradioactivematerialfollowinganaccident.Accident-monitoringinstrumentsthatarerequiredtobeseismicallyandenvironmentallyqualifiedarequalifiedin accordancewiththeseismicandenvironmental RBS USAR TABLE 1.8-1 (Cont) 145 of 238 August 1988 conditions described in Sections 3.10 and 3.11, respectively. Quality assurance is performed under the River Bend Station QA program for design and construction.
The periodic checking, testing, calibration, and calibration
verification of accident-monitoring instrument channels is
in accordance with the appropriate sections of this USAR. 1 For Category I instruments, environmental qualification is in accordance with 10CFR50.49.
1 A third channel of instrumentation for Category I instruments is not provided. Cross checking with an independent variable bearing a known relationship to the variable being monitored is the method intended for verification. If this method is not available, the operator may perturb the measured variable to determine which channel
has failed by observing the response of each instrument. The guidance for physical independence of electrical systems identified in Regulatory Guide 1.75 is addressed in a
separate compliance statement. 1 River Bend Station concurs with the regulatory position for Category 2 instrumentation, except as modified above.
1 Instruments designated as Category 1 and 2 for variable Types A, B, and C are identified to optimize human factors engineering and presentation of information to the control room operator. This position is taken to clarify the intent of Regulatory Guide 1.97, which specifies that these instruments be easily discernible for use during accident
conditions. 1 1 RBS USAR TABLE 1.8-1 (Cont) 146 of 238 August 1988 1 Paragraph 1.5 1 It is the River Bend Station position that, in terms of accident monitoring, Table 1 of Regulatory Guide 1.97 does not represent a preferred number of variables and does not
necessarily represent preferred variable ranges or
instrumentation categories. The classification of instrumentation used to measure the variables as Category 1, 2, or 3 is in compliance with the intent and method used in
Details of the number of variables, ranges, instrumentation categories, and classification of instrumentation for River
Bend Station are provided in Table 7.5-2. 1 2. Instrumentation for Monitoring Systems Operation and Effluent Release 1 Comments presented under paragraph 1.4 above are applicable to the Type D and E variables described in Section 7.5.
Paragraph 2.4
Consideration was given to each of the noted items when the instrumentation listed in Section 7.5 was developed.
Paragraph 2.5 1 Concurrence with this paragraph, as stated in paragraph 1.5 above, is applicable to this regulatory position.
1 USAR Sections - 7.1.2, 7.5.2, 11.5.2, 12.3.4
RBS USAR TABLE 1.8-1 (Cont) 147 of 238 August 1987 Regulatory Guide 1.98 (March 1976) (For Comment)
Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor
Project Position - Comply, with the following exception and clarification, respectively:
- 1. Atmospheric dispersion rates and chi/Q values are determined in accordance with Regulatory Guide 1.145.
- 2. Dose conversion assumptions are made considering the guidance presented in this regulatory guide and in
USAR Section - 15.7.1
Revision 4 148 of 238 August 1991 4 Regulatory Guide 1.99, Rev. 2 (May 1988)
Radiation Embrittlement of Reactor Vessel Materials 4
Project Position - Comply.
USAR Sections - 5.3.1.4, 5.3.1.6, 5.3.2.1
RBS USAR TABLE 1.8-1 (Cont) 149 of 238 August 1987 Regulatory Guide 1.100, Rev. 1 (August 1977)
Seismic Qualification of Electric Equipment for Nuclear Power Plants
Project Assessment - Comply, with the following clarification:
Regulatory Guide 1.89 is addressed in a separate compliance statement.
USAR Sections - 3.7, 3.10, 8.3.1
RBS USAR TABLE 1.8-1 (Cont) 150 of 238 August 1987 Regulatory Guide 1.101, Rev. 1 (March 1977)
Emergency Planning for Nuclear Power Plants
Project Position - NRC withdrew Regulatory Guide 1.101 on September 24, 1980.
Reference:
- Letter from Robert B. Minogue, Director - Office of Standards Development, to all parties on the Regulatory Guide
Distribution List (Division 1), dated 9/24/80.
RBS USAR TABLE 1.8-1 (Cont) 151 of 238 August 1987 Regulatory Guide 1.102, Rev. 1 (September 1976)
Flood Protection for Nuclear Power Plants
Project Position - Comply.
USAR Section - 3.4 RBS USAR TABLE 1.8-1 (Cont) 152 of 238 August 1987 Regulatory Guide 1.103, Rev. 1 (October 1976)
Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments
Project Position - Not applicable to RBS.
RBS USAR TABLE 1.8-1 (Cont) 153 of 238 August 1987 Regulatory Guide 1.104 (February 1976)
Overhead Crane Handling Systems for Nuclear Power Plants
Project Position - This regulatory guide was withdrawn by the NRC on August 16, 1979.
Reference - 44 FR 49321, 8/22/79.
RBS USAR TABLE 1.8-1 (Cont) 154 of 238 August 1987 Regulatory Guide 1.105, Rev. 1 (November 1976)
Instrument Setpoints
Project Assessment - Comply, with the following clarification:
Regulatory Guide 1.89 is addressed in a separate compliance statement.
USAR Section - 7.1.2 RBS USAR TABLE 1.8-1 (Cont) 155 of 238 August 1987 Regulatory Guide 1.106, Rev. 1 (March 1977)
Thermal Overload Protection for Electric Motors on Motor-Operated Valves
Project Assessment - Comply.
USAR Section - 8.3.1 RBSUSARTABLE1.8-1(Cont)156of238August1987RegulatoryGuide1.107,Rev.1(February1977)QualificationsforCementGroutingforPrestressingTendonsinContainmentStructuresProjectPosition-NotapplicabletoRBS.
RBS USAR TABLE 1.8-1 (Cont) 157 of 238 August 1987 Regulatory Guide 1.108, Rev 1 (August 1977)
Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants
Project Assessment - Comply, with the following clarifications:
- 1. Paragraph C.1.b(4) - The surveillance system for the standby diesel generator units at RBS provides remote indication of the standby diesel generator unit status
through the use of the "standby diesel generator inoperative" and the "standby diesel generator trouble" annunciators and the "standby diesel generator tripped" indicating light, all of which are found in the main control room. Indication of the HPCS diesel generator unit status is attained via the engine overspeed trip
annunciator, the generator overload alarm, and various protective device bypass alarms which are located in the main control room. There are means of communication between the main control room and the diesel generator control room that provide for the determination of the underlying cause or causes of the
particular status.
