ML19319D687
| ML19319D687 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, 05000303  |
| Issue date: | 08/10/1967 |
| From: | FLORIDA POWER CORP. |
| To: | |
| References | |
| NUDOCS 8003240668 | |
| Download: ML19319D687 (10) | |
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., Section Page 10 STEAM AN POWER CONVERSION S STM 10-1 10;l DESIGN BASES 10-1 10.2 SYSTEM DESCRIPIION AND OPERATION 10-1 10.2.1 MAIN STEAM SYSTEM 10-1 10.2.2 PROCESS STEAM SYSTEM 10-1 10.2 3 TURBINE GENERATORS 10-2 10.2.4 CONDENSATE AIG FEED-WATER SYSTH4 10-2 10.2 5 CIRCULATING WATER SYSTEM 10-L 10 3 DESIGN EVALUATION 10-4
- 10 3 1 TRIPS AND AUTOMATI? CONTROL ACTIONS 10-4 10 3 2 SYSTEM MALFUNCTIONS 10-5 10 3 3 OVERPRESSURE PROTECTION 10 c
{ 10.4 TESTS AND INSPECTIONS 10-5 4
D 0279 10-1 i
LIST OF FIGURES (At Rear of Section) 3 Figure' No. -
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Title 10-1 Flow Diagra Unit 1 - Main Steam Feedvater Ccndensate & Frocess Stea Syste=c 10-2 Flev Diagram' Unit 2 - Main Steam Feedvater Condensate & Process Steam Systers t
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10 STEAL 4 AND POWER COUVERSION SYSTE'4 10.1 LESIGN BASES The s. team and power .conversicn system is designed to accept steam frcm the 6 .
NSS. Approxicately 75' percent of the steam heat' energy supplied by the MSS is used to generate electrical energy. Steam containing the remaining heat energy is transported to the site tcundary for pr eess use by Ecw. Most cf the steam is condensed and returned to the USS as heated feedvater. The steam not
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condensed is rephced by treated takeup from Dow.
10.2 SYSTE'4 LESCRIPTICII A'iD OPERATION The ficw diagram of the system is shown on Figures 10-1 and 10-2.
10.2.1 MAIN STFE4 SYSTEM Two steam generators are provided for each unit. Steam is generated in the shell side of the steam generators. The steam for each unit is then conducted through two main headers to the turbine stop valves. Each main steam header is provided with safety valves which tack up the main steam bypass and dump system.
Steam is taken from the main steam lines for use in the turbine steam seals and in the plant auxiliary steam system. Heating steam is taken from the turbine cycle.
The main steam piping is arranged so that the Unit 1 main steam system can be supplied with steam from Unit 2 when the Unit 1 reactor is shut down. This allows continued utilization of process steam for electrical generation, which is more economical then throttling in this condition. A main steam turbine bypass and atmospheric dump system is provided for each unit to automatically dump 100 percent of full load following a turbine trip. A signal from the main steam system actuates the steam damp system. The bypass system to the condensers and atmospheric dump, in conjunction with the reactor coolant pressure control system, is adequate to prevent reactor trip from load re-Jections of approximately 100 percent. During normal shutdown, steam is dumped to the main condenser for initial decay heat removal and cooldown.
10.2.2 PROCESS STEAM SYSTEM Process steam is nor= ally furnished from the cycle as follows:
- a. h00,000 lb/h at 675 psia, throttled from Unit 1 main steam.
- b. 3,650,000 lb/h at 197 psia, frc= the Unit 1 turbine moisture separators.
0781 10-1 Amendment H3. 2 5/2 8, 59 s
Two headers transport the 197 psia steam to the site boundary. A single 7 header transports the 675 psia steam to the site bcundary.
(V Flow of 197 psia process steam from the Unit 1 turbines is uncontrolled.
Nonreturn valves are provided as required in the 197 psia extraction lines for protection of the turbine. . , ,
Eackup pressure reducing stations supply the 197 psia steam when the Unit 1 turbine is out of service or when the station electrical load demand is too low for the Unit 1 turbine to furnish the required process steam pressure.
10.2 3 TURBDTE GENERATORS Two 1800 rpm, tandem-conpound indoor turbines are provided. The steam from the Unit 1 USS flevs through a two-flow high-pressure turbine and then through moisture separator reheaters and combined intercept and stop valves to one double-flow low-pressure turbine which exhausts to the main condenser. The-steam from the Unit 2 NSS flows through a two-flow high-pressure turbine and then through moisture separator reheaters and combined intercept and step valves to two double-flow low-pressure turbines which exhaust to the two main condensers.
Superheated steam is supplied to the throttle of each turbine from the steam generators -through four stop valves and the governing control valves.
Thelubricatingoilsystemofeachturbinesuppliesoilforlt$bricatingthe bearings. A bypass stream of turbine lubricating oil flows continuously through an oil conditioner to remove water and other impurities.
' The generators are direct-connected to the turbines and are water- (conductor) and hydrogen- (inner) cooled units. The generators have the capability to accept the gross rated output of the turbine at rated steam conditions. The exciters are of the direct-connected silicon diode rectifier type. The genera-tor glands are oil sealed to prevent hydrogen leakage.
10.2.4 CONDENSATE AND FEED-WATER SYSTEM One condenser is installed perpendicular to the turbine spindle under eacc low-pressure cylinder, for a total. of three condensers. The condensers are of the deaerating type and are sized to condense exhaust steam from the main tur-bines, and the feed pump turbine drivers, and, to cool the drains from the two I lovest-pressure heaters. The condensers are also capable of condensing by-I passed steam from the main steam headers.
Each unit is provided with a twin element steam-jet air ejector with inter-and aftercoolers to maintain condenser vacuum. Initial evacuation of the con-denser is accomplished by a steam hogging ejector. Air ejector vapor discharge
, i V
0282 10-2 Amendment No. 2 5/28/69
fs .is. monitored for radioactivity. Air ejector vapor is discharged through the
. ( ,) stack.
Each unit is provided with two half-capacity electric motor-driven condensate pumps which pump the. condensate through the air ejector, gland steam condenser, l7 s
c demineralizers, .and. three stages of . low-pressure
- feed-water heaters to the suction of two half-capacity electric motor-driven feed-water booster pumps.
The feedwater is pumped through two stages of high-pressure feed-water heaters to the steam generators by the two half-capacity turbine-driven steam gen-erator feed-water pumps of each unit.
