ML20085C508
Text
. . - - . . - . - - . .
. , . 4 t
g
- k. . ' w g' 'j*
l
,1,)y j
t i
}
APPLICATION TO U.S. ATOMIC ENER0Y COMMISSION .
FOR REACTOR CONSTRUCTION PERMIT AND )
OPERATING LICE!GE ,, .
. ~b FINAL SAftDUARIC REPORT
. . (3., ,, _ d3 0 O L sa --- -- ~
' -, 3.
- s. ....,.na r~Y .
k- "
94 t
a s
,h l}[
p k
h i
\f\ '
eq- /.
~s) ,. 'd'/ '
1 911002O?99 910424 PER FOIA DEKOK91-17 PDR '
CopyTurnished Lied alice i
t-3 POREVORD This report has been prepared as a part of the Sarton Nucitar Experimental Corporation Application to the U. S. Atcznic Energy Ccamnission for a construction permit and operating license for a 20 thennal megavatt reactor facility Application an: that is being constructed at Saxton, Pennsylvania. The on July 24, 1959 1 Prelimin**y HarArds Summary Report were filed with the AEC 11, 1960. and Ccasi;ruction Permit No. CPPR-6 van issued on February This report has six sections which are as follows:
Section 100 - Description and Characteristics of Site i Section 200 - Description of Facility Section 300 - Description of Operations Section 400 - Hescarch and Development Program Dection 500 - Accident Analysis Section 600 - Itatania Analysis -
Thenecessary.
as zmport has loose-leaf pages which can be amended, replaced, or added to b Each ,page is dated in the lover left-hand corner of the page and asterisks along the left edge of the paper show the lines or paragraphs i vLere the last revisions vern made.
In submitting this report to the AEC, 3axton Nuclear Experimental
.]s*
! k. Corporation has requested an initial operating license covering only the startup,progrsa described in Subsection 405 and Subsections 308 and 309 of up toreport, the including its rated power of operaticn 20 MWT.of the reactor at successive power icvels While the report includes a general dcseription of the entire post-construction IED program as presently planned i for a five-year period, authorization vill be requested at t. later time by i
amendment subsequent totothe the license startup application for phases of the experimental program program.
and report vill be amended frcan time to time in order to obtain license re-I visions for performing later phases of the IED program.
! that th.re vill be many changes to Sectioml00 and 200 which pertain to theIt is not h site an4 the reactor design for operation up to the ncaninal power level of 20 Wr, but rather that the other sections vould be amended as necessary to vided te in the initial operating license.take cab of that portica of th o pro-o D-4 1
6/61 i,{
, - - ~ ~ ~
A_CffGPJNTS While the preparatierpio report has been the direct responsibility of the applicantcon Nuclear Experimental Corporation (SNEC); both Westinghouse Electtrporation, as the prime contractor and a project participant; and tt Associates, Inc. (OAl), as the Engineer-Constructor, deserve carable cr,cdit for the contributions thet they have made. Westinghopd GAI were particularly helpful in supplying the necessary syste.m t.ptions for preparing Section 200 -
Description of Facility and in ping plant and system operating information for Section 300 - 0;on. Since Westinghouse has the responsibility for initiating arrying out the resear:h and deyelop-nerrt program, t, hey supplied thetsary information for Section h00 -
Research and Development Prograsstinghouse was also very helpful in offering advice and performing talytical work for Section 500 - l Accident Analysie and Section 6Cazards Analysis. !
SNEC, with assistance *,eneral Public Utilities System personnel and outside consultar.tepared all the material in Section 100 - Description ard Characteri of Site, Tne SNEC staff aisc prepared most of the material inton 300 - Operation, except for the eqaipment operating instructionsexperimental procedurce, whi:h were supplied by both Westinghouse ad The SNEC staff would a.ke to acknowledge the valuable assistan:e received from numerot,viduals in the Wettinghoust Atomic Fower Department, Gilbert Associ.lnc., the Metropoljtan Edison Company, and the Pennsylvania El' Company ir. the preparation of the many figures, tables, and dap. We are also especially gratefu; to Mrs. Dorothy Klopp, Miss Jant.ey, and otherr who spent many long hours typing, retyping, cot and paying particular attention to the fo:7.at and consistency eyeport, w
SNEC STAFF i
l 1
1 1
i P
\
)
1 L/7/61
TABLE OF CONTENTS
-Pace lio.
ACKNOWLED'JMENTJ ................................................... 11 LIST OF FIGURES ..................'................................. xi-xiii -
SECTION 100 - DESCRIPTION AND CHAIMCTERISTICS OF SITE 101 - L o c at i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 01.3 102 - Topography ............................................. 1 02.1 103 - Meteorology A. Gene ral Area Climatology . . . . . . . . . . . . . . . . . . . . . . . . . . 103 1 B. Loc al Fl ood s and S t orms . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 1 C. Meteorological Instrumentation . . . . . . . . . . . . . . . . . . . . 103 1 D. Local Climatology ................................. 103 1 E. Pollution Climatol ogy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 2 F. Diffusion Estimates ........-...................... 103 8
- 0. Conclusions ....................................... 103 9 l
10k - Land U s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 04.1 105 - Populat i on De ns it y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105 1 106 - G e ol ogy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106.1 107 - S e i s m ol ogy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 107 1 w
108 - Hyd rol ogy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108.1 109 - Radi ologic al S u rvey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109 1 SECTION 200 - DESCRIPTION OF FACILITY l
201 - General Features A. Pl an t Lay out . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 201.1 B. Containment Ve ssel Arrangement . . . . . . . . . . . . . . . . . . . . . 2 01 .1 C. Control and Auxiliary luilding Arrangement . . . . . . . . . 201.2 D. Radioactive Waste Treatment Plant Arrangement . . . . . . 2 01.2 F. Existing Station Arrangement . . . . . . . . . . . . . . . . . . . . . . . 201 3 202 - Flow Diagrams ........................................... .
202.1
(
203 - Core ,
1 A. General ..... ....................................... 203 1 B. Fuel Assemblies .................................... 203 2 h/3/61 C. S uppo rt S t ruc ture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 203 4 11-
l Page No.
203 - Core (Continued)
D. Control Rods and Drive Mechanicms . . . . . . . . . . . . . . . . . . 203 5 E. Re ac t o r Phyc ic o C al c ulati ons . . . . . . . . . . . . . . . . . . . . . . . 203.8 F. Core Chnracteristics ..................... ......... 203 11
- 0. Nuclear Inst rumentation and Control . . . . . . . . . . . . . . . . 203 13 204 - Main Coo] ant System A. G e ne ral De s c ri pt i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 04 .1 B. Reactor Vessel ..................................... 204.2 C. S t e am Ge ne ra t o r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 204 3 D. Main C oolant Pum p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 04.4 E. Coolant Piping and Fittings ........................ 204 5 F. I n s t rume nt at i on and C ont rol . . . . . . . . . . . . . . . . . . . . . . . . 2?k.5 205 - Pressure Control P.nd Relief System A. Function ........................................... 205 1 B. Description ........................................ 205 1 C. Ca ponents ......................................... 205 2 D. Ins t rumentat i on and C ont rol . . . . . . . . . . . . . . . . . . . . . . . . 205 4 E. Desi6n Basis ....................................... 205 5 206 - Cnarging Sys'em A. Function ........................................... 206.1 B. De s c ri pt'l on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 206.1 C. Components ......................................... 206.1 D. I ns t rume ntati on and C ont rol . . . . . . . . . . . . . . . . . . . . . . . . 206.2 i E. Design Basis ....................................... 206.2 1
207 - Purification System w
A. Function ........................................... 207 1 i B. De s c ri pt i on . . . . . . . . '. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 207 1 l C. Ccmponents ......................................... 207 2 l D. Inst rumentation and Control . . . . . . . . . . . . . . . . . . . . . . . . 207.4 l E. Design Basis ....................................... 207 4 208 - Camponent Cooling System A. Function ........................................... 208.1 B. Description ........................................ 208.1 C. Camponents ......................................... 208.1 D. Instrumentation and Control . . . . . . . . . . . . . . . . . . . . . . . . 2 08.2' l E. Desi6n Basis ....................................... 208 3 l
209 - Chemi;al Addition System
(
A. Function ........................................... 209 1 l B. De s c ri pt i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 209 1 C. C am pone nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 209 1 D. Ins t rumentation and Contro_ . . . . . . . . . . . . . . . . . . . . . . . . 209 1 4/3/61 E. Design Basis ....................................... 209 2 iii
- - - - , w-- -y- -
m y e,--y_mg, e-mm -, ,,, rv wqy w w,w r, 4ns 4
Page No.
/ 210 - Sampling and Leak Detectiotyctem A. h etion .........................................
210.1 B. D e s c ri pt i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 210.1 C. C crn pone nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 210 3 D. Instrumentation,and Carol . . . . . . . . . . . . . . . . . . . . . . . 210 3 E. Design Daois ........L............................ 210.4 1
211 - Shutdovn Cooling System A. Punction .........................................
211.1 B. Description .........p............................ 211.1 C. Camponents .......... ............................ 211.1 D. Inst rumentation and C . col . . . . . . . . . . . . . . . . . . . . . . . . 211.1 E. Design Basis ..................................... 211.2 212 - Safety In,$ection System A. N etion ....................................... . 212.1 B. Description ...................................... 212.1 C. C ampone nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 212.1 D. Instrumentation and Corol ........................ 212.1 E. Design Basis ..................................... 212.2 213 - Storage Well System A. Function ......................................... 213 1 B. Description .-.................................... 213 1 C. Camponents ....................................... 213 1 D. In s t rume nt a ti on and C or ol . . . . . . . . . . . . . . . . . . . . . . . . 213 2 E. Design Baciu ..................................... 213 3 Elk - Cooling, Heating, and Ventiling Systems A. Function .............i........................... 214.1 l
B. Contninment Vessel CooMg, Heating,and Ventilating. 21k.1 l
C. Vaste Treatment Plant JLting and Ventilating ...... 21k.3 1 D. Control and Auxiliary Elding Heating I and Ventilating .. 6........................... '21k.4 E. Instrument and Control . . . . . . . . . . . . . . . . . . . . . . . . . . . 21k.4 215 - Vents and Drains System +
A. Function ............. . . .. . . . . . . . . . . . . . . . . . . . . . . . . 215 1 B. Description ...................................... 215 1 216 - Secondary Steam Cycle ,
i A. D e s c ri pt i on . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 216.l'
( B. Design Basis .........'............................. 216.1 C. Instrument and Control ............................ 216 3 4/3/61' iv
--P --ev -
r+ --
w--* --p----r- e y er -ce =c-w- -g - % er -c-r e-r---- -m- '--
- 'rv? - w - e'--
-- - ~ - . - - - - . - _ - - - . . . _ - . . . . _ - _ - _ - _ - - - . - . - _ . . _ _
Page No.