- 2. Paragraph C.1.b(5) - There is no first-out annunciation feature for the diesel generator protective trips.
During an emergency condition only two protective features (generator differential and engine overspeed) trip the HPCS diesel generator. There is no benefit knowing which alarm tripped first. They are mutually
independent trips; differential relay trip does not result from overspeed and overspeed does not result
from differential relay action).
Standby diesel generator surveillance systems annunciators located in the standby diesel generator control room are separated into subsystem groups. Each subsystem group is provided with a first-out
indication.
Revision 10 158 of 238 April 1998
- 3. Paragraph C.2.a - Periodic testing will be as required by Technical Specifications.
- 4. Paragraph C.2.a(3) - For the standby diesel generators, credit is taken for the performance of the overload
test as described in Section 8.3.1.1.5.2.
- 5. Paragraph C.2.a(9) - The onsite preoperational reliability tests required by this section were performed as described in Sections 8.3.1.1.4.2.1 and
8.3.1.1.5.2.
- 6. Paragraph C.3.b - Regulatory Guide 1.16 is addressed in a separate compliance statement. 10 7. Paragraph C.2.d - Diesel Generator reliability is monitored and determined per 10CFR50.65.
8.Paragraph C.2.e - Diesel Generator failure determination will be per 10CFR50.65.
9.Paragraph C.3 - All diesel generator functional failures are analyzed and reported pursuant to
10CFR50.65, 10CFR50.72, 10CFR50.73 and the Technical
Specifications, respectively. The provisions of regulatory Guide 1.108 Paragraph C.3 for accelerated
testing, failure classification, failure reporting, and
failure logging are no longer applicable.
10 USAR Sections - 8.3.1, 14.2.12 RBS USAR TABLE 1.8-1 (Cont) 159 of 238 August 1987 Regulatory Guide 1.109, Rev. 1 (October 1977)
Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I
Project Position - Comply, with the following clarification:
Regulatory Guide 1.110 is addressed in a separate compliance statement.
USAR Sections - 11.2, 11.3
RBS USAR TABLE 1.8-1 (Cont) 160 of 238 August 1987 Regulatory Guide 1.110 (March 1976) (For Comment)
Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors
Project Assessment - A cost-benefit analysis for the radwaste systems at RBS has not been performed, since the RBS construction
permit was docketed before June 4, 1976.
RBS USAR TABLE 1.8-1 (Cont) 161 of 238 August 1987 Regulatory Guide 1.111, Rev. 1 (July 1977)
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors
Project Position - Comply.
USAR Sections - 2.3.5, 11.3
RBS USAR TABLE 1.8-1 (Cont) 162 of 238 August 1987 Regulatory Guide 1.112, Rev. 0-R (May 1977)
Calculation of Releases of Radioactive Materials in Gaseous
and Liquid Effluents from Light-Water-Cooled Power Reactors
Project Position - Comply.
USAR Sections - 2.3.4, 11.2.3, 11.3.3, 15.7.1, 15.7.2, 15.7.3
RBS USAR TABLE 1.8-1 (Cont) 163 of 238 August 1987 Regulatory Guide 1.113, Rev. 1 (April 1977)
Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I
Project Position - Comply.
USAR Sections - 2.4.12, 2.4.13, 11.2, 15.7.2
RBS USAR TABLE 1.8-1 (Cont) 164 of 238 August 1987 Regulatory Guide 1.114, Rev. 1 (November 1976)
Guidance on Being Operator at the Controls of a Nuclear Power Plant
Project Position - Comply.
USAR Section - 13.5 RBS USAR TABLE 1.8-1 (Cont)
Revision 8 165 of 238 September 1996 Regulatory Guide 1.115, Rev. 1 (July 1977)
Protection Against Low-Trajectory Turbine Missiles Project Position - Not applicable to River Bend Station.
RBSUSARTABLE1.8-1(Cont)Revision8166of238August19968THISPAGEHASBEENDELETED 8
RBSUSARTABLE1.8-1(Cont)Revision12167of238December199912RegulatoryGuide1.116,Rev.O-R(June1976)QualityAssuranceRequirementsforInstallation,Inspection,andTestingofMechanicalEquipmentandSystemsConstructionPosition(Historical)-Comply,withthefollowing clarification:RegulatoryGuide1.68isaddressedinaseparatecompliance statement.OperationPosition-RefertotheQualityAssuranceProgram Manual.USARSection-RefertotheQualityAssuranceProgramManual.
12 RBS USAR TABLE 1.8-1 (Cont) 168 of 238 August 1987 Regulatory Guide 1.117, Rev. 1 (April 1978)
Tornado Design Classification
Project Assessment - Comply.
USAR Section - 3.3, 3.5.1.4
Revision 8 169 of 238 August 1996 Regulatory Guide 1.118, Rev. 2 (June 1978)
Periodic Testing of Electric Power and Protection Systems
Project Assessment - Comply, with clarifications regarding sensor response time testing:
- 1. The response time of electrical protective relays and motion sensors is verified by including them in the
response time test of the protection system. The
response time of passive sensors (potential transformers and current transformers) which are used as interfaces between the electrical system and the protective relays, does not degrade without changes in the steady state performance of the device.
Section 6.3.4 of IEEE 338-1977 says that it isn't necessary to response time test discrete portions of safety systems either known to have acceptable system response times or which are characterized by response time changes that are detectable during routine
periodic tests. 8 2. Pressure and level sensors are included in the response time test of the protection system, except where excluded by technical specifications, to determine if the response time is adequate with regard to achieving the intended safety function. The response time test is
only required to ensure that the response time is less
than or equal to the response time used in the accident
analysis.
8 3. Radiation, temperature, and some types of in-line electrical and fluid sensors are not quantitatively
tested for response time after installation.
Verification of proper installation and calibration is used as an indirect means of assuring proper response times. Equipment suppliers are required to verify the sensor response time adequacy. These response times
are combined with system response time, which is
measured independently of the sensor.
Undetected response time degradation of some types of sensors is not known to occur provided that they are
properly installed and calibrated.
RBSUSARTABLE1.8-1(Cont)Revision8170of238August199684.ParagraphC.8.a-Insofarasissafeandpractical,responsetimetestingisperformedfromsensorinputs(atthesensorinputconnectionforprocess instruments)toandincludingtheactuatedequipment exceptincaseswherethesensorisexcludedby technicalspecifications.