Condensate demineralizers are provided for 100 percent of maximum condensate flov in order to meet steam generator water purity requirements. Process returns are nor= ally ad=1tted to the Unit 1 condenser. These are desineralized in the condensate and demineralizers.
The feed pump turbines are supplied with steam from the main turbine cross-arounds downstream of _ the reheaters with backup supply from the main steam headers.
Two redundant auxiliary feed-water pu=ps are installed for each unit to supply water to the steam generators during plant start-up and on loss of station power. These pumps are described further in Section 9.8.
The feed-water each heater containing five cycle for each unit consists of two parallel trains, heaters.
Each train carries half of the feed-water flow and contains three low-pressure heaters and two high-pressure heaters in
(,j series.
The last low-pressure heaters are open deaerating heaters. All other heaters are of the closed type.
Flov of feed-water heating extraction steam from the turbine extraction ports is uncontrolled. Air-operated nonreturn valves or check valves are provided as required in the extraction lines for protection of the turbine. The air-operated valves are actuated by heater high water level or tur bine overspeed.
Extraction spill valves and lines to the condenser are provided for use when the nonreturn valves are closed, to insure continued moisture removal from the turbines.
Drains from the two-stage reheater tube sides are discharged through reheater drain tanks to the feed-water heaters. With the exception of the deaerating heaters, all heaters are arranged so that their draina normally cascade to the next lower heater in the cycle. An automatic drain control valve is provided for normal. draining of each closed heater. Alternate drain lines, each with an automatic drain dump valve discharging to the condenser, are also provided for all heaters.
The main feed-water piping is so arranged that the Unit 2 USS can be supplied with feedvater from the Unit 1 feed-water system when the Unit 1 reactor is shut devn.
i/
0283 10-3. Amendment No. 2 s/28/69
(,,~I Valving in the feed-water system is provided to permit bypassing the closed feed-water heaters in each train. Feed-water regulator valves are provided on the supply lines to each steam generator. Feed-water regulation is described in Section 7 s , a
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' 'ChemicEis are addNd'to the Seed water headers downstream of the condensate pumps for oxygen scavenging and pH control.
A condensate storage tank is provided for each unit. A condensate transfer pump is provided per tank to supply condensate makeup to the -various systems,
. Automatic controls for makeup to and reject from the condensers, maintaining the condenser hot well levels, are provided.
The total flow of process returns, described previously, includes an allowance for normal primary and secondary system losses in addition to replacement of the total process steam delivery.
10.2 5 CIRCUIATING WATER SYSTEM Cooling water is stored in a cooling pond. The pond is enclosed by a dike.
Overflow spillways control the maximum pond elevation, anu low-level gates provide for periodic blowdown discharge to the Tittabawassee River. Cooling pond makeup water is taken from the river during at least nine months of the year. The pond is sized to allow for all water losses from the pond, without makeup, during the three-month period when river flov is low.
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4 Circulating water for the condensers is taken from the cooling pond. Four vertical, wet pit circulating water pumps, two for each unit are installed adjacent to the screen wells from which they take suction. The circulation
. water piping is arranged in four parallel lines with one pump discharging through one line to one of the water boxes on the condensers. A chlorinat-ing facility is provided for algae and slime control.
Two pumps-on the north dike, adjacent to the river, provide for cooling pond makeup.
10 3 DESIGN EVAIDATION All parts of this system are designed and fabricated in accordance with appli-cable codes. The components are similar to those which have experienced service in operating power plants. Adequate protective devices and controls are provided to assure reliable and safe operation.
10 3 1 TRIFS AND AUTOMATIC COITIROL ACTIONS Trips and automatic control actions are described in Section 7.4.
, 0284 10-4 Amend =ent No. 2 5/28/69
(m) v 10 3 2 SYSTEM MAIEUNCTIONS The effects of inadvertent steam relief or steam bypass are covered by the anaksis of the -steam line failure given in 14.1.2.9 The effects of an in-
", s . advertent rapid. throttle valve closure are. covered by the' loss of: full load-discussion in 14.1.2.8.
10 3 3 OVERPRESSURE PROTECTION Pressure relief is required at the system design pressure of 1050 psig, and the first safety valve bank will be set to relieve at this pressure. The design pressure is based en the operating pressure of 925 psia plus a 10 percent allevance for transients and a 4 percent allowance for blevdown. Additional safety valve tanks are set at pressures up to 110L psig, as allowed by the ASME Code.
The pressure relief capacity is such that the energy generated at..the rated NSS steam flow can be dissipated through this system.
10.4 TESTS AND INSPECTIONS Equipment, instruments and controls are regularly inspected in order to insure proper functioning of systems.
The turbine stop valves, combined intermediate valves, extraction line non-return valves, main steam bypass system and the auxiliary feed-water pu=ps may be tested while the turbines are in operation.
Lifting levers are provided on the safety valves, as required by the ASIE Boiler and Pressure Vessel Code,Section VIII.
In addition, all equipment, instruments and controls will be thoroughly checked and inspected when these are not in use during refueling periods.
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Crystal River Units 3&4 Nuclear Generating Plant REllMINARY A AFETY o ~
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J2_. /c;2 d Docket Nos . 50-302 50-303 February 7, 1968
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I AMENDMENT NO. 2 FLORIDA PO'JER CORPORATION Crystal River Plant Units 3 & h Amendment No. 2 to the Florida Power Corporation's Preliminary Safety Analysis Report includes both insert pages, as listed below, _ and Supplement No.1.
Supplement No.1 consists of the response to the letter dated January 19, 1968 from Dr. Peter A. Morris, Director, Division of Reactor Licensing. The supple-ment also contains answers to the " Requested Additional Information" by D.R.L.
en January 19, 1968 (1.0 through 9.15).
NOTE Inclosed herewith, immedtately following the instruction sheets, you will find a title sheet entitled " Appendices" and a complete Table of Contents (pages "i" through "vii"). These sheets are to be inserted in the binder entitled " APPENDICES which accompanies this amendT.ent.
Remove the contents in existing Volume h--from the tab entitled " APPENDIX" to the end of the volume (Appendix 12A)--and insert all accendices in the binder enhtled
" APPENDICES." (The title sheet and table of contents in existing Volume h should remain in place.)
The fol10 wing sheets of the Florida Power Corporation's Preliminary Safety Analysis Report are to be deleted and, where appropriate , revised sheets dated 2-7-68 should be inserted.