217 - Water Treatment Systems A. Main Coolant System ................................ 217 1 B. Secondary Steam System ............................. 217 1 218 - Station Service Electrical System A. Function ........ .................................. 218.1 B. General Description ................................ 218.1 C. G e n e ra t o r Bu s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 218.1 D. Reac tor Plant Elect rical Service . . . . . . . . . . . . . . . . . . . 218.1 E. Main khO V Reactor Burses .......................... 218.2 F. Pressurizer Heater Control Center . . . . . . . . . . . . . . . . . . 218 3 G. Motor Control Centers No.1 and No. 2 . . . . . . . . . . . . . . 218 3 H. Lighting Bus ....................................... 218 3
- 1. Eme rgency 120-208 V Tran s f ome r . . . . . . . . . . . . . . . . . . . . 218.h J. WDF Mot or Cont rol Center . . . . . . . . . . . . . . . . . . . . . . . . . 218.4 K. Safety Injection Pumps Supply . . . . . . . . . . . . . . . . . . . . . . 218.4 L. Bat te ry Cha rge r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 218.4 .
M. Inverter Bus and Vital Bus Supply . . . . . . . . . . . . . . . . . . 218 5 . - ---
N. Main O oolant Pump Supplie s . . . . . . . . . . . . . . . . . . . . . . . . . 218 5 O. Emergency L16hting ................................. 218.6 y/ 210 - Radioactive Waste Disposal Facility A. Introduction ....................................... 219 1 B. Solid Waste Disposal System ........................ 219 1 C. Liquid Waste Disposal System ....................... 219 2 D. Gaseous Waste Disposal System ...................... 219 5 E. Instrumentation and Control ........................ 219.6 F. De s i gn C ri te ri a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 219 7 s 220 - Radiation Monitoring System w A. Function ........................................... 220.1 B. De s c ri pt i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 220.1 C. Design Basis ....................................... 220.2 D. Camponents ......................................... 220.2 V 221 - Shieldin6 A. General-............................................ 221.1 B. Neutron Shield ..................................... 221.1 C. Prima ry Shi eld . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 221.1 D. S e c ondary Sh i eld . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 221.1 E. Fuel HandlinC Shield ............................... 221.2 P. Auxiliary Shield ................................... 221.2 G. Design Basis ....................................... 221.2
( ,/ 222 - Fuel Handling A. General ............................................ 222.1 B. Reactor Campartment and Stcrage Well . . . . . . . . . . . . . . . 222.1 C. Fuc1 Handling Tools and Equilnent . . . . . . . . . . . . . . . . . . 222.1 Ih/3/61 ,
V 1
t
-- , -- - - .- = - , - - _ . -, . - . - -- - - ---- _
--- - - - . ~ . - - - . - - - . - . . . _ _ - - -. _- .. . - - -..- - - . .
Page No.
223 - Containment 1 A. General ............................................. 223 1 B. Design Pressure ..................................... 223 1 C. De s i gn Fe a t u re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 223 2 SECTION 300 - DESCRIPI' ION OF OPERCIONS 301 - Organization A. General .............................................. 301.1 B. Nuclear Plant Organi zation . . . . . . . . . . . . . . . . . . . . . . . . . . . 301.1 !
.C. Traininj, ............................................. 301 3 302 - Administrative Policy and Procedurco A. Records ............................................. 302.1 B. Supervision ......................................... 302.1 C. Identification ............................. ........ 302.2 D. Switching and Valving ............................... 302.2 303 - Radiation Protection A. General ............................................. 303 1 B. Are a C ont rol . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 303 1 !
C. Personnel Protection and Control .................... 303 3 i D. Radioactive Material Control .....~................... 303 6 E. Radiation Incidents and Emergency Procedures . . . . . . . . 303 10
]
304 - Plant Erection, Innpection and Preoperational. Checkout l A. Equipment Specifications and Manufacturers ' Test % . . 304.1 B. Inspection and Insta11atun of Equipment in the Field 304.1 C. Preoperational Checkout of the Secondary Plant ...... 304.2 ,
D. Preoperational Checkout of the Nuclear Plant ........ 304.2 l
305 - Nomal Operating Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 305 1 1
3 06 - Eme rgenc y Proc e d ure s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 306.1 307 - Maintenance .............................................. 307 1 l l
308 - Initial Core Loading and Lov Power Core Tests '
A. General ............................................. 308.1 B. Special Instrumentation ............................. 308.1 C. Initial Core Loading and Installation of Internals .. 308.2 l D. Control Rod Drive and Plant Scram Test .............. 308 3 1
( E. Initini Criticality (Banked and Programed Rods) . . . . 303.4 j F. Control Rod, Boron, Flov and Void Worth Detemination '
at Ambient Temperature ........................... 308.4 h/3/61 vt
- - . - - -- - . - - . - . - - - . - . - - - - - _ - - . -~ ,
Pare No.
303 - Jnitial Core Loading and Lov Power Core Tests (Continued)
O. 'lemperature and Pressure Coefficient at Shutdovn Boron Concentration ............................... 303 5 H. Control Rod Worth, Baron and Flov Vorth at Operating Tempe ra ture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 308 5
- 1. Temperature and Pressure Coefficient Detemination at Lov Boron Concentration ........................... 308.6 J. Instrumentation Response at Lov Pover ................ 303.6 309 - Initial Power Operational Tests A. General .............................................. 309 1 B. Power Coefficient Measurements ....................... 30).1 C. Loss of Load Transient Tests ......................... 309 2 D. Calibration of Nuclear Plant Instramentation System and Primary - Secondary Calorimetry . . . . . . . . . . . . . . . 309 2 E. Pission Product Effect on Reactivity Following Power inc re as e and/or De c re as e . . . . . . . . . . . . . . . . . . . . . . . . . . 309 2 F. Biological Shielding Effectiveness Test .............. 309 2
- 0. Instrumentation and Control Response ................. 309 3
- 310 + Ch emi c al Shim Te s t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 311 - Spiked Element Tests ..................................... *
- 312 - Bulk Boiling' Tests and Increased Specific Power Te:ts . . . . *
'
- 313 - Boiling Water Operation Tests ............................
- 314 - Nuclear Superheat Loop Te st s . . . . . . . . . . . . . . .~. . . . . . . . . . . . . .
- l*
w I
l SECTION 400 - RESEARCH AND DEVEL0lV.ENT PROGRAM 401 - General A. Purpose .............................................. 401.1 B. Technical Safeguards Control ......................... k '1.1 402 - Pre-0;wration Desi6n and Development Program i
A. General .............................................. 4 02.1 B. Core Design .......................................... 402.1 C. Puel Assembly and Control Rod Follover Development ... 402.1 D. In-Core Instrumentation Design ....................... 402.2 l E. Modifications in Reactor Vessel . . . . . . . . . . . . . . . . . . . . . . 402.2 l F. Evaluation of Soluble Neutron Poisons . . . . . . . . . . . . . . . . 402 3 1
- Subsections not included with initial report. Hay be subnitted in future as amendments.
4/7/61 'y vii
Page No.
LO3 - Post-Construction Research and Develoinent Program A. General ............................................. 403 1 l B. Scope ............................................... 403 1 i 404 - In-Core Instrumentation A. Gene ral De s c ription . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 404.1 B. Mechanical Support Structures and Seal Assemblies . . . 404.2 405 - Startup Program l A. General ............................................. 405 1 B. Benctor Critical Experimente ........................ 405 1 C. Measurement of Core Behavior During Stepwise Approach to Full Pover .................................... 405 1 D. Steady State Measurements ........................... 405 1
- 406 - Reactivity Control DeveloInent . . . . . . . . . . . . . . . . . . . . . . . . . .
407 - Puel Development ........................................
- 408 - Pushed Pres surized Water Operation . . . . . . . . . . . . . . . . . . . . . .
- s
- kO9 - Boiling Water Operation ................................. *
- klo - Ocuponent and System Develoinent . . . . . . . . . . . . . . .........
- SECTION 500 - ACCIDENT ANALYSIS ,
501 - Genera 1 ...................................... ..... m... 501.1 502 - Possible Causes of Accidents A. Introduction ........................................ 502.1 B. Acts of God ......................................... 5 02.1 C. Fire ................................................ 502.2 D. Sabotage, Riots, Strikes, Acts of War .............. 502.2 E. H uman E rror . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
502 3 T. Failure of EquiInent or Controls . . . . . . . . . . . . . . . . . . . 502 3 503 - Reactivity Accidents A. General ............................................. 503 1 B. Uncontrolled Rod Withdrawal at Startup .............. 503 2 C. Uncontrolled Rod Withdrawal at Power ................ 503 4 D. Uncontrolled Heat Extraction by Steam Plant Valves
( or Rupture ....................................... 503 5 E. C old Wat e r In t roduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 503 7
- Subsections not included with initial report. May be subnitted in future as amendmente.
i 4/7/61 l viii l
_. __ . _ _. _ ~ _ __
Page No.
503 - Reactivity Accidents (Continued)
F. Loss of Chemical Neutron Absorber .................... 503 7
- 0. Xe n on Bum out . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 503 8 H. Conclusion ........................................... 503 8 50k - Mechanical Accidents -
A. Loss of Coolant ...................................... 504.1 B. Loss of Coolant Flov ................................. 504 3 505 - Missile Protection ....................................... 505 1 506 - Pressure Duildup in the Vapor Container . . . . . . . . . . . . . . . . . . 506.1 507 - Experimentd. Considerations A. General .............................................. 507 1 B. Boric Acid Concentration Requirement and Power Operation with Chemical Shim Control .............. 507 1 C. Inc reased Power ExIeriments . . . . . . . . . . . . . . ......... 507 2 D. Startup vith Reactor Heat . . . . . . . . . . . . . . . . ........... 507 2 E. Advanced Fuel Element Experiments . . . . . . . . . . . . . . . . . . . . 507 3 F. Boiling Expe riment s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 507 3
, G. Nuclear Superheat Experiment . . . . . . . . . . . . . . . . . . . . . . . . . 507 3 503 - Definition of. Maximum credible and Maximum Hypothetical Accident ............................................... 508.1 SECTION 600 - HAZARDS ANALYSIS .