8ThefollowingclarificationappliestotheHCPSPowerSupply System-DivisionIII:ParagraphC.6-TripofanassociatedprotectivechanneloractuationofanassociatedClass1Eloadgroupisrequiredonremovaloffusesoropeningofabreakeronlyforthepurposeof deactivatinginstrumentationandcontrolcircuits.USARSections-8.1,8.3.1 RBS USAR TABLE 1.8-1 (Cont) 171 of 238 August 1987 Regulatory Guide 1.119 (June 1976)
Surveillance Program for New Fuel Assembly Designs
Project Position - This regulatory guide was withdrawn on June 23, 1977 by the NRC.
Reference - 42 FR 33387, 6/30/77
RBS USAR TABLE 1.8-1 (Cont) 172 of 238 August 1987 Regulatory Guide 1.120, Rev. 1 (November 1977) (For Comment)
Fire Protection Guidelines for Nuclear Power Plants
Project Position - The fire protection program for RBS follows Appendix A of Branch Technical Position APCSB 9.5-1, dated
August 23, 1976.
Appendix A to BTP APCSB 9.5-1 provides guidance on the preferred and, where applicable, acceptable alternatives to the fire protection design for those nuclear power plants for which applications for construction permits were docketed prior to July 1, 1976. The RBS construction permit application was
docketed in 1973.
USAR Sections - 9.5.1, Appendix 9A, 17.2
RBS USAR TABLE 1.8-1 (Cont) 173 of 238 August 1987 Regulatory Guide 1.121 (August 1976) (For Comment)
Bases for Plugging Degraded PWR Steam Generator Tubes
Project Position - Not applicable to BWRs.
RBS USAR TABLE 1.8-1 (Cont) 174 of 238 August 1987 Regulatory Guide 1.122, Rev. 1 (February 1978)
Development of Floor Design Response Spectra For Seismic Design of Floor-Supported Equipment or Components
Project Assessment - Comply, with the following clarification:
Regulatory Guide 1.92 is addressed in a separate compliance statement.
USAR Sections - 3.7.2, 9.1.2
Revision 12 175 of 238 December 1999 Regulatory Guide 1.123, Rev. 1 (July 1977)
Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants 12 4 2 Construction Position (Historical) - Comply.
Operation Position - Refer to the Quality Assurance Program Manual.
2 4 12 RBSUSARTABLE1.8-1(Cont)Revision12176of238December1999124USARSection-RefertotheQualityAssuranceProgramManual.
412 RBS USAR TABLE 1.8-1 (Cont) 177 of 238 August 1987 Regulatory 1.124, Rev. 1 (January 1978)
Service Limits and Loading Combinations for Class 1 Linear-Type Component Supports
Project Assessment - Comply, with the following exceptions and additions pertinent to non-NSSS supports (S&W):
- 1. The following paragraph should be added to paragraph C.3.
"Paragraph C.3.c. The bending stress limit, F b , resulting from tension and bending in structural members as specified in Appendix XVII-2214 of Section III, Division 1, should be the smaller value of
0.66 S y or 0.55 S u for compact sections, 0.75 S y or 0.625 S u for doubly symmetrical members with bending about the minor axis, and 0.6 S u or 0.5 S u for box-type flexural members and miscellaneous members."
The paragraph added to paragraph C.3 is necessary because of an apparent oversight in applying the 5/6
factor to bending stress allowables.
- 2. The second paragraph under paragraph C.4 should be replaced with the following:
"However, all increases [i.e., those allowed by NF-3231.1 (a) XVII-2110 (a), and F-1370 (a)] shall always be limited by XVII-2110 (b) of Section III. The
critical buckling strengths defined by XVII-2110 (b) of Section III should be calculated using material
properties at temperature.
The increased allowable permitted for tensile stress in bolts shall not exceed the lesser of 0.70 S u or S y at temperature. The increased allowable permitted for shear stress in bolts shall not exceed 0.42 S u at temperature."
The third sentence in the second paragraph of paragraph C.4 prohibits the application of the increased allowables presently permitted by NF-3231.1(a) and F-1370(a) to Service Limits A or B for bolted connections. The danger of applying the RBS USAR TABLE 1.8-1 (Cont) 178 of 238 August 1987
increase presently allowed by Subsection NF has been pointed out at Subsection NF Committee meetings. The
stated position asserts that the maximum safe increased
allowables are achieved by limiting bolting tensile stress to the lesser of 0.7 S u or S y at temperature and bolting shear stress to 0.42 S u at temperature. The 0.7 S u limit is well recognized in Section III of the Code. The average shear strength of bolting material is about
0.62 S u according to test data, with a standard deviation of 0.033. Results indicate that the ratio of shear strength to tensile strength is independent of the bolt grade. Curves showing this appear on page 50
of "Guide to Design for Bolted and Riveted Joints," by J. W. Fisher. Test data are given in a paper by J. J. Wallaert and J. W. Fisher, "Shear Strength of
High-Strength Bolts," Journal of the Structural
Division, ASCE Volume 91, ST3, June 1965.
- 3. Paragraph C.5.a should be revised as follows:
"The stress limits of XVII-2000 of Section III and Regulatory Position 3 of this guide should not be exceeded for component supports designed by the linear
elastic analysis method. These stress limits may be increased according to the provisions of NF-3231.1 (a) of Section III and Regulatory Position 4 of this guide when effects resulting from constraint of free-end displacement and anchor motion are added to the loading
combination."
Loads developed by anchor motions are also deformation limited and, as such, are considered to be grouped in the same category as loads from restraint of free-end displacement. The resulting stresses are essentially
of the secondary type.
- 4. Paragraph C.8 should read as follows:
"Supports for the 'active components' that are required for safe shutdown during an emergency or faulted plant condition and that are subjected to loading
combinations described in Regulatory Positions 6 and 7, are designed within the design limits described in Regulatory Position 5 or other justifiable design limits. These limits are RBS USAR TABLE 1.8-1 (Cont) 179 of 238 August 1987
defined by the Design Specification and stated in the
SAR, such that the function of the supported systems are maintained when they are subjected to the loading combinations described in Regulatory Positions 6
and 7."
Paragraph C.8 is revised as shown because this section implies that the lower stress limits associated with the design levels A or B service limits must be used for any component support that serves a safety-related
function during an emergency or faulted plant condition. This would seem to imply that a main coolant pump support, which constitutes a passive element in the main coolant loop, would have to be designed to meet the design levels A or B service limits during an emergency or faulted (LOCA) plant condition. This would require that a snubber providing
restraint on an RHR line would have to be designed to the design levels A or B service limits during an emergency or faulted plant condition. If this is the intent, it is a severe departure from current practice.