Remove the fcilowing sheets: Insert the following sheets:
Pages: Table of contents - vii Pages: Table of contents - vii (one each in Volumes 1, 2, 3, and h) (one each in Volumes 1, 2, 3, and 4)
Pages: 1 ,, 1-28, 1-29, 1-30, 1-35, Pages: 1-27, 1-28, 1-29, 1-30, 1-35, ,
and 1-36. and 1-36. ;
Fiaures: 1-2, 1-3, 1 h, 1-5, 1-6, 1-7, Figures: 1-2, 1-3, 1 4, 1-5, 1-6, 1-7, l 1-9, and 1-12. 1-9, and 1-12.
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Pages: 5-17, 5-18, and 5-19. Pages: 5-17, 5-18, and 5-19.
Figure: 5-6. Figure: 5-6.
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Docket Nos. 50-302
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. AMENDMENT.,NO.. 1 ,,, ,
FLORIDA POWER CORPORATION Crystal River Plant Units 3 & L
' Preliminary Safety
, The following sheets of the Florida Power Corporat ion s Analysis fieport are to be deleted; and, where appropriate, revised cheets dated 1-15-68 should be inserted.
Insert the following sheets:
Remove the following sheets:
Pages: ' Table of contents - iv and Faces: Table of contents - iv and vi (one each in volumes 1, 2, 3, vi (one each in volumes 1, 2, 3, and h). and b).
1-3, 1 4, 1-13, 1-14, 1-25, Pages: 1-3, 1 4, 1-13, 1-14, 1-25, Paces: 1-26, 1-27, 1-28, 1-29, 1-30, 1-31, 1-26, 1-27, 1-28, 1-29, 1-30, 1-31, 1-32,1-33,1-34, and 1-35 1-32,1-33,1-3h , and 1-35 1-2 , 1- 3, 1-4 , 1-5 , 1-6 , Figures: 1-2, 1-3, 1-4, 1-5, 1-6, Figures:
1-T, 1-8, 1-9, 1-10, 1-11, and 1-14. 1-7, 1-8, 1-9, 1-10, 1-11, and 1-14.
Pages: 2-3, 2 4, 2-5, 2-6, 2-T, 2-8, Pages: 2- 3, 2 h , 2-5, 2-6, 2-T , 2-6, 2-11, and 2-12. 2-11, and 2-12.
M U Pages: 3-vi, 3-3, 3 4, 3-5, 3-6, 3-9, Pages: 3-vi, 3-3, 3 h, 3-5, 3 6, 3-9, 3-10, 3-11, 3-12, 3-13, 3-14, 3-31, 3-32, 3-10, 3-11, 3-12, 3-13, 3-14, 3-31, 3-6T, 3-68, 3-69, 3-TO, 3-71, 3-72, 3-87, 3-32, 3-67, 3-68, 3-69, 3-70, 3-71, 3-88, 3-89, 3-90, 3-91, 3-92, 3-95, 3-96, 3-72, 3-72a, 3-72b, 3-87, 3-88, 3-89, 3-97, 3-98, 3-103, and 3-104. 3-90, 3-90a, 3-90b , 3-91, 3-92, 3-95, 3-96, 3-97, 3-98, 3-103, 3-103a, 3-103b, and 3-104.
Figures: 3-1, 3-2, 3-5, 3 6, 3-39, 3 h0, Figures: 3-1, 3-2, 3-5, 3-6, 3-39, 3-57, 3-58, 3-61, 3-62, 3-65, 3-66, 3-67, 3 40, 3-57, 3-58, 3-61, 3-61a, 3-62, 3-65, 3-66, 3-67, and 3-68.
and 3-68.
Pages: h-3, h 4, h-15, h-16, h-23, h-24, Pages: h-3, h h, h-15, 4-16, h-23, h-25, h-26, 4-27, h-28, h-33, h-34, h-35, 4-24, 4-25, 4-26, h-27, h-28, 4-33, 4-3h, h-35, and h-36.
and 4-36.
5-11, 5-111, 5-3, 5 h, 5-5, 5-6, Pages: 5-11, 5-111, 5-3, 5-4, 5 ha, Pages:
5-7, 5-8, 5-9, 5-10, 5-11, 5-12, 5-13, 5-5, 5-6, 5-7, 5-Ta, 5-8, 5-8a, 5-9, 5-14, 5-15, 5-16, 5-17, 5-18, and 5-20. 5-10, 5-11, 5-12, 5-13, 5-14, 5-15,
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5-16, 5-16a, 5-17, 5-18, and 5-20.
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Docket Nos. 50-302
- 50-303 Remove the following sheets: Insert the following sheets:
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Figure: 5-5 Figure: 5-5 Pages: 6-11, 6-12, 6-13,-6-14, 6-19, Pages: 6-11, 6-12, 6-13, 6-14, 6-20, 6-21, and 6-22. 6-1976-20,6-21,and6-22.
Pages: 7-5, 7-6, 7-7, 7-8, 7-17, Pages: 7-5, 7-6, 7-i, 7-8, 7-17, 7-18, 7-19, 7-20, 7-23, 7-24, 7-27, 7-18, 7-19, 7-20, 7-23, 7-24, 7-27, 7-28, 7-29, 7-30, 7-31, and 7-32. 7-28, 7-29, 7-30, 7-31, and 7-32.
/igures: 7-2, 7-11, and 7-12. Figures: 7-2, 7-11, and 7-12.
Pages: 8-1, 8-11, 8-1, 8-2, 8-3, Pages: 8-1, 8-ii, 8-1, 8-2, 8-3, 8-4, 8 ,5, 8-6, 8-7, 8-8, and 8-9 8-4, 8-5, 8-6, 8-7, 6-8, 8-9, 8-10,
- 8-11, and 8-12.
Figure: 8-l '. Figure: 8-1.
Paces: 9-1, 9-2, 9-7, 9-8, 9-9, 9-10, Pages: 9-1, 9-2, 9-7, 9-8, 9-9, 9-11, 9-12, 9-13, 9-14, 9-15, 9-16, 9-10, 9-11, 9-12, 9-13, 9-14, 9-15, 9-25, 9-26, 9-29, 9-30, and 9-37. 9-16, 9-25, 9-26, 9-29, 9-30, 9-37, and 9-37a.
Figures: 9-3, 9 4, 9-8, and=9=.W.- Figures: 9-3, 9-4, 9-8, emL +.10.
4 Dages: 10-1, 10-2, 10-3, 10-4, and Pages: 10-1, 10-2, 10-3, 10-4, and
(] 10-5 10-5.