601 - General .............................................w.... 601.1
- 602 - Accident Assumptions for an Upper Boundary of Hazards . .. . 602.1 l
l 603 - Fission Products Released to Containment Vessel . . . . . . . . . . 603 1 I
l 604 - Containment Vessel LeakaBe ............................... 604.1 605 - Meteorological Conditions and Diffusion .................. 605 1 j 606 - Direct Radiation ......................................... 606.1 g/ 607 - Air-Bome Radiation A. General ...................................... ....... 607 1 B. External Dose frcan Air-Borne Radiation . . . . . . . . . . . . . . . 607 1 C. Inhalation Dose ...................................... 607 1
(
608 - Deposition or Washout .................................... 603.1 h/7/61 ix
Page No.
- 609 - Maximum Credible Experimental Accident .......... .......
610 - 11a za ris Evaluati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 610.1 4 611 - Major Experimental Accident }{a:,ards Evaluation . . . . . . . . . .
- 612 - Conclusions ............................................. 612.1 w
I i
l t
l
\
l l
l t
- Subsections not included vith initial report. May be submitted in future
, as amendments.
gj7jg X
l l
LIST OF FIGUPIS l
Figures appear in the report at the end of the indicated sectiens. l l
Figure Section Number T,itle 101 1 Site Location of the Saxton Reactor 2 Property Map - Saxton Steam Generating Station 3 Aerial Photograph of the Reactor Site 102 1 Geologic Survey Map of the Reactor Site 103 1 Percentage Frequency at Station "A" 2 Percentage Frequency at Station "B" 3 Stable Condition Wind Rose 4 Stability Wind Rose 105 1 Radial Population Distribution - 10 Mile Radius l 2 Saxton Power Station and Vicinity l 3 Radial Population Distribution - 4000 Foot Radius 106 1 Test Hole Data 108 1 River Flow - Saxton Gaging Station 201 1 General Plan-Yard Layout i 2 Artist's Conception Saxton Nuclear Facility 3 Floor Plans - Elevation 765'8" and 781'4" h Floor, Plans - Elevations 795'2", 812'0" and 818'0" 5 Sections A-A and B-B 6 Sections C-C and D-D 7 Control & Auxiliary Baiiding Architectual Plans 8 General Layout of R.W.D.F. - Waste Treatment Plant 202 1 Piping - Main Flow Diagram %
2 Piping - Main Flow Diagram Instrumentation 3 F1 ping - Miscellaneous Flow Diagram 4 Piping - Miscellaneous Flow Diagram Instrumentation 5 Piping - Services Flow Dia; ram 6 Piping - Services Flow Dia6 rem Instrumentation 203 1 Fuel Assembly and Control Rod Cross Section 2 Core Cross Section 3 Reactor Vessel Assembly without Core Instrumentation 4 Reactor Vessel Assembly with Core Instrumentation 5a Control Rod - Absorber Section 5b Control Rod - Follover Section 6 Control Rod Drive Mechanism 7 Block Diagram - Nuclear Instrumentation System 8 Block Diagram - Reactor Control System 9 Schematic Diagram - Rod Control 10 Schematic Diagram - % d Position Indication 4 11 Control Roam Iayout 3/29/61 .
x1
. _ _ _ _ . . - - - _ . _ . ._ _ . . _ _ _ _ - _ _ . _ _ - . _ _ _ _ _ _ _ _ . _ _~
Figure Section Number Title 1 20k 1 Flov Diagram - Primary slant System 2 Reactor Vessel Cross St tion 3 Steam Generator 4 Dual Gasket Design 5 Westinghouse Canned Motor Pump 205 1 Pressure Relief System 2 Pressurizer 206 1 Flov Diagram - Charging System 207 1 Purification System 208 1 Ceeponent Cooling System 209 1 Flow Diagram - Chemical Addition System 210 1 Sampling and Leak Detection System 211 1 Flow Diagram - Shutdown Cooling System 212 1 Flov Diagram - Safety Injection System 214 1 Schematic Flow Diagram - Containment Vessel Cooling and Ventilating System 2 Building Service Air Flow Diagram 3 Air Flov Diagram - Control and Auxiliary Building 215 1 Vents and Drains System 218 1 One Line and Relay Diagram, Generatioh and Station Service 219 1 Piping - Waste Disposal Flow Diagram 2 Piping - Waste Disposal Flow Diagram Instrumentation 220 1 Block Diagram - Radiation Monitoring System 223 1 Electrical - Conduit Details - Containment Vessel Cable Penetrations - M.I. and Coaxin3 Cables 2 Electrical - Conduit Details - Containment Vessel Cable Penetrations - Lead Covered Cable 3 Electrical - Conduit Details - Containment Vessel Cable Penetrations - Strain Gage and Thermocouple Leads 301 1 Saxton Nuclear Project Organization Chart 403 1 Saxton Post Construction R and D Program 404 1 Core Cross Section - Proposed Location Thimbles and Core
( Outlet Instrumentation 2 Proposed Location - Core Inlet Instrumentation 3/29/61 xii
t Figure Section Number Title 503 1 Reactor Power Level Respogse Resulting frczt a Ramp ChanEe in Reactivity of 5 x 10' 4 X/sec.
- 2 Reactor Power Level Responpe Resulting frcn a Ramp Change in Reactivity of +5 x 10*'+d K/sec.
3 Maximum Fuel Temperature Rgsulting from a Ramp Change in Reactivity of +5 x 10' 4K/sec.
4 Reactor Pover L& vel Response Resulting frcra a 0.034 Square Foot Ductile Rupture of the Secondary Steam Dome 504 1 Loss of Coolant Accident - Nomal Operation at 20 MwT -
Safety Injection by Two Pumps 2 Loss of Coolant Accident - Nomal Operation at 20 MwT -
Safety Injection by One Pump 3 Loss of Coolat? Accident - Nomal Operation at 20 MwT -
No Safety Injection l
4 Flow Coast Down and Transient Heat Flux l 506 1 Instantaneous Release of Main Coolant - Containment Vessel i
Pressure vs Time 606 1 Direct Gamma Radiation - Dose Rate vs Distance from Containment Vessel 2 Direct Gamma Radiation - Integrated Dose vs Distance from Containment Vessel 607 1 Iodine - Integrated Thyroid Dose vs Distance fram Containment Vessel t
3/29/61 s 0 xiii
I l
SECTION 100 DESCRIPTION AND CIUJtACTERISTICS OF SITE 101 LOOATION 102 TOP 00RAPliY 103 METEORO100Y 10h LAND USE 105 POPULATION DENSITY 106 OEOLOGY 107 SEISMOLOGY 108 HYDROLOGY 107 RADIO 1001 CAL SURVEY t
O O
i I
f 3/1h/61
- ,~ _ _ _ _ _ _ _ . _ . _ .. _ _._ _ _. .
101..
101 - LOCATION The site is located ebout 100 p'les east of Pittsburgh and 90 miles vest of Harrisburg in the Allegheny Mountains, three fourths of a mile north I of the Borough of Sexton in Liberty Township, Bedford CJanty, Pennsylvania.
The general location of the site in south central Pennsylvania with respect 1 to Altoona and Huntingdon is shown on Figure 101-1. The site is on the north s'.de of Pennsylvania Route 913,17 miles scuth of U.S. Route 22, and about 15 miles north of the Breetevood Interchange of the Pennsylvania Turnpike.
The nuclear facility is being built on the east side of and adjacent to the Saxton Steam Gene *% 1ng Station of Pennsylvania Electric Company.
This station is located on the east bank of the Baystown Branch of the Juniata River as shown on property map, Figure 101-2. The property comprises
- approximately 150 ac ms. A small plot of land, consisting of 1.148 acres on ,
'which the reactor facilit/ is located, hr s been deeded to Saxton Nuclear Experimental Corporation (SNEC) by the Pennsylvania Electric Company. A recent aerial photograph of this property is shown on Figum 101-3 This photograph was made with the camera facing a south'vesterly direction. The ,
small adjacent communities (see Figure 105-2) can be seen in the background. , !
The primary features of the existing statico am shown on Table 101-1.
TABLE 101-1
, PRIMARY FEAWRES - SAXMN STEAM CENERATING STATION
\
Owner Pennsylvania Electric Company, Johnstown, Pennsylvania Plant Capacity Nominal capacity 50,000 kv; mariana capability, 64,000 kv.
Turbine Generators No.1 unit - 10,000 kw ncminal capacity (13,000 marimum capability),
single casing, 1800 rpm, non-extraction, condensing unit. Full load steamrate12.4lbc/kvb.
No. 2 unit - same as unit No.1, except full lead steam rate of 117 lbs/kvh.
No. 3 unit - 30,000 kw nominal capacity (38,000 maximum capability),
single casing,1800 rpa, extmetion, coedensing unit with 3 stages of extraction for feedwater heating. Fullloadsteamrate11.0lbs/kvh.
House unit - 937 kv, 3600 rim, back pressure unit (2 pais) for statica g
auxiliary supply or backup.
S*2am Cceditions l At all turbines, 285 Paig Pressum ,'6300F total temperature, total steam flow to turbines - approximately 750,000 lbs/hr.
l L . . _ _ -. _ . _ . .--. _ _ _ _ _ -_ ___ _-.__ _-- - -
-- ._- - -- - .- __ . ..- =. - ._ ..-. - -. .--.
101.2' Turbine Plant Auxiliaries Cct::plete condensing, feedvater, and other supporting systems are in active service.
Boiler Plant Eight (6) existing stoker fired Sterling type bof.lers ans. supporting auxiliaries.
Ele $trica3 Facilities 3
Co=plete station electrical facilities. Two_(2) cf the three (3) !
115 KV trancmission lines which emanate from the station are connected to the Pennsylvania Electric Company 115 KV transmission syctem wh'.ch has numerous other power sources. One of the 115 KV transmission lines is a radial feeder line serving the Bedford area.
Saxton stati(n is also one of the terminals of 13-mile long A60 KV experimental line that could be used as a backup in an emergenc;y.
A 23 KV transmissioniline that leaves the station from a different direction could also be used as a backup in an emergency.
O t'
-/5/61-
, !t j '
' ), , ' ;b1 '
.7 '!T
, I d' ' "'s
'~^),91')lV> 7 $ % if ~
dbb '
h ?"l<
- " "'t 4
'w=fj:&,!il g.w:,
- %,, -%%gja/s0.f g 4 .g/.
9 y. ?,,:d> g.$ -
- gQQ G>.if . ,
p\,v -"r, %n b, )II
,y~ , , . /6 ,$
V .
h ' '
?;qjh % V$%if %)
f .,
- l. !