Only active components, such as valves, whose operation
is required for safe shutdown during an emergency or faulted condition have been required to meet design stress limits for these plant conditions. Levels C or D service limits have been considered adequate to assure pressure boundary integrity under the more severe
operating conditions.
The following statement pertains to NSSS supports (GE): All Class 1 linear-type component supports are designed in accordance
with the rules of the ASME Boiler and Pressure Vessel Code,Section III, Subsection NF. The design requirement in NF
includes the analysis and/or tests to demonstrate that all such component supports do not deform under faulted plant conditions
to the extent that would impair the required operability of the supported components to perform a safety function for safe
shutdown of the plant.
USAR Section - 3.9.3 RBS USAR TABLE 1.8-1 (Cont) 180 of 238 August 1987 Regulatory Guide 1.125, Rev. 1 (October 1978)
Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants
Project Position - Not applicable to RBS.
RBS USAR TABLE 1.8-1 (Cont) 181 of 238 August 1987 Regulatory Guide 1.126, Rev. 1 (March 1978)
An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification
Project Position - GE meets the requirements of this regulatory guide with the exception of the method of derivation of the
densification values from resintering tests.
GE feels that the NRC method in the regulatory guide represents a
significant departure from previously approved GE methods.
Specifically, this departure requires:
- 1. An increase in the level of statistical confidence level from 50 percent to 95 percent employed to infer
population parameters from the sampling results, and
- 2. Identification and individual characterization of lots (powder types) within the quantity of material of
initial interest (initial core or reload).
This departure from the GE approach previously approved by the
staff is interpreted as the introduction of additional
conservatism in the GE densification analyses, and such a Staff position is considered inappropriate in recognition of the GE/NRC agreed upon conservatisms incorporated into the individual
densification models during their formulation.
USAR Sections - 4.2.1.2, 4.2.3.2.8 RBS USAR TABLE 1.8-1 (Cont) 182 of 238 August 1987 Regulatory Guide 1.127, Rev. 1 (March 1978)
Inspection of Water-Control Structures Associated with Nuclear Power Plants
Project Position - Not applicable to RBS.
RBS USAR TABLE 1.8-1 (Cont) 183 of 238 August 1987 Regulatory Guide 1.128, Rev. 1 (October 1978)
Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants
Project Assessment - Comply, with the following clarifications:
Regulatory Guides 1.120 and 1.100, as referenced by paragraphs C.2 and C.3, respectively, are addressed in
separate compliance statements.
USAR Sections - 8.1, 8.3.2
Revision 22 184 of 238 Regulatory Guide 1.129, Rev. 1 (February 1978)
Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants
Project Assessment
- Comply , with the following clarification. 1. Paragraph C.1
- The specified maximum interval of 18 months between battery service tests has been extended to 30 months.
USAR Sections - 8.1, 8.3.2
RBS USAR TABLE 1.8-1 (Cont) 185 of 238 August 1987 Regulatory Guide 1.130, Rev. 1 (October 1978)
Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports
Project Assessment - The design for Class I plate-and-shell type component supports fully complies with Subsection NF,Section III, ASME Boiler and Pressure Vessel Code. Some of the analytical details of the guide which are in addition to the code
are not included in the plate- and shell-type component support analysis. However, it is concluded that the conservative ASME
Code analysis demonstrates the adequacy of the design.
USAR Section - 3.9.3 RBS USAR TABLE 1.8-1 (Cont) 186 of 238 August 1987 Regulatory Guide 1.131 (August 1977) (For Comment)
Qualification Tests of Electrical Cables, Field
Splices, and Connections for Light-Water-Cooled Nuclear Power Plants
Project Assessment - All Seismic Category I (safety-related) specifications for electric cable require compliance to IEEE 383-
- 74. The implementation provisions of the guide do not impose these requirements for RBS. However, where practical the provisions of Revision 0 of the guide will be implemented.
Regulatory Guide 1.89 is addressed in a separate compliance
statement.
USAR Sections - 3.11, 8.3.1, Appendix 9A
RBS USAR TABLE 1.8-1 (Cont) 187 of 238 August 1987 Regulatory Guide 1.132, Rev. 1 (March 1979)
Site Investigations for Foundations of Nuclear Power Plants
Project Assessment - The soil program for RBS was reviewed and approved prior to the issuance of this regulatory guide.
RBSUSARTABLE1.8-1(Cont)Revision14188of238September2001THISPAGELEFTINTENTIONALLYBLANK RB S U S AR TABLE 1.8-1 (Cont)
Revision 20 189 of 238 Regulatory Guide 1.134, Rev. 1 (March 1979)
Medical Evaluation of Nuclear Power Plant Personnel Requiring Operator Licenses
Project Position - Comply, with the following exception s: Paragraph B RB S takes exception to compliance with AN S I N546-1976, "Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants."
The licensed operator medical certification process used at RB S meets the standards prescribed in AN S I / AN S 3.4-1983 of the same title.
Paragraph C.1 7 RB S takes exception to submitting background medical information prior to the physical examination. In lieu of pre-physical submittal, this information is conveyed to the medical practitioner at the time of the examination. The adherence to this position complies with the intent of the regulatory guide while at the
same time it alleviates potential tracking problems.
7 U S AR S ections - 13.1.2, 13.1.3 RBS USAR TABLE 1.8-1 (Cont) 190 of 238 August 1987 Regulatory Guide 1.135 (September 1977) (For Comment)
Normal Water Level and Discharge at Nuclear Power Plants
Project Assessment - Comply, with the following clarification:
Regulatory Guide 1.59 is used to determine initial water levels for the Design Basis Flood analysis.
USAR Section - 2.4 RBSUSARTABLE1.8-1(Cont)191of238August1987RegulatoryGuide1.136,Rev.1(October1978)MaterialsforConcreteContainmentsProjectPosition-NotapplicabletoRBS.
Revision 24 192 of 238 Regulatory Guide 1.137, Rev. 1 (October 1979)
Fuel-Oil Systems for Standby Diesel Generators Project Assessment - Comply, with the following exceptions: 1.Paragraph C.1.f references Section 7.3 of ANSI N195-1976which states that adequate heating shall be provided for thefuel oil system. No heating system has been provided for
the Diesel Generator Building.Site ambient temperature is sufficiently high in the winterto allow specifying fuel oil cloud point below the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> minimum soak temperature thereby assuring that fuel oil can be supplied and ignited at all times under the most severe
environmental conditions.2.Paragraph C.2.g states that "the method of adding[additional] fuel oil should be such as to minimize the creation of turbulence of the accumulated residual sediment in the bottom of the supply tank." The RBS project has extended tank fill lines to within 5 in. of the bottom to eliminate possible fire paths due to oil vapors with low tank level. This could cause turbulence in the bottom
sediments during filling.Sufficient filtering capacity exists downstream of the fuelstorage tank to mitigate the consequences of any sediment being stirred up. Additionally, provision is made to drain off accumulated water and sediment from the tank bottom on a routine basis thus reducing the possibility of contaminating
clean oil. 93.All references made to ASTM D975-77 shall be replaced byASTM D975-81. The newer version of the standard maintains the same specifications/limits on diesel fuel, yet allows
the use of newer up to date testing methods.