Figure: 10-1. Figure: 10-1.
Pages: 11-3, 11-4, 11-5, 11-6, 11-7, Pages: 11-3, 11-4, 11-5, 11-6, 11-7, 11-8, 11-9, 11-10, 11-11, 11-12, 11-23, 11-8, 11-9, 11-10, 11-11,11-11a, 11-24, 11-29, and 11-30. 11-12, 11-23, 11-24, 11-29, and 11-30.
Figure: 11-1. Figure: 11-1.
Pages: 12-1, 12-1, 12-2, 12-5, 12-6, Pages: 12-1, 12-1, 12-2, 12-5, 12-6, 12-7, and 12-8. 12-6a, 12-7, and 12-8.
Figure: 12-1. Figure: 12-1.
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Dockst Noa. 50-302' 50-303 f73 , Remove the following sheets: Insert the following sneets:
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Paces: 14-11, 14-v, 14-3, 14-4, Fages: 14-11, 14-v, 14-v(a), 14-3, 14-5, 14-6, 14-7, 14-8, 14-9, 14-10, 14-4, 14-5, 14-6, 14-7, 14-8, 14-9, 14-15, 14-16, 14-17, 14-18, 14-21, 14-10, 14-15,,J4-16, 14-17, 14-18, 14-22, 14-23, 14-24, 14-25, 14-26, 14-21, 14-22, 14-23, 14-24, 14-25, 14-27, 14-28, 14-29, 14-30, 14-35, 14-26, 14-27, 14-28, 14-29,-14-30, 14-36, 14-39, 14-40, 14-41, 14-42, 14-35, 14-36, 14-39,14-39a, 14-40,'
14-43, 14-44, 14-49, 14-50, 14-53, 14 41,14-41a, 14-41b,14-41c, 14 41d, and 14-54. 14-42, 14-43, 14 44, 14-49, 14-50, 14-53, and 14-54.
Figures: 14 42. Figures: 14-34 a ,14-34b ,14-40a ,
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14-41a, 14-42, 14 44a,14-44b, 14-44c, 1k 44d,14-44e, and 14-4kf.
Pages: 1A-1, lA-2, lA-3, and 1A 4 Pages: lA-1, lA-2, lA-3, 1A-4, and 1A-ha.
Pages: Cover Sheet--Appendix 2C Pages: Cover Sheet--Appendix 2C and all sheets up to and including Cover Sheet- "2. Flood Studies for Crystal River Nuclear Power Plant."
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Your revised Appendix 2C will now include two separate sections:
(1) " Plant Protection Against Hurri-cane Wave Action"...this is a new section included with this amendment and not found in the original P.S. A.R.
(2) " Flood Studies for Crystal River Nuclear Power Plant"...the original Appendix 2C, which now becomes Section 2 of Appendix 2C.
Pares: 2G-1 to and including 2G-85. Pagec: 2G-1 to and including 2G-119.
Figures: 2G-1, 2G-6, 2G-7, and 2G-8. Figures: 2G-1, 2G-6, 2G-7, and 2G-8.
Pages: 5A-1, 5A-2, 5A-3, and 5A-4. Pages: SA-1, 5A-2, SA-2a, 5A-3, and 5A-4.
Figure: Figure: 5A-1.
Paces: 5B-1, 5B-2,'5B-3, 5B-4, and Pages: 5B-1, 5B-2, 5B-3, SB-4, 5B-5, 5B-5 SB-6, 5B-7, SB-8, 53-9, 5B-10, 5B-11, 5 5B-12, 5B-13, and 5B-14 Figures: Figures: 5B-1, 53-2, 5B-3, SB 4, 5B-5, SB-6, 5B-7, and 5B-8.
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Docket Hos. 50-302
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!~p. " : ,Pages: SC-1 and SC-2.
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Pages: SC-1, SC-2, SC-2a, and SC-2b.
Figure: Figure: SC-1.
Pages: SD-1, SD-2, SD-3, 5D-4, Pages: SD-1, SD-2, SD-3, SD-h, 5D-5, 5D-6, and SD-7. SD-5, SD-6, SD-7, 5D-8, 5D-9, and SD-10.
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TABLE OF CONTENTS Section Pgge 1 INTRODUCTION AND
SUMMARY
. . . . Volume 1 . . Tab 1 . . 1-1
1.1 INTRODUCTION
. . . . . . . . . . . . . . . . . 1-1 1.2 DESIGN HIGHLIGHTS . . . . . . . . . . . . . . . . 1-2 1.2.1 SITE CHARACTERISTICS . . . . . . . . . . . . . . 1-2 1.2.2 POWER LEVEL . . . . . . . . . . . . . . . . . 1-2 1.2.3 PEAK SPECIFIC POWER LEVEL . . , . . . . . . . . 1-2 1.2.h REACTOR BUILDING SYSTEM . . . . . . . . . . . . 1-2 1.2.5 ENGINEERED SAFEGUARDS . . . . . . . . . . . . . . 1-3 1.2.6 ELECTRICAL SYSTE!S AND DfERGENCY POWER . . . . . . . . 1-3 1.2.7 ONCE-THROUGH STEAM GENERATORS . . . . . . . . . . . 1-4 1.3 TABULAR CHARACTERISTICS . . . . . . . . . . . . . . 1-h 1.h FRINCIPAL DESIGN CRITERIA . . . . . . . . . . . . . 1-7 1.h.1 CRITERION 1 . . . . . . . . . . . . . . . . . 1-7 1.4.2 CRITERION 2 . . . . . . . . . . . . . . . . . 1-9 1.k.3 CRITERION 3 . . . . . . . . . . . . . . . . . 1-10 1.k.h CRITERION k . . . . . . . . . . . . . . . . . 1-10 1.4.5 CRITERION 5 . . . . . . . . . . . . . . . . . 1-11 1.h.6 CRITERION 6 . . . . . . . . . . . . . . . . . 1-11 1.k.7 CRITERION 7 . . . . . . . . . . . . . . . . . 1-12 1.k.8 CRITERION 8 . . . . . . . . . . . . . . . . . 1-13 1.h.9 CRITERION 9 . . . . . . . . . . . . . . 1-13 O.