?v "
w *. / .
? J' hf 'U;h5 :- )pm'"gry%m :g.
,e'
,b ?
g gy'n
,4- , ~.
e
- .h"M W sf fib O v R'$ #fq't 4y'MYh i ,1 4
- jy' ., I n ' sl& 4 .f .2v;&Y>ht?% Dy
}&
, ,a ,
j fY , . / >> '
T 'Y,,$ .
j,
} ,. *'*"*"'~ \ T I'< ? ,: -
$ h,1)ffhQ { '
'} ( k {. :f ,,{ j ,hj,b A \ 1. %( 2 p g gl y u :, g7%::;3+,.
w f.(; fi4 * *' d: ' n' a
- ' i4,. ,. / 1f J'5 N d];'6Mt.f b .J ,
@ 'l g, .
ll 5 .
$0=kff'i Y ; l a- i>f ff.%p4:240, f we%Emm:A ff I L
, %%t%:
Scale-1:250,000 -
1 Site location of the Saxton Reactor TIGUIE 101-1.
---_-_:__=_ :-- . _ _ - . _ _ .
Js-u--m--hLwJ=4.--h,#M4L-Ay ---a--JLa.-,a4L- w Apr--J.- i GW.h4 e6 .6,me_
- a-- .a -,,4.=ceA.mhdMaM..-4-4mw@e u 6F Mas _-WaS a. 4 . 434.W_W.J11M (ape,Jie e. h134 .s.A J s.3,J .JS_.., 3 mrJL 't-Aa J 44 m44*N=44--b A m AAa W OA 4 0
P d/\u;
/ bl.?y W::
l 'jh.)!,! .
%,,, CONTAINMENT
'i f VESSEL lx _
r
En e
f dA '
d' o
he , >
I' lu' I
/Iq'ig q j' ,
j l
a!
't
. p C l ,s'!
. ,o
\
s, ri.
/
w
'y$\
x nw vwmnr y i to 4
. g s.
g
\ ,
t
\ m i
E Euc PROPERTY LINE
/ ~
g N
N g
(
....s.... ,
~
(_
FIGURE 101 kl5/61- .
, ~ , . .,. , .---
% y-.. y , , , , , , -,..,,-,-.ymem..,,,w,w
,M',,,,,, u,a,. .,v,,. g --.w.,,_
. ,, .._g...~,,-+-,,,e - . - , - . , .o. c.vg,-,-.., yw, w _p- , , ,
,a . . ..
g.
- h ;.E;
. ;;: d; y
,, El-, , ' <f N ,. $
9.y. .
p .- f
\
o_x, ac.,5 u 1 .
f-3"
< r ,. - >- c .
DenJ4G' <
1!
!g h,et j-nL. l.
e, j
m#:w,..
< , :% m,g - , e 3 ', .
c$ ,i q t >. g. 3 v..s ip*p t.
i t 3
g Qt ,
j C '. >
g
< ,i g~g p
.a' ~ - .
f, f .1 .
u...;f-
.; e
') ;
3 b
+ %W l . 3g&jf..
FIGURE 101-3
102.:
102 - TOP 03RAPHY The site is in the valley of the Raystown Branch of the Juniata River which meanders in a general direction from south southwrut to north northeast. The river valley lies between Tussey Mountain to to west and Terrace Mountain to the east, as shown on topographic map Fip ce 101-1.
It is located in the northwest en corner of the Broad Top Quadrangle of the U.S. Geological Survey map. At Saxton, the river is normally at an elevation of about 79h feet with the site on gently sloping land about 17 feet above the river level. The ridges immediately to the northwest of the site rise to 1300 feet and to the southeast, they rise to 1500 feet, as shown on Figure 102-1.
t 0
l l
I l
?/2h/61-
! I >
h i$i ihk,oypAe$hj muse 3 1
xraeuaak l .
t I
Scale 1:62,500 l
Geologic Survey Map of the Reactor Site
!"_'TJFE 102-1 1
103..
103 - METEOROLCGY A. General Area Climatology The general area climatology of the south central Pennsylvania area in which the Saxton site is located was described on pages 2-1 and 2-2 of the Saxton Nuclear Experimental Corporation (SNEC) Preliminary Hazards Summary Report.
B. Local Floods and Stoms Local floods and stoms in the Saxton site area are discussed on page 2-3 of the SNEC Preliminary Hazards Summary Report.
C. Meteorclogical Instrumentation A micrometeorological network has been set up and operated at the site fo2 the past year. Data frcn this network hwe been used to establisn estimates of disper-ion and diffusion characteristics of the site.
The micrometeorological network consists of three stations. These stations hace been designated as Stations "A", "B", and "C". Station "A" con-sists of a 35-foot vooden pole .atructure located 738 feet east of the con-tainment vessel center and includes the following instrumentation:
- 1. One resistance themameter bulb in an aspirated enclosure mounted at an elevation of 056 feet (45 feet above site grade level) and associated temperature stripchart recorder.
- 2. One vind di,rection and velocity anemometer with special six-bladed rotor to provide a starting speed of 2 mph mounted at an elevation of 860 feet and associated vind direction and velocity strip chart recorder.
Station "B", having the same type of instrument'ation as Station "A",
is mounted on a 55-foot wood pole structure atop a hill 3219 feetworthwest of Station "A". The resistance themometer bulb of Station "B" is located at an elevation of 1396 feet (540 feet above Station "A"). The anemometer at Station "B" is located at an elevation of 1406 feet.
Station "C" is located approximately 1000 feet vest of Station "A".
At this station vet and dry bulb temperatures are measured with mercury ther-mometers hourly and a recording rain gauge records rainfall or precipitation.
These measurements are made at an elevation of 815 feet.
The data from these meteorological stations along with other dats from the generating station log sheets are placed on IBM cards on an hourly basis. These data include temperatures and temperature differences from Stations "A", "B", and "C", river temperature, relative humidity, barcmetric pressure, precipite. tion amount and type, sky conditions and vind velocity and directions at Stations "A" and "B" .
g D. Local Climatology
- 1. Topographic Influences T:2e Saxton reactor site lies in the main valley fomed by Terrace and Saxton Mountains to the east, and Tussey Mountain to the vest. Allegrippis I
.- - - . _ . . ~ . - - . - . . - . - - . . _ - . - - - - - . - . - - _ .
-103 2 Ridge divides the main valley so that the site lies in a steep-sided valley between Terrace and Saxton Mountains to the east, and Allegrippic Ridge to the vest. These steep-sided valleys are the most important influence on the local climatology. One influence of these mountains and ridges on the site climatology is that of channeling of vinds, the effect of which is to give a high frequency of occurrence of vinds along the valley as indicated by Figure 103-1.* The prevailing upper vinds approach the ana from a vesterly direction and are channeled down the van ey, giving rise to a southerly prevailing vind at the site. Tha mountain ridge tops are shown in the inner circle of Figum 103-1,*
vith meteorological Station "A" at the canter.
A second phenomenon caused by the mountain-valley topography is that of valley-slope circulations. The most pronounced effects of this phen menon occur during the night when the cooler air from the Broad Top plateau flows down into the valley frcn the east through the gap between Terrace and Saxton Mountains. The easterly vinds caused by this drainage into the valley do not carry over Allegrippis Ridge. Instead, the easterly drainage vinds cross the site and striking the steep vall of- Allegrippis Ridge, vest of the site, are diverted down the valley to the NNE. Also, during the night, the cooler air within the valley to the south flows down the valley to the north seeking the lover elevation.
A third effect of the topography is the turbulence at the lover elevations caused by the constant shiftin6 and turning of the vind due to the meandering of the river.
A fourth effect of the topography is caused by the relative width
- of the valley at the lower elevations at the site. The valley at lower elevations is vider at the site than it is imediately up or down the valley. This increase in vidth of the valley at the site gives rise to lover vind velocities when the air moving up or down the valley expands into the vider portion:near the site.
E. Pollution Climatology
- 1. Important Meteorological Regimes w
Because of the influence of the steep-sided valley the percentage occurrence of unstable conditions is only 3 2 per cent of the time. Thus, the dispersal of radioactive products frcan the site can be c.onsidered under two meteorological regimes.- These regimes am:.
- a. Under moden.te lapse conditions, air within the site valley is generally mixed with fne air within the main valley. . Consequently, the ultimate dispersion is in a direction deterrined by the-vind direction in'the main valley as indicated by Figure 103-2.* These vinas have two acminating directions; one is from-the southerly direction and consequently down tne valley, the other is from a vesterly direction with winds blowing up out of the valley through the gap between Terrace and Saxton Mountains to the east.
- b. Under stable conditions, stratification isolates the site valley from the general air flow of the main valley except when the flov is down the valley from the southerly direction. - Thus, under stable conditions, expected
[ dispersion from the site is determined: by vind observations taken within the -
valley at Station "A". Ultimate dispersion during stable conditions is determined, by the wind direction as shown on Figure 103-3
- Figures 103-1 and 103-2 have been plotted from data in Tables 103-1 and 103-2, respectively. ,
'4/s/61
i ' !
aL L 9 7 1 7 2 9 5 5 1 5 1 9 7 8 8 6 A 8 1 f k. 0 5 2 5 9 h. 2 0 2 6 4 6 3 7 5 6 4 3 5 6 4 5 4 2 7 91 71 2 1 3 T
S P _
U H O P 3 1 1 2 3 2 2 2 9 2 2 3 2 R M 1 0 0 0 1 1 2 6 2 0 o. 0 6 G
i )
1 1
0 0 0 o o oo 0 0 0 0 0 0 0 0 0 1 c
n M
A >
O 0S L 0N 2 : O V 7I H T P D1 A M N6 V A9 4R 0 7 3 7 0 o 3 2 1 1 o 0 0 8 9 1 N ,
1 ME S 1
6 4 0 1 1 0 2 9 4 2 2 2 1 3 1 O
I9 0B 6 0 0 0 o o 0 0 0 0 o o 1 1 0 0 o 6 0o P1 :
C 9 EY (3 RR 3 IA T6 H DU H3 P N G M SA I 2 4 1 5 1 3 5 6 8 h 7 5 3 3 6 9 2 UJ N 5 5 0 5 1 8 k. 1 8 5 k. 6 6 6 3 1 2 2 o -
IH RG 3 0 1 O 0 0 1 1 0 1 1 0 o o 0 0 o 2 1
AU Vo <
N u '
Iu "A60 H P
1 N9 M 8 3 0 6 9 0 0 1 9 0 2 o7 0 3 8 5 O1 6 0 1 2 8 0 0 2 1 1 7 3
I E / h. 6 2 1 2 9 0 T , - 0 1 1 1 2 3 2 3 6 2 o o o o 0 o 5 1 A6 0 2 T
- E SY i .{' j l *li !5 ,- i '
L R B TA A AJ n H .