9 4.Paragraph C.2.b states that prior to adding new fuel oil to the supply tanks, onsite samples of the fuel oil should be taken. As a minimum, prior to the addition of the new fuel,tests for the following properties should be conducted: 1)Specific or API gravity, 2) water and sediment, and 3) viscosity. Test results for the latter two tests should not exceed the limits specified in the applicable specification.
Analysis of the other properties of the fuel oil listed inthe applicable specification should be completed within 2 weeks of the addition.
Analysis time requirements for new diesel fuel specifiedin Technical Specification 5.5.9.
USAR Section - 9.5.4 RBSUSARTABLE1.8-1(Cont)193of238August1987RegulatoryGuide1.138(April1978)(ForComment)LaboratoryInvestigationsofSoilsforEngineeringAnalysisandDesignofNuclearPowerPlantsProjectAssessment-ThesoilsprogramforRBSwasreviewedandapprovedpriortotheissuanceofthisregulatoryguide.
RBSUSARTABLE1.8-1(Cont)194of238August1987RegulatoryGuide1.139(May1978)(ForComment)GuidanceforResidualHeatRemovalProjectAssessment-Comply,withthefollowingclarificationtoparagraphC.2.a:Redundantinterlockspreventtheopeningofvalvestothelowpressuresuctionpipingwhenthe reactorpressureisabovetheshutdownrange.
Thesesameinterlocksinitiatevalveclosureupon increasingreactorpressure.Inaddition,ahigh pressurecheckvalveclosestopreventreverse flowifthepressureshouldincrease.Relief valvesinthedischargepipingaresizedto accountforleakagepastthecheckvalve.Thus,alongwithvalvepositionindicationinthemaincontrolroom,systemisolationisassured withoutrequiringoperatoraction.RegulatoryGuide1.68isaddressedinaseparatecompliancestatement.USARSection-5.4.7 RBSUSARTABLE1.8-1(Cont)195of238August1987RegulatoryGuide1.140,Rev.1(October1979)Design,Testing,andMaintenanceCriteriaforNormalVentilationExhaustSystemAirFiltrationandAdsorptionUnitsofLight-Water-CooledNuclearPowerPlantsProjectAssessment-Comply,withthefollowingclarificationsandexceptions:1.ParagraphC.2.d-RegulatoryGuide8.8isaddressedinTable9.4-6andTable1.8-1.2.ParagraphC.3.c-ForHEPAfiltersandadsorbermountings,therequirementsofANSIN509-1976Section5.6.3arecompliedwithexceptforthe tolerancerequirements.ThetolerancesforHEPA filtersandadsorbermountingframesaresufficientto passthebankleaktestsofparagraphs5.cand5.dof theguide.Anacceptablebankleakrateistheprimaryobjective.Variationsinmanufacturefromthetolerancevalues listedinORNL-NSIC-65(Table4.2)areconsideredtobe
acceptable.3.ParagraphC.3.h-ExceptionistakentoSection5.2.2.4ofANSIN509-1976whichcallsforameansof compactiontouniformdensity.Whereuniform compactioncanbedemonstrated,compactingmeansare notrequired.Ameansforcompaction,vibratoryorotherwise,neednotbemandatoryifuniformcompactionisdemonstrated.4.ParagraphC.3.ia.SystemresistancesaredeterminedinaccordancewithSection5.7.1ofANSIN509-1976exceptthat faninletandoutletlossesarenotcalculatedin accordancewithAMCA201.Fanblastareadatanecessarytocalculateinletandoutletlosses,perAMCA201,arethe RBS USAR TABLE 1.8-1 (Cont) 196 of 238 August 1987
responsibility of the fan manufacturers and are
not available from them.
- b. Exception is taken to Section 5.7.2 of ANSI N509-1976. Copies of fan ratings or test reports are
not necessary when certified fan performance
curves are furnished.
It is unnecessary to require fan manufacturers to furnish laboratory test data used to develop
performance curves and tabulated design data.
- c. Exception is taken to Section 5.7.3 of ANSI N509-1976. Balancing techniques specified need not be
followed. Maximum permissible vibration velocity
level method need not be complied with.
The maximum vibration velocity method imposes
unrealistic requirements for certain operating
speeds. Displacement criteria following normal
industry practice are used.
- d. Exception is taken to Section 5.7.5 of ANSI N509-1976. Where AMCA certification ratings are
submitted, documentation is not furnished.
AMCA certification ratings are granted on the basis of data required under Section 5.7.5 of
ANSI N509-1976.
- 5. Paragraph C.3.k - The air flow distribution is within `20 percent of the average air flow as tested in
accordance with ANSI N510-1975.
Turning vanes are provided only where a uniform air distribution can not be achieved.
It is not necessary to provide turning vanes for filter units where a uniform air flow distribution is
demonstrated by testing.
- 6. Paragraph C.3.1 - Exception is taken to Section 5.9 of ANSI N509-1976:
RBS USAR TABLE 1.8-1 (Cont) 197 of 238 August 1987
- a. Dampers are not designed to the specifications of ANSI B31.1.
- b. Butterfly valves are not used.
- d. Dampers with shaft lengths §24 in have a minimum shaft diameter of 1/2 in. Dampers with shaft lengths >24 in and §48 in have a minimum shaft
diameter of 3/4 in.
Systems and components are designed to preclude uncontrolled releases of radioactivity. This satisfies the intent of Section 5.9 of ANSI N509-1976. Shaft sizes for small dampers are based on Manufacturer's
Standards.
NOTE: Items a and b do not pertain to containment penetrations.
- 7. Paragraphs C.2.f and C.3.f - The following exceptions are taken to Section 4.12 of ANSI N509-1980 for maximum allowable leakage for air cleaning effectiveness and
duct and housing quality requirements.