1.4.10 CRITERION 10 . . . . . . . . . . . . . . . . . 1-lk 1.k.11 CRITERION 11 . . . . . . . . . . . . . . . . 1-15 1.h.12 CRITERION 12 . . . . . . . . . . . . . . . . . 1-15 1.k.13 CRITERION 13 . . . . . . . . . . . . . . . . . 1-16 1.4.14 CRITERION 1h . . . . . . . . . . . . . . . . . 1-17 1.k.15 CRITERION 15 . . . . . . . . . . . . . . . . 1-2 ?
1.h.16 CRITERION 16 . . . . . . . . . . . . . . . . . 1-18 1.h.17 CRITERION 17 . . . . . . . . . . . . . . . . . 1-19 1.k.18 CRITERION 18 . . . . . . . . . . . . . . . . . 1-20 1.4.19 CRITERION 19 . . . . . . . . . . . . . . . . . 1-21 1.k.20 CRITERION 20 . . . . . . . . . . . . . . . . . 1-22 1.h.21 CRITERION 21 . . . . . . . . . . . . . . . . . 1-22 1.h.22 CRITERION 22 . . . . . . . . . . . . . . . . . 1-22 1.4.23 CRITERION 23 . . . . . . . . . . . . . . . . . 1-23 1.4.2h CRITERION 24 . . . . . . . . . . . . . . . . . 1-2h 1.h.25 CRITERION 25 . . . . . . . . . . . . . . . . . 1-2k 1.h.26 CRITERION 26 . . . . . . . . . . . . . . . . . 1-25 1.h.27 CRITERION 27 . . . . . . . . . . . . . . . . 1-26 1.5 RESEARCH AND DEVELOPMENT REQUIREMENTS . . . . . . . . . 1-26 1.5.1 CNCE-THROUGH STEAM GENERATOR TEST . . . . . . . . . . 1-26 -
1.5.2 CONTROL ROD DRIVE LINE TEST . . . . . . . . . . . 1-26 1.5.3 SELF-POWERED DETECTOR TESTS . . . . . . . . . . . . 1-27 1.5.4 THERMAL AND HYDRAULIC PROGRAMS . . . . . . . . . . . 1-27 1.6 IDENTIFICATION OF AGENTS AND CONTRACTORS . . . . . . . . 1-27
1.7 CONCLUSION
S . . . . -. . . . . . . . . . . . . . 1-28 O
V 0297 i
q Section Page 2 SITE AND ENVIRONMENT . . . . . Volume 1 . . . Tab 2 . . 2-1 2.1
SUMMARY
. . . . . . . . . . . . . . . . . . . 2-1 2.2 SITE AND ADJACENT AREAS . . . . . . . . . . . . . . 2-1 2.2.1 SITE LOCATION AND TOPOGRAPHY , . . . . . . . . . . 2-1 2.2.2 SITE OWNERSHIP . . . . . . . . . . . . . . . . 2-2 2.2 3 SITE ACTIVITIES . . . . . . . . . . . . . . . . 2-2 2.2.h POPULATION . . . . . . . . . . . . . . . . . 2-3 2.2.5 LAND USE . . . . . . . . . . . . . . . . . . 2-3 2.2.6 DAIRY ANLJALS . . . . . . . . . . . . . . . . 2-3 2.3 METEOR 0ILGY AND CLIMATOLOGY . . . . . . . . . . . . 2-3 2 3.1
SUMMARY
. . . . . . . . . . . . . . . . . . 2-3 2.3.2 DESCRIPTIVE METEOROLOGY . . . . . . . . . . . . . 2h 2.3.3 ATMOSPHERIC DIFFUSION . . . . . . . . . . . . . . 2-7 2.3.h SITE METEOROLOGICAL PROGRAM . . . . . . . . . . . . 2-9 -
2.h HYDROLOGY . . . . . . . . . . . . . . . . . . 2-10 2.4.1 CHARACTERISTICS OF STREAMS IN VICINITY . . . . . . . . 2-10 2.h.2 FLOOD STUDIES AND HURRICANE t m CTS . . . . . . . . . 2-11 2.h.3 DESIGN OF CIRCULATING WATER SYSTEM . . . . . . . . . 2-11 2.h.4 LIQUID WASTE DISCHARGES . . . . . . . . . . . . . 2-12 2.h.5 GROUNDWATER . . . . . . . . . . . . . . . . . 2-12 2.5 GEOLOGY . . . . . . . . . . . . . . . . . . . 2-12 2.6 SEISMOLOGY , . . . . . . . . . . . . . . . . . 2-13 2.6.1 SEISMICITY STUDY . . . . . . . . . . . . . . . 2-13 f) 2.6.2 RESPONSE SPECTRA . . . . . . . . . . . . . . . 2-13 V 27 SITE ENVIRONMENTAL RADIOACTIVITY PROGRAM . . . . . . . . 2-13
2.8 REFERENCES
. . . . . . . . . . . . . . . . . . 2-14 3 REACTOR . . . . . . . . . . Volume 1 . . . Tab 3 . . 3-1 31 DESIGN BASES . . . . . . . . . . . . . . . . . 3-1 3.1.1 PERFORMANCE OBJECTIVES . . . . . . . . . . . . . 3-1 3.1.2 LIMITS . . . . . . . . . . . . . . . . . . . 3-1 3.2 REACTOR DESTGN . . . . . . . . . . . . . . . . . 3-6 3.2.1 GENERAL SUiEARY . . . . . . . . . . . . . . . . 3-6 3.2.2 NUCLEAR'DIdiGN AND EVALUATION . . . . . . . . . . . 3-7 3.2.3 THERMAL AND HYDRAULIC DESIGN AND EVALUATION . . . . . . 3-32 3.2.4 MECHANICAL DESIGN LAYOUT . . . . . . . . . . . . . 3-68 3.3 TESTS AND INSPECTIONS . . . . . . . . . . . . . . 3-95 3.3.1 NUCLEAR TESTS AND INSPECTION . . . . . . . . . . . 3-95 3.3.2 THERMAL AND HYDRAULIC TESTS AND INSPECTION . . . . . . . 3-95 3.3.3 FUEL ASSD4BLY, CONTROL ROD ASSEMBLY, AND CONTROL ROD DRIVE MECHANICAL TESTS AND INSPECTION . . . . . . . . . . 3-98 3.3.h INTERNALS TESTS AND INSPECTIONS . . . . . . . . . . 3-103
3.4 REFERENCES
. . . . . . . . . . . . . . . . . . 3-104 h REACTOR COOLANT SYSTB4 . . . . . Volume 1 . . . Tab h . . 4-1 h.1 PERFORMANCE OBJECTIVES . . . . . . . . . . . . . . h-1 4.1.2 DESIGN CHARACTERISTICS . . . . . . . . . . . . . 4-1 I) v 4.1.3 EXPECTED OPERATING CONDITIONS . . . . . . . . . . . h-2 u 0298
Section G .