T P 3 0 4 2 8 7 8 7 3 2 8 D u M 3 1 0 4 1 5 2 4 0 0 0 2
5 Nm I
W 1
1 0 0 o o o o o 0 0 o 0 1 o 0 0 o 3 FO OR M
F ,
E CS H NN P j EO M 1 3 9 3 7 8 5 2 0 8 1 6 96 5 3 6 RI 7 7 3 1 0 1 1 2 9 0 2 8 2 7 5 1 3 RT 0 UA 1 1 0 0 0 0 0 0 o1 3 2 2 2 0 o 1 8 CV - 1 CR 6 oE S
FB )
OO 4 YY M S H CL 0N P 2R 0O
- I M
6 1 7 8 5 9 1 7 1 4 7 2 6 0 7 1 T. UC 8T 5 2 8 2 6 6 7 6 6 0 6 4 5 4 6 4 8 2
7 QB E
A V
R2 3 1 1 1 0 0 0 o 0 2 2 1 1 1 0 o 0 8 F1 M 1 E7 9 AMR G 0O AN 0:
TO H N 89 P ED (7 M CE 2 9 2 7 5 o 9h 0 6 8 4 6 6 h 5 5 0 RS EA Y4 A
2 5 0 9 8 l. 7 5 9 9 7 7 7 6 3 1 3 5 PB D 0 o 1 o o 1 o o 0 1 1 o o o o oo 3 1
m N O
I .
T .
C L E A -
R E E E E W W W W r I N E r S E S S W S N wN o -
D N N N nE E S S S S S W w W N N T -
i - : i
l TABLE 103-2 PERCENTAGE FREQUENCY OF OCCURRENCE OF WIND AT STATION"B"AND PRECIPITATION AT STATION"C" Based on 5341 hourly observations from February 6, 1960 through January 19, 1961
'! DIRECTION VELOCITY PRECIPITATICN 0-2 3-5 6-10 n Total station "c" N 1.0 1.h 0.8 0.1 33 6.70 NNE 1.0 2.4 07 0.1 4.2 21 35 NE 1.0 2.4 07 0.2 h.3 13 35 ENE 1.1 17 03 0 31 3 50 E 1.0 1.0 0.4 0.4 2.8 3 70 E.2 1.0 1.1 0.6 - 0.1 2.8 3 35 SE O.8 2.2 1.8 0.6 5.h 3 70 SSE 1.2 27 1.2 0.4 55 5 00 s 19 65 45 0.1 13 0 7 05 ssa 13 54 52 0.h 12 3 10.60 sw 07 2.0 2.1 -
0.h 52 6 50 Wsw 1.0 1.h 1.6 1.1 51 6.10
-W 1.2 2.2 32 4.2 10.8 4.65 WNw 09 13 h/2 53 11 7 3 35 RW O.3 0.8 27 25 63 0.20 RNW O.6 :1.1 17 0.8 4.2 1.10 mrAL 16.0 35 6 31 7 16 7 100 100 5
?
c-
' ~ ' ' ' ' ' ~ ~ ~ ~ ~ ' '
103.!
- 2. Unstable and Moderately Unstable Conditions The meteorological data for the pericd f ram February 6,1960 to January 19, 1961 ve,: analyzed for stability using the difference in elevation of 5k0 feet between Stations "A" and "B". In this analysis, the stability classes are defined as follova:
Class Tngn - TnAn Inversion po t.o 0 Moderately stable O to -2.9 Moderate lapse -2.9 to -6 Unstable -6 to - cc From Tables 103-3 and 103-4, it is apparent that mixing between the site and main valley air can be expected to occur approximately 51 per cent (moderate lapse and unstable) of the time, or approxLmately 70 per cent of tne time during the day. Under these conditions when the vind velocity is generally greater than 3 miles per hour, radioactive material vould be carried out of the site valley and be dispersed in the main valley air or free air above by vinds frcn a predcninantly south-westerly direction.
At night, however, mixing with main valley air cannot be expected to occur more than 29 per cent of the time and with vinis of lover velocity than i during the day. Particularly during the su:::mer, the valley at night is essentially isolated from the main valley air flow.
3 Inversion and Moderately stable conditions The data of Tables 103-3 and 103-4 and Figure 103-4 indicate that stable atmospheric conditions (Inversion and Moderat,ely Stable) can be expected 49 per cent of the time. Of this, 25 per cent are inversions ar.d 24 per cent are moderately stable with both occurring predcninantly Q night.
Inversion conditions existed on 61 per cent of the nights with stable periods seldom lasting for more than 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. During these stable conditions, vind speeds of less than 3 miles per hour prevail 51 per cent of the time during night time observations and 14 per cent of the time during daytime observations.
There is a pronounced tendency for the vind to blov down the valley (easterly vinds are generally diverted down the valley by the effect of Allegrippis after crossing the site) as indicated in Figure 103-4.
A striking feature of the anemcneter recorder traces is the high degree of vind fluctuation on clear nights when the vind velocity is less than l
3 miles per hour. This high degree of eddying motion can be attributed to the influence of the tortuous path down the slopes and the many promotories which break vp the characteristics laminar type flow at night. The data of Table 103-5 shos that on clear and partly cloudy or broken cloudy days with vind velocities less than 3 miles per. hour (9-16-60, 6-17-60, and 10-25-60) the standard deviation of vind direction is 12 9o or mom. In the case of the
(
11-25-60 run the standard deviation was only 8 70, however, there vas considerable gustiness with vind velocity varying from 0 to 4 miles per hour. Observations of
,. smoke frcn the Saxton steam plant stack during stable conditions with low wind l velocity indicate that smoke is rapidly dispersed in the horizontal and vertical 1 directions to fem a layer across the valley, i/23/61 l
_ _ . _ _ _ _ _ _ _ . . _ .. _ _ _ _ _ _ . _ _ . . . . ~ . _ .
$.,64.8.G.83.%.n.28.R."O. M. S. e4E.O R. g 103 6
@ e4 A.
A N 2 n.
-e en m N e4 e.t e4 e4 N @ >4 -t tts 6ts E, t 8$6e8%%RRdR&RRRM d 8h t &&Ad5555dAAahAdA A f3 es e m g i
$m m
- $. 9. , , , , , , A. d. 5. R. F. . 8. 9 R. M.-
g A 0 0 0 0 0 0 0 0 0 m 5 25 3 Me s La S, s. ?. %. 8. 8. n. $. f. 5. G. 2. O. ?. W. %. G.
q @ s O O O O O O e4 m -4 mm O O O e a a o c.d L
$ e R98%8Mt%#&R8&SA? E neb -
A dad 5555dAAAAA556 a'
$4 en es , eo nm a -
7 e. e. e e. gee 109m gme999g ie.
m gr.l2 m O O O O O O O O O O O O O O O O
. . . 9tt%
O m'N So sO ::' O e4 R" 3o R. R. $. %. A. R. $. $. n. 3. #. R. P, 8. 4. S. . G.
S O O O O O O O O H H O O O O O O 0%
hdd q g O 8 k g h /\
I I (1 4 4 I e e i ddd i I a e d
$ U
~ 5Rl use 2 48R88 9 8 0 '~ n s 9 2 y N g"; s#e ddddd ddddd d d A l
- l p p 5
km995.945 O O O O O O O O O O O O O O O O mRRBRB9@e&8 4 S
a "1 P$649N@@@N@148? 4 bl@s e4 e
O O
?
O O O O O O O O O O O O O O O O to H ?.4 h
"*s e -
hh b b k e4 hb rn b b b N fn O O b
'G h b bbbbb bbbbbbb Ob n M O
>< cd b gvg g4 i e a e a e I I O 8 O O a e i O
$$' E o [98 n l 2, 9. 8. D. B. B. 8. 9. 8. 8. S. . , , , R.
O O Mg H O O O O O O O O O Y b tt\ O y @w @o m wos8Onnese ed e4 O en rn N N en a,
u 5 <, eed , .
m l g 3 m O O O O O O.O O O O O O O O O
!$$ m.
O R. B. 8. R. M. *,. M. M. E. M. R. $. 4 9. 9. 8 O O O O O O O O O O O O O O O O 5
m l
k M O
N a
Bas2 E 8 M O m anam amHO Ha**3. 9
I! ;' ; ; i i; , ,! .
cY" L
A 3 7 2 2 3 8 1 3 6 o 5 o 9 7 4 3 3 20 5 T
O 4 1 7 k. 2 E. 6 5 7 L. 6 1 2 5 3 7 8 b.
T 1 2 1 1 h 4 3 4 8 E 1 2 2 o 0 c 4 1 5 h h S
P U
C l R2 a 8 3 9 7 1 2 7 1 0 7 8 9 9 9 2 4 6 G6 7
t o
9 2 9 2 h. 2 1 3 0 5 7 5 5 3 2 5 2 E Y2 E T 0 1 0 o o o o o 1 1 0 1 1 o o o 2 L T S 1 B IH I A LC A 3 9 9 3 5 8 4 4 5 T 0 0 2 4 2 0 0 S II BH L
n1 0 - 4 - - - - -
0 0 0 o 0 0 0
3 1 U N
AW T
E p T
SF A O i D
NS L' 0 6 8 h 4 0
4 3 4 3 3 6 3 3 8 0 2 5 2 7 8 1 1 2 9
8 D 1 3 2 0 AN o - - - -
O M 6 o 0 0 o 0 0 0 0 0 o 0 o o 3 TI TT 6 0 6 h 3 3 4 2 2 8 2 6 8 9 9 2 IA CV 5 3 5 3 o. 1 1 0 3 6 2 3 3 1 0 o. 8 OR - -
LE ES 3 0 o oo0 0 0 0 0 0 0 o o o b, ~
3 VB1
,o 96 3 5 9 3 8 8 4 3 6 2 4 9 9h 3 1
0 2
2 1 4 5 2 2 1 0 2 3 3 0 0 0 o.