HVAC duct/filter system air leakage in excess of the allowable leakage for a particular section of ductwork could occur at equipment (e.g., damper shafts and fan
shafts through their housing penetrations, etc).
In areas or sections of systems where leakage is in excess of Section 4.12 requirements, an analysis or tests are performed to demonstrate that system
functional criteria and radiation protection concerns
are met. However, the total allowable leakage for the
entire system will not be exceeded.
- 8. Paragraphs C.2.f and C.3.f - The following exception is taken to Section 5.10.8.2 of ANSI N509-1980, Fan
Pressure Test:
RBSUSARTABLE1.8-1(Cont)198of238August1987CertainisolatableportionsofHVACductworkassociatedwiththeturbinebuilding(HVT)andcontainmentpurge (HVR)charcoalfiltrationsystemswerefieldpressure testedatpressureslessthantheirfanpeakpressure.TheHVTwastestedat15.5inW.G.,butthesystemfanpeakis18.8inW.G.TheHVRwastestedat15.0in W.G.,butthesystemfanpeakis18.5inW.G.Theductworkfabricationcharacteristics(i.e.,sheetmetalgauge,reinforcementangles,andwelding)arethe sameforthesepressurerangesandencompassboththe actualtestedpressuresandthefanpeakpressure.AprototypesampleductsectionrepresentingtheweakestductspoolwithintheHVTandHVRsystems (i.e.,longestductsectionwithnoreinforcement)was fieldshoptestedatapressuregreaterthan18.8in W.G.Thisadditionaltest,conductedatapressure greaterthanthehighestpressureofthetwosystems, willensurethatthestructuralintegrityoftheHVT andHVRductsectionscanbemaintainediftheirfan peakpressureoccurs.9.ParagraphsC.2.fandC.3.f-ThefollowingexceptionistakentoSection5.10.8.1ofANSIN509-1980,Air LeakageTest:Airleakagetestswereconductedinthefieldtodeterminetheallowableairleakageontheisolatable portionsofductworkfortheturbinebuilding(HVT)and containmentpurge(HVR)charcoalfiltrationsystems.
Thisquantitativeleaktestingwasperformedat pressureslessthantheirfanpeakpressures.SomeportionsoftheHVTductswerepressuretestedat4.64inW.G.andotherportionsat11.83inW.G.,but thesystemfanpeakpressureis18.8inW.G.Some portionsoftheHVRductswerepressuretestedat 4.0inW.G.,andotherportionsat12.0inW.G.,but thefanpeakpressureis18.5inW.G.
Revision 22 199 of 238 An analysis was performed using the actual test results (i.e., the volume of air leaked and the pressures they were tested at) in conjunction with each system's fan
peak pressure. This mathematical analysis established
what the volume of air leakage (in cfm) would have been had the systems been tested at their respective fan
peak pressures.
A comparison between the actual tested leakage and the calculated leakage was performed and analyzed with regard to radiation protection concerns. It has been determined that the adjusted pressures are below the leakages necessary to ensure safe operation of equipment and personnel as required by Sections 4.12, Pressure Boundary Leakage, and 4.12.2, Health Physics
Requirements, of ANSI N509-1980.
- 10. Paragraph C.6.a.2 - The following exception is taken to the requirement that "new activated carbon meets the physical property specifications given in Table 1 of Regulatory Guide 1.140, 1979." The charcoal absorbent now commercially available does not meet the physical requirements of Table 1, but does meet the requirements
of ANSI/ASME N509-1980.
- 11. Paragraph C.6.b - The following exception is taken to the requirements of conducting laboratory tests of representative samples as indicated in Table 2 of
Regulatory Guide 1.140: representative samples will be
tested in accordance with ASTM D3803-1979.
- 12. Paragraphs 5.c and 5.d, Table 2
- Test frequencies specified as "approximately 18 months" will be scheduled on a 24-month frequency.
USAR Section - 9.4 RBS USAR TABLE 1.8-1 (Cont) 200 of 238 August 1987 Regulatory Guide 1.141 (April 1978) (For Comment)
Containment Isolation Provisions for Fluid Systems
Project Assessment - Comply, with the following clarification:
Regulatory Guide 1.89 is addressed in a separate compliance statement.
USAR Section - 6.2.4 RBSUSARTABLE1.8-1(Cont)201of238August1987RegulatoryGuide1.142(April1978)(ForComment)Safety-RelatedConcreteStructuresforNuclearPowerPlants(OtherthanReactorVesselsandContainments)ProjectAssessment-TheRBSprojectdoesnotcomplywiththisregulatoryguide.TheconstructionpermitapplicationforRBSwasdocketedin1973,atwhichtimesafety-relatedconcrete structureswerebeingconstructedusingACI318-1971andother applicablecodesandspecifications.Furtherdiscussionmaybe foundinSection3.8.4ofthisUSAR.
Revision 24 202 of 238 Regulatory Guide 1.143, Rev. 1 (October 1979)
Design Guidance for Radioactive Waste Management
Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants
Project Assessment - Comply, with the following exceptions and clarifications to paragraph C.5:
- a. ACI 318-71 is used in the design of structures housing radwaste systems rather than ACI 318-77.
- b. The support elements, including the skirts, legs, and anchor bolting, for the charcoal adsorber tanks of the
offgas system are designed as follows:
(1) The fundamental frequency of the charcoal adsorber tanks, including the support elements, is greater
than 33 Hertz.
(2) The charcoal adsorber tanks are mounted on the base mat of the building housing the tanks.
(3) The charcoal adsorber tanks, including the support elements, are designed with a vertical static coefficient of 0.11g and a horizontal static
coefficient of 0.28g.
(4) The stress levels in the support elements of the charcoal adsorber tanks do not exceed 1.33 times the allowable stress levels permitted by the AISC
Manual of Steel Construction, Seventh Edition, 1970. c. Portions of the radioactive liquid waste system (LWS) contain fiberglass reinforced plastic pipe (FRP), High Density Polyethylene (HDPE) pipe and polypropylene-lined steel pipe (PPL). FRP pipe is only used to handle condensate quality water, i.e., those portions of LWS handling water which has been processed and is being transferred to the condensate storage tank. HDPE piping is also only used to handle condensate quality water that is being discharged. PPL piping is only used in the demineralizer subsystems because of its
superior corrosion resistance.
RBS USAR TABLE 1.8-1 (Cont) 203 of 238 August 1987
Regulatory Guide 8.8, as referenced by paragraph C.4.1 and Regulatory Guides 1.92 and 1.122, as referenced by paragraphs C.5.2.2 and C.5.2.3, respectively are addressed in separate
compliance statements.