Page
. s 4 REACTOR COOLANT SYSTD4 (CONTINUED) . Volume 1 . . . Tab h h.1.h SERVICE LIFE . . . . . . . . . . . . . . . . . h-3 h.l.5 CODES AND CLASSIFICATIONS . . . . . . . . . . . . 4-6 h.2 SYSTEM DESCRIPTION AND OPERATION . . . . . . . . . . . 4-6 h.2.1 GENERAL DESCRIPTION . . . . . . . . . . . . . . 4-6 h.2.2 MAJOR COMPONENTS . . . . . . . . . . . . . . . 4-6 4.2.3 PRESSURE-RELIEVING DEVICES . . . . . . . . . . . . 4-12 4.2.4 ENVIRONMENTAL PROTECTION . . . . . . . . . . . . . h-12 4.2.5 MATERIALS OF CONSTRUCTION . . . . . . . . . . . . 4-12 h.2.6 MAXIMUM HEATING AND COOLING RATES . . . . . . . . . . 4-lh h.2.7 LEAK DETECTION . . . . . . . . . . . . . . . . h-14 h.3 SYSTB4 DESIGN EVALUATION . . . . . . . . . . . . . h-16 h.3.1 SAFETY FACTORS . . . . . . . . . . . . . . . . L-16 h.3.2 RELIANCE ON INTERCONNECTED SYSTD4S . . . . . . . . . 4-23
). 3.3 SYSTEM INTEGRITY . . . . . . . . . . . . . . . 4-23 h.3.h PRESSURE RELIEF . . . . . . . . . . . . . . . . h-23 4.3.5 REDUNDANCY . . . . . . . . . . . . . . . . . h-2h h.3.6 SAFETY ANALYSIS . . . . . . . . . . . . . . . . 4-2h 4.3.7 OPERATIONAL LIMITS . . . . . . . . . . . . . . . h-2h h.h TESTS AND INSPECTIONS . . . . . . . . . . . . . . h-25 4.h.1 COMPONENT IN-SERVICE INSPECTION . . . . . . . . . . h-25 h.h.2 REACTOR COOLANT SYSTEM TESTS AND INSPECTIONS . . . . . . h-27 h.h.3 MATERIAL IRRADIATION SURVEILLANCE . . . . . . . . . . 4-28
4.5 REFERENCES
4-30 O
5' CONTAINMENT SYSTEM . . . . . . Volume 2 . . . Tab 5 . . 5-1 5.1 REACTOR BUILDING . . . . . . . . . . . . . . . . 5-1 5.1.1 DESIGN BASES . . . . . . . . . . . . . . . . . 5-1
! 5.1.2 STRUCTURE DESIGN . . . . . . . . . . . . . . . 5-2 5.2 ISOLATION SYSTEM . . . . . . . . . . . . . . . . 5-9 5.2.1 DESIGN BASES . . . . . . . . . . . . . . . . . 5-9 5.2.2 SYSTEM DESIGN . . . . . . . . . . . . . . . . 5-10 5.3 VENTILATION SYSTEM . . . . . . . . . . . . . . . 5-11 5.3.1 DESIGN BASES . . . . . . . . . . . . . . . . . 5-11 5.3.2 SYSTEM DESIGN . . . . . . . . . . . . . . . . 5-12 ;
5.h LEAKAGE MONITORING SYSTB4 . . . . . . . . . . . . . 5-13 55 SYSTEM DESIGN EVALUATION . . . . . . . . . . . . . 5-15 5.6 TESTS AND INSPECTION . . . . . . . . . . . . . . . 5-15 5.6.1 PREOPERATIONAL TESTING AND INSPECTION . . . . . . . . 5-15 5.6.2 POSTOPERATIONAL LEAK MONITORING . . . . . . . . . . 5-16 6 ENGINEERED SAFEGUARDS . . . . . Volume 2 . . . Tab 6 . . 6-1 6.1 EMERGENCY INJECTION . . . . . . . . . . . . . . . 6-1 6.1.1 DESIGN BASES . . . . . . . . . . . . . . . . . 6-1
. 6.1. 2 - DESCRIPTION . . . . . . . . . . . . . . . . . 6-2 6.1.3 DESIGN EVALUATION . . . . . . . . . . . . . . . 6-3 6.1.h TESTS AND INSPECTIONS', . . . . . . . . . . . . 6-6 6.2
() 6.2.l' REACTOR BUILDING ATMOSPHERE COOLING AND WASHING .
DESIGN BASES . . . . . . . . . . . .
6-13 6-13 iii 0299
Section Pgge
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V' 6 ENGINEERED SAFEGUARDS (CONTINUED) . Volume 2 . . . Tab 6' 6.
2.2 DESCRIPTION
. . . . . . . . . . . . . . . . . 6-13 6.2.3 DESIGN EVALUATION . . . . . . . . . . . . . . . 6-lh 6.2.4 TESTS AND INSPECTIONS . . . . . . . . . . . . . . 6-19 6.3 ENGINEERED SAFEGUARDS LEAKAGE AND RADIATION CONSIDERATIONS . . . . . . . . . . . . . . . . 6-20 6.
3.1 INTRODUCTION
. . . . . . . . . . . . . . . . . 6-20 6.3.2 SlH ARY OF POSTACCIDENT RECIRCULATION AND LEAKAGE CONSIDERATIONS . . . . . . . . . . . . . . . 6-20 6.3.3 LEAKAGE ASSUMPTIONS . . . . . . . . . . . . . . 6-21 6.3.4 DESIGN BASIS LEAKAGE . . . . . . . . . . . . . . 6-22 6.3.5 LEAKAGE ANALYSIS CONCLUSIONS . . . . . . . . . . . 6-22 7 INSTRUMENTATION AND CONTPOL , . . Volume 2 . . . Tab 7 . . 7-1 7.1 PROTECTION SYSTEMS . . . . . . . . . . . . . . . 7-1 7.1.1 DESIGN BASES . . . . . . . . . . . . . . . . . 7-1 7.1.2 SYSTEM DESIGN . . . . . . . . . . . . . . . . 7-5 7.1.3 SYSTEMS EVALUATION . . . . . . . . . . . . . . . 7-11 7.2 REGULATING SYCTEMS . . . . . . . . . . . . . . . 7-15 7.2.1 DESIGN BASES . . . . . . . . . . . . . . . . . 7-15 T.2.2 SYSTEM DESIGN . . . . . . . . . . . . . . . . 7-17 7.2.3 SYSTEM EVALUATION . . . . . . . . . . . . . . . 7-22 7.3 INSTRUMENTATION , . . . . .