NY1 - -
OL 0 0 o 0 0 0 0 0 0 0 0 0 o 0 o 0 3 IR ,
TU9 CO1 EI I R Y l ILR a 7 4 5 0 0 8 8 1 2 4 4 o 7 2 9 2 3 DAA t 2 6 4 7 7 0 5 5 2 2 h. 3 2 1 0 1 7 TU o NON ITA T o o o 0 1 2 1 1 2 'l o oo o oo 3
1
" J E A8 L 4 7 2 3
" 5H 0 0 1 h N0G O6U B
A T
n00 - - - - - - -
0 0
0 3
- I o S >
o TNG AOI Y 0 4 4 3 8 7 3 7 5 3 4 l T T L 1 0 0 0 0 0 1 0 0 0 5 E SD E - - - - - - - -
L E0 T 6 0 0 0 o 0 0 0 0 0 0 B TS6 A A AA9 R
_ T B1 E 2 8 8 3 8 8 8 8 2 6 4 8 2 4 7 7 3 D D 5 0 1 0 0 2 6 5 3 h. 5 1 1 1 0 0 0 8
_ N) ,
o -
IM6 WA M 3 0 o 'o 0 0 o 0 0 0 0 0 0 0 0 0 0 3 Y
F0R 7 6 3 7 2 7 2 3 6 5 1 7 2 8 2 5 3 O0A S 2 1 4 3 6 k. 3 9 1 6 5 2 1 0 0 0 2
- U N - c.
E7R O 0 0 0 o 0 1 1 o 1 1 0 0 0 o 0 0 0 9 C B I .
ioE T
_ J nTF I o
iMM D. l DPO o'? a f C R 8 0 8 5 2 8 6 1 4 9 3 1 3 6 3 7 4 C0F C t o 1 3 2 4 1 5 8 7 5 5 4 2 4 0 0 0 8
_ o0 E T o o oo2 2 1 2 5 1 o o o 0 o 0 8
- : - L 1 F9 B O(E A M T 3 3 8 YSI S 2 0 0 CRT NU N n - - - - -
0 o - 0
- - - - - o.
- - 0 EoT UHH Q G O
I S
> 0 E I R REN FI E 0 V 1-2 0
7 )
0 o 3 6 34 2 0 0 0 0 0 1
3 TG N - - - - s - - - -
E N I 6 0 0 o 0 0 0 o 0 o GTI AHR TGJ X 3 o6 7 4 3 5 4 5 4 8 4 7 3 3 NII EN 5
0 l. 0 o. 4 8 6 5 8 4 0 0 0 - -
0 2 C E 3 0 o 0 0 0 0 o o 0 o 0 0 0 0 4 R3R ECE PFV 2 5 8 2 8 8 8 7 5 3 9 9 3 4 6 3 4 2 1 1 2 3 6 6 1 1 6 0 2 1 3 0 0 0 2 o o ooo 1 1 1 2 4 1 oo o o o o 4 1
- N O
I T
C L E A R E E E E w w W w T I N E N S E S s W s N w N O D N N N E E E S S s s. S vwW N N T
- i j , ; ; ' 1
103 The meteorolo61 cal data indicate that light vinds predominate within the valley at night. However, despite the temperature stability,a turbulent air motion prevails, thereby providing a rd stively high dege of dispersion of an effluent.
- 4. Deposition and Washout Due to the prevailing vind direction down the valley and the relatively lover vind velocity which prevails in this direction, it can be expected that the major portion of the particulate matter originatin6 at the site vill be deposited in the valley North-North-East of the site.
In the case of vashout, the precipitation data of Table 103-2 indicate a predominance of precipitation from the North-Easterly direction.
Thus, vashout of particulate matter vould be expected to occur primarily along the river southwest of the site.
F. Diffusion Estimates
- 1. Diffusion Equations
- a. General The preceding s m ary of meteorological conditions provides the basic vind information required to calculate the concentration of radioactive material at varying distances frcn the reactor. These concentrations are i estimated for three sources, namely: a ground level release for an accident, a distributed source for an accident, and an elevated source associated with the continuous operation of ,the reactor.
Subsequent concentration estimates are based on the following diffusion equations of Sutton and Bryant-Davidson.
- b. Accident @ses ThemaxmpconcentrationatY=Z=.OforagIoundlevelcource is:
% (y = z = 0) = 9o
- . '7/' Cy Cz U x.d -n The concentration for the distributed source under stable conditions can be estimated by assuming the source to give rise to the formation ,
of a layer of radioactive material across the valley with a thickness equal to /
height range of the distributed source and at the same elevation.
- c. Operational Case The maximum averaSe concentration at any point at ground level frcn an elevated source of elevation h is civen by
.d % max. = S (Q y Cz I
PTh2 u Where h is the effective height of the stack h=h aetual +0
. W7/61 U i
i _ -
1034
- 2. Diffusion Equation Parameters In order to estimate the diffusion parameters of Sutton during stable conditions and during moderate lapse rate conditions, high speed anemometer test runs vere carried out. These test runs vere rade for ten minute intervals and readings of vind velocity and direction vere taken at ten second intervals during the ten minute runa " sing these data along with the average temperatures at Station "A" and "E 'nfomation of Tables 103-5 and 103-6 vere obtained. In these tables 6 T g s the temperature at Station "B" minus the temperature at Station "A", 5 s the aver ~e vind velocity at Station "A", G is the average vind direction at Station A, O is the standard deviation of vind direction at Station "A", R/f% is the rance of vind direction fluctuation divided by the standard deviation, n is Sutton's turbulence parameter taken as 0.25 due to the turbulence of valley vinds and since the velocities between Stations "A" and "B" during test runs did not seem to follow the expected exponential rise in velocity with altitude, Cy is Sutton's horizontal diffusion I coefficient perpendi:ular to the average vind direction. The value of Cy was
! detemined from the Famogram on page 119 of " Meteorology and Atomic Energy".
Using the data of Tables 103-5 and 103-6 the following diffusion parameters vere estimated for the stable and moderate lapse rate conditions.
n g g U meters /sec.
Stable 0.25 0.20 0.05 1 Moderate Lapse Rate 0.25 0 54 0 34 3
( G. Conclusions
- 1. With moders,te lapse rates and unsta.ble atmospheric conditions which exist 51 per cent of the time, effluent from the reactor vill diffuse vertically and transport out of the site valley and into the main valley at elevations above ground level and most often in a direction covn the valley away frcn Saxton,
- 2. With inversion and moderately stable atmospheric conditions which exist h9 per cent of the time, effluent vill be restricted to thew ite valley
! vith a predominantly lov vind velocity, but turbulent air motion. The transport I
of' effluent at this time vil also be predccinantly down the valley away from Saxton.
3 The inversion er?.mcderately stable conditions which generally exist at night change to moderate lapse and/or unstable conditions during the day, and thus prevent long periods of contamination buildup within the valley.
- 4. Deposition of radioactive particulate matter vill be predcninantly in a direction down the valley in an area which is very sparsely populated and which is almost completely covered by forests.
! .. Washout of radioactive particulate matter vill take place pre-dominantly in a direction south-southwest to-south-west of the reactor. In l this direction, the controlled property line extends for more than 3,000 feet.
Consequently, the main portion of any vashout should occur on controlled property.
l
[
3/23/61
m -
TABLE 103-5 HIGH SPEED RUNS - STABLE (DNDITIO!4S Date AT(540 Ft.) U Q (TO Mr3 n Cf Sky Conditions 10-14 60 + 2.83 3.60 21 9.6 4.66 0.25 0.11 Clear 11-25-60 + 2.73 2.21 185 8.7 2.88 0.25 0.11 Clear 12-9 60 0.00 4.32 150 14.3 4.83 0.25 0.41 Clear 8-26-60 - 1.60 5 54 223 23.2 3.63 0.25 0.20 Clear 2-19-60 - 1.63 15.9 251 22.4 3.80 0.25 0.19 Light overcast 8-19-60 - 2.00 4.68 36 24.4 4.92 0.25 0.21 Partly Cloudy 9-16-60 - 2.24 4.2.00 227 12.9 2 33 0.25 0.16 Broken Light Clouds 7-15-60 - 2.50 5.14 43 32.6 4.00 0.25 0.29 Clear 10-7-60 - 2.50 6.42 351 23 5 4.65 0.25 0.21 Clear 3-3-60 - 2.66 '4.50 21 5.5 4.90 0.25 0.071 overcast - Snow 6-3-60 - 2.67 5.50 192 25 1 5.37 0.25 0.24 Partly Cloudy 8-12-60 - 2.67 <2.00 351 19.7' 3.45 0.25 0.23 Light overcast 9-23-60 - 2.67 4.22 189 23.8 3.78 0.25 0.22 Partly Cloudy 6-17-60 - 2.83 2.40 161 77.9 3.17 0.25 0.45 Partly Cloudy 7-7-60 - 2.83 3.60 36 24.8 4.50 0.25 0.23 Light Overcast 10-28 60 - 2.83 2.83 58 16,6 5.12 0.25 0.18 Broken Heavy Clouds U
Y E
TABLE 103-6 HIG5 PgD RUtG - JIODERATE LAPSE RATE Date o T(5h0 Ft) ii 0 09 R/dD n 07 6-10-60 - 3 00 3 90 255 h9.h 3.6L 0.25 0.L6 7-29-60 - 3 00 <. 2.00 61 h6.6 3.65 0.25 0.5h 12-2-60 - 3 00 2.60 176 17.5 6.00 0.25 0.19 h-29-60 - 3 10 6.90 157 33 9 h.51 0.25 0 30 5-6-60 - 3.13 8.20 191 2h.0 3.h2 0.25 0.22 h-1-60 - 3 20 < 2.00 213 69.8 3.63 0.25 0.8h
- 3 30 6.15 17.1 h.67 0.25
~
9-30-60 17h G.17 l h-8-60 - 3.33 7 33 203 12.0 h.58 0.25 0.12 l 5-20-60 - 3 33 9.72 23 22 3 h.h8 0.25 0.2h 10-21-60 - 3 50 < 2.00 75 56.5 2.62 0.25 0.70 l 1-6-61 - 3 56 10.50 217 18.0 5.57 0.25 0.16 l 9-9-60 - 3.67 5.20 205 16.1 3 60 0.25 0.16 11-10-60 - 3 70 6.57 301 55.8 h.30 0.25 0.5h 11-h-60 - 3.77 9.58 230 33.8 h.00 0.25 0.2S 7-22-60 - 3.83 5.55 -
212 15.2 3.62 0.25 0.15 l 8-5-60 - h.00 3.90 18h 30.6 2.62 0.25 0.29 12-23-60 - h.23 7.ho 272 31.0 h.93 0.25 0.27 5-13-60 - h.67 3.90 19h 18.3 h.10 0.25 0.20 12-16-60 - h.70 6.20 316 75.0 h.06 0.25 0 Eh 7-1-60 - h.83 4 2.00 209 1h.8 5.17 0.25 0.19 12-30-60 - 5.00 6.00 2ho 29.8 3.87 0.25 0.26 s.
b
_ e
/
l y) f;%
g /
% v. \'
- W ~ .
g ALLEGRIPPIS g
/
TUSSEY , , /
O f
- \
TERRACE hM EN O r: ;d))hl; SAXTON
- /'
l \ ,
N,/ . M O U NTAIN f
j/' \ \/ '_ . g N /
/ \ .-
/ N w
,/ 9 v
i ?<
/
d L.:i DAY NIGHT-I b-4)))) Dmi ; --j
( VIND Ross - Percentage Frequency at 0-'2 MPH 3-5MPHl>6 MPH Btation'1" Based on 7912 Ilourly Observations From February 6, 1960 Through January 19, 1961 FJOU12103-1
. -- - - . ~ . . . . . _ . . - . . - - - - - - . - . . . - . . . - . -
1
- 12.5 ~ -..~ l n'
..-'y ~. ,.
p
's
~
.- 1 0 -- . .. _
s % ,
,./y s, ~.,' %
,f' ,
's,
' s
,i
, ss ' ,.