The preceding method of seismic design for the structures housing radwaste systems is based on direction given by the NRC in 1975; Ref: Appendix D of supplement 2 to the Safety Evaluation Report for RBS. The RBS PSAR was amended in December 1975 to outline
this method.
USAR Sections - 11.2.1, 11.3.2, 15.7.2, 17.2
RBSUSARTABLE1.8-1(Cont)Revision12204of238December1999RegulatoryGuide1.144,Rev.1(September1980)AuditingofQualityAssuranceProgramsforNuclearPowerPlants12ConstructionPosition(Historical)-Comply,withthefollowingclarificationstoSections4.3.1and4.3.3ofANSIN45.2.12-1977:Pre-auditandpost-auditconferencesmaybefulfilledbyavarietyofcommunications,suchastelephoneconversation.OperationalPosition-RefertoQualityAssuranceProgramManual.USARSection-RefertoQualityAssuranceProgramManual.
12 RBSUSARTABLE1.8-1(Cont)205of238August1987RegulatoryGuide1.145(August1979)(ForComment)AtmosphericDispersionModelsforPotentialAccidentConsequenceAssessmentsatNuclearPowerPlantsProjectAssessment-Comply.USARSections-2.3,13.3,Chapter15 RBS USAR TABLE 1.8-1 (Cont)
Revision 12 206 of 238 December 1999 Regulatory Guide 1.146 (August 1980)
Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants 12 Construction Position (Historical) - Comply.
Operational Phase - Refer to the Quality Assurance Program Manual.
USAR Section
- Refer to the Quality Assurance Program Manual.
12 RBS USAR TABLE 1.8-1 (Cont)
Revision 8 207 of 238 August 1996 Regulatory Guide 1.147 Inservice Inspection Code Case Acceptability ASME Section XI Division 1 8 Project Position - Comply as delineated in the latest revision of the Inservice Inspection (ISI) Plan.
8 RBS USAR TABLE 1.8-1 (Cont) 208 of 238 August 1987 Regulatory Guide 1.148 (March 1981)
Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants
Project Assessment - RBS does not comply explicitly with all of the requirements of this regulatory guide, since the guide was issued after the valve purchase orders were placed. However, some of the requirements of the guide are addressed in the
specifications for active valve assemblies.
The valve operability program outlined in Sections 3.9.3.2A and 3.9.3.2B provides the data necessary to demonstrate valve
operability.
USAR Section - 3.9.3.2A, 3.9.3.2B
Revision 23 209 of 238 16 Regulatory Guide 1.149 Revision 4 (April 2011
) Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations 16
Project Position - Comply.
Revision 25 210 of 238 Regulatory Guide 1.150, Rev. 1 (February 1983)
Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations
Project Position
- 1. Preservice Examinations
As detailed in Section 5.0 of the RBS Preservice Inspection (PSI) Program Plan submitted in a letter dated November, 5, 1984, this regulatory guide does not apply since
all vessel baseline examinations were completed prior to the
effective date of this guide.
- 2. Inservice Examinations 8 Comply as delineated in the latest revision of the Inservice Inspection (ISI) Program Plan.
8 Note, this Regulatory Guide was withdrawn and the content incorporated into the updated ISI Programs and Appendix VIII.
Regulatory Guide 1.151 (July 1983)
Instrument Sensing Lines
Project Position - Comply, with the following interpretations:
- 1. Position C.1 - As stated in the value/impact statement, paragraph 2.2, the intent of Position C.1 is to meet provisions of Sections 4.7.3 and 4.7.4 of IEEE 279-1971. Compliance with this position is by the interpretation of Regulatory Guide 1.53 as discussed in
Table 1.8-1.
- 2. Positions C.2 and C.3 - As stated in the value/impact statement, paragraph 2.3, the intent of Positions C.2 and C.3 is to meet provisions of Regulatory Guide 1.26.
Compliance with this position is by the interpretation
of Regulatory Guide 1.26 as discussed in Table 1.8-1.
- 3. Positions C.4 and C.5 - Environmental control and monitoring systems applied to instrument sensing lines are non-Class 1E in accordance with the recommendation of IEEE 622-1979. The environmental control and alarm circuits have reliable power sources and are therefore considered to be designed to "standards commensurate
with their importance to safety."
Regulatory Guide 1.155 (June 1988)
Station Blackout Project Position - Comply with the following clarification:
Guidance on an acceptable method of analysis was provided by the NRC in Regulatory Guide 1.155 which finds NUMARC 87-00 as an acceptable alternative to demonstrate compliance with the Station Blackout Rule.
River Bend Station was evaluated using the guidance provided in NUMARC 87-00 EXCEPT where the Regulatory Guide takes precedence. Table 1 to Regulatory Guide 1.155 provides a cross-reference between RG 1.155 and NUMARC 87-00 and notes where the regulatory guide takes precedence.
USAR Section:
15C RBS USAR TABLE 1.8-1 (Cont) 9 Regulatory Guide 1.163, Rev. 0 (Sept. 1995)
Performance-Based Containment Leak-Test Program
Project Position - Comply, but with the following clarification:
In lieu of leak rate calculation using minimum pathway, RBS will calculate leak rate using the more conservative maximum
pathway. RBS will seek approval of any desired exceptions in
accordance with 10CFR50.90 to the RBS Technical
Specifications.
USAR Sections - 6.2.6 9 RBS USAR TABLE 1.8-1 (Cont)
Revision 23 211c of 238 Regulatory Guide 1.190, Rev. 0 (March 2001)
Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence
Project Position - Comply
USAR Section
- 5.3 RBS USAR TABLE 1.8-1 (Cont) 212 of 238 August 1987 Regulatory Guide 4.15, Rev. 1 (February 1979)
Quality Assurance for Radiological Monitoring Program (Normal Operations)
- Effluent Streams and the Environment
Project Position - Comply.
USAR Sections - 13.4.2.1, 13.4.3.7
RBS USAR TABLE 1.8-1 (Cont) 213 of 238 August 1987 Regulatory Guide 8.1 (February 1973)
Radiation Symbol
Project Position - Comply.
USAR Sections - 12.3.1.2, 12.5.3.3 RBS USAR TABLE 1.8-1 (Cont) 214 of 238 August 1987 Regulatory Guide 8.2 (February 1973)
Guide for Administrative Practices in Radiation Monitoring
Project Position - Comply.