7-25
T 7.3.1 (V 7.3.2 NUCLEAR INSTRUMENTATION .
NONNUCLEAR PROCESS INSTRUMENTATION 7-25 7-27 7.3.3 INCORE MONITORING SYSTEM . . . . . . . . . . . . . . . 7-28. -
7.h OPERATING CONTROL STATIONS . . . . . . . . . . . . 7-31 7.4.1 GENERAL LAYOUT . . . . . . . . . . . . . . . . 7-31 7.4.2 INFORMATION DISPLAY AND CONTROL FUNCTION . . . . . . . 7-31 7.h.3
SUMMARY
OF ALARMS . . . . . . . . . . . . . . . 7-31 7.h.h COMMUNICATION . . . . . . . . . . . . . . . . 7- 32 7.h.5 OCCUPANCY . . . . . . . . . . . . . . . . . . 7-32 7.h.6 AUXILIARY CONTROL STATIONS . . . . . . . . . . . . T-33 7.h.7 SAFETY FEATURES . . . . . . . . . . . . . . . . 7-33 8 ELECTRICAL SYSTEMS Volume 2 .
. . . . . . . . Tab 8 . . 8-1 8.1 DESIGN BASES . . . . . . . . . . . . . . . . . 8-1 8.2 ELECTRICAL SYSTEM DESIGN . . . . . . . . . . . . . 8-1 8.2.1 NETWORK INTERCONNECTIONS . . . . . . . . . . . . 8-1 8.2.2 PLANT DISTRIBUTION SYSTEM . . . . . . . . . . . . 8-2 8.2.3 SOURCES OF AUXILIARY POWER , . . . . . . . . . . . . 8-6 8.3 TESTS AND INSPECTIONS . . . . . . . . . . . . . . 8-9l1 9 AUXILIARY AND EMERGENCY SYSTEMS . Volume 2 . Tab 9 .
. . . . 9-1 9.1 MAKEUP AND PURIFICATION SYSTEM . . . . . . . . . . . 9-2 O
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9 AUXILIARY AND D4ERGENCY SYSTD4S (CONTINUED) . Volume 2 . . Tab 9 9.1.1 DESIGN BASES . . . . . . . . . . . . . . . . 9-2 9.1.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9-3 9.' 2 CHEMICAL ADDITION AND SAMPLING SYSTEM . . . . . . . . 9-9 9.2.1 . DESIGN BASES . . . . . . . . . . . . . . . . 9-9 9.2.2 SYSTE4 DESCRIPTION AND EVALUATION . . . . . . . . . 9-10 9.3 COOLING WATER SYSTE4S . . . . . . . . . . . . . . 9-18 9.3.1 DESIGN BASES . . . . . . . . . . . . . . . . 9-18 9.3.2 SYSTE4 DESCRIPTION AND EVALUATION . . . . . . . . . 9-19 9.h SPENT FUEL COOLING SYSTE4 . . . . . . . . . . . . 9-2h 9.4.1 DFSIGN BASES . . . . . . . . . . . . . . . . 9-2h 9.h.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9-2h 95 DECAY HEAT REMOVAL SYSTEM . . . . . . . . . . . . 9-27 9.5.1 DESIGN BASES . . . . . . . . . . . . . . . . 9-27 9.5.2 SYSTE4 DESCRIPTION AND EVALUATION . . . . . . . . . 9-27 9.6 FUEL HANDLING SYSTE4 . . . . . . . . . . . . . . 9-31 9.6.1 DESIGN EASES . . . . . . . . . . . . . . . . 9-31 9.6.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9-32 9.7 PLANT VENTILATION SYSTEMS . . . . . . . . . . . . 9-37 9.7.1 DESIGN BASES . . . . . . . . . . . . . . . 9-37 9.7.2 SYSTE4 DESCRIPTION AND EVALUATION . . . . . . . . . 9-37 10 STEAM AND POWER CONVERSION SYSTD4 . Volume 2 . . . Tab 10. . 10-1 b 10.1 DESIGN BASES . . . . . . . . . . . . . . . . . 10-1 10.1.1 OPERATING AND PERFORMANCE REQUIRE 4ENTS . . . . . . . . 10-1 10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS . . . . . . . . . . 10-1 10.1.3 FUNCTIONAL LIMITATIONS . . . . . . . . . . . . . 10-1 10.1.h EECONDARY FUNCTIONS . . . . . . . . . . . . . . 10-1 10.2 SYSTEM DESIGN AND OPERATION . . . . . . . . . . . . 10-2 10.2.1 _ SCHEMATIC FLOW DIAGRAM . . . . . . . . . . . . . 10-2 10.2.2 CODES AND STANDARDS . . . . . . . . . . . . . . 10-2 10.2 3 DESIGN FEATURES . . . . . . . . . . . . . . . . 10-3 10.2.4 SHIELDING . . . . . . . . . . . . . . . . . . 10-3 10.2.5 CORROSION PROTECTION . . . . . . . . . . . . . . 10-3 10.2.6 IMPURITIES CONTROL . . . . . . . . . . . . . . . 10-3 10.2.7 RADI0 ACTIVITY , . . . . . . . . . . . . . . . 10-3 10.3 SYSTEM ANALYSIS . . . . . . . . . . . . . . . . 10-3 10.3.1 TRIPS, AUTOMATIC CONTROL ACTIONS, AND ALARMS . . . . . . 10-3 10.3.2 TRANSIENT CONDITIONS . . . . . . . . . . . . . . 10-4 10.3.3 MALFUNCTIONS , . . . . . . . . . . . . . . . 10-5 10.3.4 OVERPRESSURE PROTECTION . . . . . . . . . . . . 10-5 10.3.5 INTERACTIONS . . . . . . . . . . . . . . . . . 10-5 10.3.6 OPERATIONAL LIMITS . . . . . . . . . . . . . . . 10-5 10.h TESTS AND INSPECTIONS . . . . . . . . . . . . . . 10-5 0