- 7. 5 ~ ~ .. '.
- _s., .
/ 'N 5~~ ~
/' /
y %
a
.-. M e
x \
s \
T
.., /'s i i
~~
, N f \
l i
fl i((3 q'P7}/"/Q}/- -
Pf.C
}L 1 f .$,\ - -
t'
\ / ,.
\\ \
o V
v
/
V
% v -
V
~
g' V V
% v v
h .'
+
'N
, WIND ROSE - Percentage Frequency at station"sasased on 5341-Hourly l
Observations From February 6, 1960 10-2 MPH l3-5 MPHl>6 MPH l l
i Through January 19, 1961 FIGURE 103-2 :-
~ b S
f g
-yx g
f ^ %
S ^
- s. x
( \
\ \ >
i,- --- --owr-g
\ / I
/ %~.,/
s
~ -
i /
/
~
a ' \
e\ m r- -
'o '
/ '
g N .
i,
'A L 3 v 5V 0s l
l l
DAY NIGHT c2 )) M"2 L ,
O - 2 MPH 3-5WH -16 WH STABLE CONDITION WIND ROSE - Percentage frequency of vinda during stable conditions (Inversion and M::derately Stable Conditions TB-TA.0 - -2 9 F) besed on 2945 hourly observations during stable conditions from February 6,1960 through January 19, 1961.
f FIGURE 103-2
-x -
,.,,-.,u - - . - +.n. n- -,- .,e.-- , - , - - - - - - , _e.- -.--,+--...c-
h* ~
~..,,
/ / ,. I
/ %/ ,
/ .- .
,~
N q9
/ ',/
l
[..J. . .
dyg;'c!q
- Eft, . ,j F - f1"'NT=t 1
\
}
"~ '
// ( /
'O x w
.s
]
/3 1
DAY NIGirP r __ , ,
M.X - - - -
N 3SION' -
I -(- l INODERATE urse. ~l-T327A - M-0 0 - -2 9 -2 9'- -6.0'.
' STABILITY WIND ROSE Percentase Frequency at Station 'R" Based on 6058 hourly -
observations from February 6,1960 +Prough January 19, 1961. Unstable. conditions 3 2 percent not shown.
FIGURE 103-h
10h 10h - LAND USE The principal products of the area are coal, clay, limestone, pulpwood, shoes, textiles and those of related industries. A large percentage of the local population is employed in connection with these items. Each individual operation is small and only a few industries within 10 miles of the site employ more than 30 persons at one location.
Conpanies employing over 30 people are listed on Table 10h-1. Commercial activity within a 10-mile radius is limited mainly to the type of retail business necessary to support the small mining communities. There is some ferming in tl. tea; however, approximately 67 percent of the area is wooded, mountainous te. rain so the amount of agricultural products is small and generally is consumed locally. There is very little land used for farming or grazing in the Raystown Branch of the Juniata River Valley and the major farming area is located on the westward side of Tussey Mountain. The 33.h miles of river between Saxton and Raystown Dam, which is 18 air miles downstream from Saxton, it used as a recreation area with summer cottages along the river.
FABLE 10h-1 INDUSTRY IN THE AREA 0F THE SITE
- Miles Distance Direction Number
. Company ProducL from Site from Site Employees Saxton Bottling Company Soft Drinks .75 South h2 Saxton Mfg. Company Lingerie .75 South 1ho Martinsburg Shoe Company Shoes 7.5 Northwest h0h New Enterprise Crushed and .
l Stone & Lime Company Broken Limestone 9.5 West-Southwest 90 l New Enterprise Crushed and *
. Stone & Lime Company Broken Limestone 11.5 Northwest 85 Bare Paper Company Paper Products 11.5 Northwest 397 Roaring Springs Blank Book Compaly Blank Books 11 5 Northwest 19h General Refractories Co. Nonclay Refractories 12.0 West-Northwest 531 l
l Other major industries at Holidaysburg, Huntingdon, and oltoona.
- 1959 Industrial Directory of the Commonwealth of Pennsylvania
(
'2h/61 j
105 105 - POPULATION DE13ITY Since the area within a 10-mile radius of the site is approximately '
67 percent forest land on mountainous terrain, the population density is low with concentrations in the valleys and along main highways. The radia) population distribution within this area is shown on Figure 105-1. The residential population within one mile of the uite is approximately 1,790 persons and consists primarily of the Borough of Saxton and the small adjacent cornunities of East Saxton and Stonerstown. This number includes a populatioa of 975 for the Borough of Saxton, as recorded in the 1960 census, and represents approximately its present population. As indicated on Figure 105-1, there are other small towns located within a 10-mile radius of the site; however, of prime concern are the portions of the Borough of Saxton and the small communities of East Saxton and Stonerstown which lie in a direct line of sight from the plant. The location of these communities in relation to the reactor site is shown on Figure 105-2 which indicates that the Borough of Saxton and the southeast portion of Stonerstown is sftuated on a hill approximately three fourths of a mile to the south of the plant with a major portion of these communities to the south of the brow of the hill and out of direct line of sight from the plant. It can also be seen on Figure 105-2 that the northwest portion of Stonerstown is located out of direct line of sight from the reactor plant because the existing power plant and the gently sloping land southwest of the plant, which is generally higher in elevation than the northwest portion of Stonerstown, are situated between Stonerstown and the reactor plant. Hence, the principal concern is that area 'shown on Figure 105-2 which lies within 4
the indicated h000-foot radius and is generally in direct line of sight from the plant. The concentration of population within the h000-foot radius is shown on Figure 105-3 which denotes the number of persons living within the indicated sections of this area. It is clear from this figure ,
that the population close to the site is concentrated in the area which lies between an easterly and southwesterly direction from the site. The residential population of this latter area, which was obtained by field count, is approximately 833 persons. This number does bot include the present plant employees or the enrollments of a high school and a grade school located within the area, except for those employees and p1pils who are residents in the area. From the analysis of the upper limit of the maximum credible accident, as exclained in the Hazards Anal." sis Section of this report, it is reasonable to assume that ample time is available to evacuate to safety all of the people who could be subjected to direct radiation prior to their receiving an integrated dose of 25R.
The population density for the area is shown on Table 105-1.
The population density within a 5-mile radius of the site is about 6h p/er
- square mile and for a 10-mile radius, 53 per square mile. When one excludes Saxton and its environs, the population density within a 5-mile radius of the site is about 38 per souare mile and for a 10-mile radius, h7 per square mile.
(
2/27/61
_ _ _ _ _ _ _ _ _ _ _ _ _ l
105 TABLE 105-1 POPULATION DENSITY OF AREA AROUND SAXTON SITE Population Density, Residents per Square Mile Radius in Population Including Saxton Excluding Saxton Miles in Circle * & Environs & Env.trons 1 1790 570 h 2 231b 18h 25 3 2936 loh 33 5 h983 6h 38 7 8377 55 h1 10 16699 53 h7
- From 1960 census .
e 2h/61.
- . . - - . . . ._. . - _ .. - .- . - - . . - . .~ . ~ . - - . . -
N CNTRIKEN Y
MARTINS 8UR 4: CLOVER
%gCREEK H LL BEAVC4 T U" CU RYVILLg CREEK 8AKERg s.ENRIETTA
- TOD
{ SUMMIT 4 WO005UR)
( + le 2 5 5 7 IOMI sAxToN AO T DUOLEY E WATERSIDE
/ ROSERTSDALE 4
LOY 9 8 RfDDLESBURG
- I DEFW KEAMNEY N0PEwgL CREEK LAN 00NDALE .
SANYYRUN g.
R AOlUS, POPUL ATION MIL E S IN CIRCLE l l 1,7 9 0 2 2,344 3 2,936 5 4,983 i 7 8.377 10 16,699 RADIAL POPUL ATION DISTRIBUTION 10 MILE - R ADIUS FIGU RE 105-1
_ , , __ _ _ _ _ . _ _ , _ _ _ . . _ - . . _ _ _ - . . - . . ~ , ,
SAXTON POWER STATION AND VICINITY s\,
\ ',9Q /
,- / ,s- ,s
'% ./ ,/ ./,-
f ': y . %
~
o /n/,/ 'r. N
% / / .
18
,/ , dU -v{[ ;,<j [ e.,;
/ '
s,- r[" ,v / d,' N v
- u. .3.(s e%y n~
/t e
/.,
, x, x j' q Mpd i %,a..,!q[x['\h_
,(
y ~ g94g q -
\x hh yy~ww,s 2 ;/ &,.fny m hk a,
~ is i .
i ,i ,.1 /-
1 Y
t' /
y ' - --
- A l' l3, s - .
}g }fg ()$ -
? (( /
,,) >:/
y <) / /
x s,
% -. d
, x.;;, x N, g w ,. ,i,/
x, x .s Y
/,,
-y, ,. ,
,,4 ,
-) - ,
t
/vu ii
((
. m 1., \ l / s v \,J ) 3/ p[_;i FIGURE 105-2
. . ~ _ . . . - - .- - - .- -
k do)O'
~
J 3?00' 3000'
~ -
=
t $ 00* _
2000* f
- - 1500' ~
- 1200' _ _
_ 8000
~
_~
6
~
4
~
~ 2
- I 33
~
36 13 9
- 9 67 gg 14
~~
(2)
' 2 73 13
'"~
2 II
~
47 i 47 l
25 l
88 l 120 -
(3)
NOTESi
- t. ExtSTING PL ANT EMPLOYEES NUMSER SO QURING THE DAY AND 10 AT NIGHT.