USAR Sections - 12.3.4, 12.5.1, 12.5.3, 13.2.3
Regulatory Guide 8.3 (February 1973)
Film Badge Performance Criteria Project Position - Thermoluminescent or optically stimulated luminescent dosimetry is to be used at River Bend Station instead of film badges.
USAR Sections - 12.5.2.2.3, 12.5.3.7 RBS USAR TABLE 1.8-1 (Cont) 216 of 238 August 1987 Regulatory Guide 8.4 (February 1973)
Direct-Reading and Indirect-Reading Pocket Dosimeters
Project Position - Comply.
USAR Sections - 12.5.2.2.3, 12.5.3.7
RBS USAR TABLE 1.8-1 (Cont) 218 of 238 August 1987 Regulatory Guide 8.6 (May 1973)
Standard Test Procedure for Geiger-Muller Counters
Project Position - Comply.
USAR Section - 12.5.2.2.2 RBSUSARTABLE1.8-1(Cont)Revision9219of238November19979RegulatoryGuide8.7Rev.1(June1992) 9OccupationalRadiationExposureRecordsSystemsProjectPosition-Comply.USARSection-12.5.3 RBS USAR TABLE 1.8-1 (Cont) 220 of 238 August 1987 Regulatory Guide 8.8, Rev. 3 (June 1978)
Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations will be as Low as is Reasonably Achievable
Project Position - Comply.
USAR Sections - 12.1, 12.3, 12.5, 13.2.3, Table 9.4-6 RBS USAR TABLE 1.8-1 (Cont)
Revision 9 221 of 238 November 1997 9 Regulatory Guide 8.9 Rev 1(July 1993) 9 Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program
Project Position - Comply.
USAR Sections - 12.5.2, 12.5.3
Revision 25 222 of 238 Regulatory Guide 8.10, Rev. 1-R (May 1977)
Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is Reasonably Achievable
Project Position - Comply, with the following exception:
Paragraph C.1.d Exception is taken to the annual training and testing of radiation workers. Refer to Quality Assurance Program Manual (QAPM) for training requirements.
USAR Sections - 12.1.1, 12.1.3, 12.5.1, 12.5.3, 13.2.3
RBS USAR TABLE 1.8-1 (Cont) 223 of 238 August 1987 Regulatory Guide 8.11 (June 1974)
Applications of Bioassay for Uranium
Project Position - Not applicable to RBS.
RBSUSARTABLE1.8-1(Cont)Revision9225of238November19979RegulatoryGuide8.13,Rev.2(December1987) 9InstructionConcerningPrenatalRadiationExposureProjectPosition-Comply.USARSections-12.5.3,13.2.3 RBS USAR TABLE 1.8-1 (Cont) 226 of 238 August 1987 Regulatory Guide 8.14, Rev. 1 (August 1977)
Personnel Neutron Dosimeters
Project Position - Comply.
USAR Sections - 12.5.2.2.3, 12.5.3.7 RBS USAR TABLE 1.8-1 (Cont)
Regulatory Guide 8.15 (October 1976)
Acceptable Programs for Respiratory Protection 13 Project Position and Operating Position - Comply, with the following exception:
The protection factors for respirators delineated in 10CFR20, Appendix A, are used for River Bend Station in lieu of those
identified in Table 1 of the Regulatory Guide.
The use of contact lenses is permitted with respirator wearer as outlined in NRC Policy Letter (RBC-48232, contact lenses
used with respirators).
The Fit Testing Protocols for respirators as delineated in OSHA Regulations are used for River Bend Station.
13 USAR Sections - 12.5.2.2.4, 12.5.3.5
RBS USAR TABLE 1.8-1 (Cont) 228 of 238 August 1987 Regulatory Guide 8.18 (December 1977)
Information Relevant to Ensuring that Occupational Radiation Exposures at Medical Institutions Will be as Low as Reasonably Achievable
Project Position - Not applicable to RBS.
RBS USAR TABLE 1.8-1 (Cont) 229 of 238 August 1987 Regulatory Guide 8.19, Rev. 1 (June 1979)
Occupational Radiation Dose Assessment in
Light-Water Reactor Power Plants - Design Stage Man-Rem Estimates
Project Position - Comply.
USAR Section - 12.4 RBS USAR TABLE 1.8-1 (Cont) 230 of 238 August 1987 Regulatory Guide 8.20, Rev. 1 (September 1979)
Applications of Bioassay for I-125 and I-131
Project Position - Comply.
USAR Section - 12.5.3.7
RBSUSARTABLE1.8-1(Cont)231of238August1987RegulatoryGuide8.21,Rev.1(October1979)HealthPhysicsSurveysforByproductMaterialatNRC-LicensedProcessingandManufacturingPlantsProjectPosition-NotapplicabletoRBS.
RBS USAR TABLE 1.8-1 (Cont) 232 of 238 August 1987 Regulatory Guide 8.22 (July 1978)
Bioassay at Uranium Mills
Project Position - Not applicable to RBS.
RBS USAR TABLE 1.8-1 (Cont) 233 of 238 August 1987 Regulatory Guide 8.23, Rev. 1 (January 1981)
Radiation Safety Surveys at Medical Institutions
Project Position - Not applicable to RBS.
RBS USAR TABLE 1.8-1 (Cont) 234 of 238 August 1987 Regulatory Guide 8.24, Rev. 1 (October 1979)
Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication
Project Position - Not applicable to RBS.
RBS USAR TABLE 1.8-1 (Cont) 235 of 238 August 1987 Regulatory Guide 8.25 (August 1980)
Calibration and Error Limits of Air Sampling Instruments for Total Volume of Air Sampled
Project Position - Comply.
USAR Section - 12.5.2.2.4
RBS USAR TABLE 1.8-1 (Cont) 236 of 238 August 1987 Regulatory Guide 8.26 (September 1980)
Applications of Bioassay for Fission and Activation Products
Project Position - Comply.
USAR Section - 12.5.3.7
RBS USAR TABLE 1.8-1 (Cont) Revision 25 237 of 238 Regulatory Guide 8.27 (March 1981)
Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants Project Po s ition Co m ply, with t he follow in g excepti on: Paragraph 2.2 Exception is taken to refresher training on an annual basis.
Refer to Quality Assurance Program Manual (QAPM) for training requirements.
USAR Sections - 12.5.3.8, 13.2.2 RBS USAR TABLE 1.8-1 (Cont) 238 of 238 August 1987 Regulatory Guide 8.29 (July 1981)
Instruction Concerning Risks from Occupational Radiation Exposure
Project Position - Comply.
USAR Sections - 12.5.3.3, 12.5.3.8, 13.2.1.1.13.3