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/s 11 RADI0 ACTIVE WASTES AND RADI/ TION' PROTECTION . . . . . . . . Volume 3 . . . Tab 11. . 11-1 11.1 RADI0 ACTIVE WASTES . . . . . . . . . . . . . . . 11-1 11.1.1 DESIGN BASES . . . . . . . . . . . . . . . . . 11-1 11.1.2 SYSTEM DESIGN . . . . . . . . . . . . . . . . 11-3 11.1.3 TESTS AND INSPECTIONS . . . . . . . . . . . . . . 11-12 11.2 RADIATION SHIELDING . . . . . . . . . . . . . . . 11-12 11.2.1 PRIMARY, SECONDARY, REACTOR BUILDING, AND AUXILIARY SHIELDING . . . . . . . . . . . . . . 11-12 11.2.2 AREA RADIATION MCNITORING SYSTEM . . . . . . . . . . 11-17 11.2 3 HEALTH PHYSICS . . . . . . . . . . . . . . . . 11-18 11.'s REFERENCES . . . . . . . . . . . . . . . . . . 11-22 12 CCNDUCT OF OPERATIONS . . . . . Volume 3 . . . Tab 12. . 12-1 12.1 ORGANIZATION AND RESPONSIBILITY . . . . . . . . . . . 12-1 12.1.1 FUNCTIONAL DESCRIPTION . . . . . . . . . . . . . 12-1 12.1.2 QUALIFICATIONS . . . . . . . . . . . . . . . . 12-2 12.1.3 ORGANIZATION DIAGRAM . . . . . . . . . . . . . . 12-2 12.2 TRAINING . . . . . . . . . . . . . . . . . . 12-2 12.2.1 STATION STAFF . . . . . . . . . . . . . . . . 12-2 12.2.2 REPLACEMENT PERSONNEL . . . . . . . . . . . . . . 12-5 12.2.3 ON-THE-JOB T3AINING , . . . . . . . . . . . . . 12-6 12.2.4 EiERGENCY PLANS . . . . . . . . . . . . . . . 12-6
' ') 12.2 5 PROCEDURES APPLICABLE TO ACCIDENTS INVOLVING RADIOACTIVE MATERIALS . . . . . . . . . . . . . 12-6 12.3 WRITTEN PROCEDURES . . . . .. . . . . . . . . .-
. 12-T ,
12.h RECORDS . . . . . . . . . . . . . . . . . . . 12-7 12.5 ADMINISTRATIVE CONTROL . . . . . . . . . . . . . . 12-7 13 INITIAL TESTS AND OPERATION . . . Volume 3 . . . Tab 13. . 13-1 13.1 TESTS PRIOR TO REACTOR FUELING . . . . . . . . . . . 13-1 13.2 INITIAL CRITICALITY . . . . . . . . . . . . . . . 13-1 13.3 POSTCRITICALITY TESTS . . . . . . . . . . . . . . 13-1 14 SAFETY ANALYSIS . . . . . . . Volume 3 . . . Tab 14. . 14-1 14.1 CORE AND COOLANT BOUNDARY PROTECTION ANALYSIS . . . . . . Ih-1 14.1.1 ABNORMALITIES . . . . . . . . . . . . . . . . Ih-1 14.1.2 ANALYSIS OF EFFECTS AND CONSEQUENCES . . . . . . . . . lk-3 lb.2 STANDBY SAFEGUARDS ANALYSIS . . . . . . . . . . . . 1h-20 14.2.1 SITUATIONS ANALYZED AND CAUSES . . . . . . . . . . . lh-20 14.2.2 ACCIDENT ANALYSES . . . . . . . . . . . . . . . 1h-21
14.3 REFERENCES
. . . . . . . . . . . . . . . . . . 1k-57 15 TECHNICAL SPECIFICATIONS . . . . Volume 3 . . . Tab 15 . 15-1 D
(G vi (Revised 1-15-68) ()302 m = =
- M-p TABLE OF APPENDICES Appendix 1A . TECHNICAL QUALIFICATIONS . . . . . . . . Appendicea . . . . . Tab 1A 2A POPULATION AND -LAND USE . . . . . . . . Appendices . . . . . Tab 2A 23 METEOROLOGY . . . . . . . . . . . . . . Appendices . . . . . Tab 23 2C FLOOD STUDIES AND HURRICANE EFFECTS . . Appendices . . . . . Tab 2C 2D RADIOACTIVE LIQUID WASTE DISCH!.RGE LIMITS . . . . . . . . . . . . . . . . Appendices . . . . . Tab 2D 2E ' GROUNDWATER . . . . . . . . . . . . . . Appendices . . . . . Tab 2E 2F - GENERAL GEOLOGY--REGIONAL TECTONICS . .-Appendi:es . . . . . Tab 2F 2G ENGINEERING GEOLOGY AND FOUNDATION STUDIES. . . . . . . . . . . . . . . . Appendices . . . . . Tab 2G 2H BEDROCK SOLUTION STUDIES . . . . . . . . Appendices . . . . . Tab 2H 2I SEISMOLOGY . . . . . . . . . . . . . . . Appendices . . . . . Tab aI SA STRUCTURAL . . . . . . . . . . . . . . . Appendices . . . . . Tab SA 53 DESIGN PROGRAM FOR REACTOR BUILDING . . Appendices . . . . . Tab 53 5C DESIGN CRITERIA FOR REACTOR BUILDING . . Appendices . . . . . Tab SC SD QUALITY CONTROL . . . . . . . . . . . . Appendices . . . . . Tab 5D SE LINER PLATE SPECIFICATION . . . . . . Appendices . . . . . Tab SE 5F REACTOR BUILDING INSTRUMENTATION . . . . Appendices . . . . . Tab 5F SG TURBINF-GEllERATOR MISSILES . . . . . . . Appendices . . . . . Tab SG t 12A
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- FLORIDA PUBLIC SAFETY EMERGENCY PROCEDURES . . . . . . . . . . . . . . Appendices . . . . . Tab 12A Supplement 1 Response to DRL letter, 1-19-68. . . . . Volume 4 . . Supplement No. 1 2 Voluntary Response to AEC Oral Inquiry . Volume h . . Supplement No. 2 3 Voluntary Response to AEC Oral Inquiry . Volume h . . Supplement No. 3
'h Response to DRL letter, 3-13-69. . . . . Volume h . . Supplement No. k 5 Response to.DRL letter, 11-8-69. . . . . Volume 5 . . Supplement No. 5 6 Response to DRL letter, 11-8-69. . . . . Volume 5 . . Supplement No. 6 (p
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