2 A Hl0H SCHOOL LOCATED IN THIS SECTION HAS AN ENROLLMENT OF APPROXIMATELY 1000 STUDENTS.
3.A GRADE SCHOOL LOC ATED IN THIS SECTION HAS AN ENROLLMENT OF APPROIIMATELY SCO PUPtLS wwo ARE NOT INCLUDED IN THE POPULATION SHOWN EXCEPT FOR THOSE STUDENTS WHO RESIDE IN 'ME SECit0N.
i RAOlUS, POPULATION FEET IN CIRCLE l 1200 8
! 1500 35 l 2000 44 2500 109 f 3000 294 3500 528 4000 833 RADIAL POPULATION DISTRIBUTION 4000 FT. RADIUS FIGURE 105-2
106.3 106 - 0;0 LOGY The Saxton site lies in the Appalachian Highlands in the Ridge and Valley Province. The Ridge and Valley Province comprises alternate successions of narrow ridges and broad or narrow valleys trending generally northeast. This is a region of alternating hard and soft sedimentary rocks that have been severely folded by Interal compression into a series of antic 11nes and synclines. The ridge is of Tuscarora quartzite and small amounts of Pleistocene gravel and recent aluvium are found along the river.
Most of the area is underlaing by Devonian St ata. The strata dip in the area of the site are about 50 sloping up to the west. The data from several test holes drilled on the site are shown on Figure '.06-1. The layers of shale and sandstone found at depths greater then 12 feet below the aurface provide a firm base for the reactor plant structure.
Although coal is nined in the general area of the site, no coal has been reported to lie beneath the site, nor has the site been undermined.
O e
(
'2h/61 %s
Y 6 FM f a e< :2 n e w sy -
g ,,,
si w
e E
i N,
e 5
r
- Wu 2
[
vf 6 S u
o o w - go w -
e b .i g 4 9 v5 !! #
b dd a, s 3 MN g 6 e '
-.. .___; 3 iii g WRs<
g, %,
g O
TJ 6 s
- m w
T' -
, .o . ,oi s - :I b :: ' I n T .+- +-
& EU } !D 9 -___ l += l
- x. .= _ _
- :=: i til _
.o o. s a 3E llll kkf .
- - 'w y o -
o !n im k=g -
4 N :: inir u______ =
x'-- +l: , -.- -+ h d Jl.e. y l F y
L
. t.
g iiiiiiiE'"'
d*
- 9'4q' 1 g ..e,- g a '
< r .
b u.
p N
A iiiiiiiii n i i n o .$4,-(
h ,4 : h W
qN
-'s h
1 s
D
~o '
\
w iiiiiiiiii Y.W sNNNN\\ ' '\;'-
- Q,'$N' N'
J m' , om,g g i,m,,,
ggggg m.ng :s. s., ,y o .
x I
4R IiteiitiiiA \
b
\\\A%sA h, I
4y iiiiiiiiiiIi
' QRQQQQQQQQ. \
g._
!jj!!!!!!!!! ;QQ('<fqlRQWRI w < Ret 00N ;(2'0cceNNNsk]N U =202 \\
i i iil i : , il ii ; ili i iil o iil i ,,..l i i i i i i i i iii i i i l i n ,l i i i i 3l , i i li ii ii i i ii l i i n l 9 a
- n 0 8 s I id W 8 R 133:1 WI Hid30 370H IS31 L
FIGURE 106-
.~
. k(' '
~ , ' l, *. ' - , .
- . . - . . - _ . - - . . _ . _ . . . - ~ - - - . - . . - . - - - - - - . _ - . - - - . _ . . .
107 l 107 - SEISMOLOGY The area of central Pennsylvania has shown very little earthquake In fact, in this part of Pennsylvania only one activity in the past.
minor earthquake has been recorded during the past 200 years and this cucurred in July 1938 in southern Blair County, epicentered at Drab, approximately 10 miles north of the site. This minor earthquake caused no structural damage, although a sprinC which had run for generations was reported to have stopped flowing at the time of the shaking. In light of this information, it is felt that the possibility of a severe earthquake in this area is extremely small and that seismic tramers do not require further analysis in this report.
\
l l
\
f I
l i
i i
( .
2/2h/61
- _ . - - - - . - . - - . - - - . - - - - . - . ~ _ _ .. - -_- -_ - . . -
100.
10B - HYDRO 1rGY The ground water of the area is derived almost entirely from precipitation in the form of rain or snow. Part of the water that falls as rain or snow is carried away directly to the ocean by the streams and part of it percolates downwkrd into the rocks until it reaches the water table. In this area the main source of ground water is the limestone, dolonites and sand 9 tone. The shales provide only small amounts in joints and fractures. The water derived from shallow wells and springs is generally derived from precipitation in the imediate vicinity and water from deerser wells is derived from precipitation in the general vicinity, usually within the same county. Some water from rain and snow commonly percolates to the water table throughout the area.
Hence, the water table is an undulating surface which generally stands higher beneath the upland areas and which slopes downward to the level of the streans. The level at which water was found in the test holes indicated on Figure 106-1 was from h to 11.5 feet below the surface or at at, clevation of about 803 feet. On the other hand, the average level in observation well No. 738, at Saxton, three fourths of a mD e from the site and approximately 120 feet higher in elevation, is 50 feet below the surfact. This places tne water table at about 680 fett and indicates the magnitude of the water table rise at .igher elevations. Thus, it is expected that subsurface ground water movements will be toward the Raystown Branch of the Juniata River.
Sulface water in the area will travel down the sides of the ridges into small streams, such as Shoup's Run which crosses the site, and will be carried to tha river. Also some surface water will run off directly to the river. The water shed area extending upstream from Saxton is about 756 square miles. The average numbcr of days with a given flow of the Raystown Branch of the Juniata River at the Saxton gaging station is shown on Figure 108-1. Data obtained from this station, which is about ? ri)es upstream from the site, indicates that the maximum ficw, during the 1936 flood was 80,1y efs, the average flow is 915 ofs, and ue m.rinum flow was 52 cfs. Since the river flows through a steep sidt, alley, the flow downstream will increase, in fact at Huntingdon
. the averaCe flow of the hyastown Branch of the Juniata River is 1125 cfs. A hydroelectric dam (the Raystown Dan) of the Pennsylvania Electric Company is located 33 miles downstream from the site. This dam sometimes holds up the stream flow so that the minimum flow recorded at Huntingdon i was 12 cfs as compared to 52 cfs at Saxton. Such holdup possibilities might prove useful in the event of accidental liquid releases at the site.
'* The public water supplies of the area withh a 10-mile radius of the site are obtained primarily from springs and wells, in most of the small communitieu " dug wells" provide water for individual families.
Only six of the population centers indicated on Figare 105-1 have public i water supplies; these are Defiance, Martinsburg, Robertsdale, Saxton,.
~
Waterside, and Woodburg. The public water supply for Martinsburg is obtained fron nine wells, while the other communities obtain their l supplies from uprings. These water supplies are stored in impounding
( reservcirs, but none of these reservoirs lie within the valley of the
/10/61 i
-m<--e r p - -3:a , , ~ - w ., , ,- p w w-
108.1 i Raystown Branch of the Juniata River. Thus, the runoff, if any, which may flow into thcse reservoirs is from the west side of Tussey or the east side of Terrace Mountains. The Borough of Saxton uses two spring-fed impounding reservoirs with a total capacity of three million gallons.
These reservoirs are located on Putts Hollow and Shoup's Run, about one mile east of Saxton. The runoff which might flow into these reservoirs is from the east side of Terrace or Saxton Mountains as indicated on F1gure 102-1.
The conmercial and industrial water supplies of the area in a 10-mile radius from the site are obtained primarily from wells and springs.
There is no cenmercial or industrial use of water from the Raystown Branch of the Juniata River downstream from the site. The only known use of drinking water from the main branch of the Juniata River downstream from Saxton, is an emergency intake at the Borough of Newport, 60 miles east of Saxton. Even though this water supply is used only in emergency, it is put through a filtration process before entering the borough mains.
There are enly two known water supp?.ies for industrial use from the main branch of the Juniata River. These supplies are taken by the American Viscose Corporation at Lewistown and by the Pennsylvania Glass Sand Corporatien at Mapleton and at McVeytown. Amelican Viscose uses the water for cooling purposes and for make-up in their manufacturing processes and the water is treated in a filtration plant prior to use.
Water is used at Mapleton and st McVeytown for washing sand and gravel.
The Raystovn Branch of the Juniata River is not uced for trans-portation purposes; however, several miles below the site the river i becomes a recreational area with summer cottages and a Doy Scout Camp.
The hydrological characteristics of the area show that surface and subsurft e water flows into the Raystown Branch of the Juniata River; thus any dispersed radioactivity will gradually be washed into the river where average flow is sufficient te greatly dilute such activity. Also, since no public water supplies are ta(en from the river or utilize runoff from the mountain sides facing the site or river, there is little likelihood of 'he public water eupplies being contaminated in case of accidental releases of radioactivity. The nearest water supply, that for Saxton, lies on the opposite side of the mountain from the site. Wind direction data obtained at the sito indicate that winds seldom blow from the site toward these reservoirs.
(
/2h/61
RIVER FLOW RAYSTOWN BRANCH-JUNIATA RIVER l
.AXTON GAGING STATlON l
AVERAGE FOR 16 YE AR PERIOD
)
1 S6o - '
/
- f _
/
l
/
500
/
/_.
/
too
/ ~
/
/
/ ~
/
too
/
/
. - /
- y .-. ,/
iso
/'
, r j
f,/ .
/
soo 7
f
/
/ I r
so ,
M ES 60 78 gno ggy gyn g, f o AY#/ YE AR THAT FLOW IS EQUAL ' TO OR LESS THAN INDICATED Alf0UNT FIGUIE 103-1
109 1 l
l
' 109 - RADIOIK,ICAL SURVEY A preoperational radiological curvey of the environment of the reactor site vas initiated on June 7,1960.
A progrom vas developed on the basis that the deposition of radio-activity en the ground frcn either a reactor or. fall-out ccnes about'frcn particulate matter carried by the vind and by rainfall. Once on the ground, the radioactivity may run off vith the surface water,, beccce immobilized in the soil, or become incorporated in vegetation. In viev 7 of this, and recognizing that any gradual build-up of radioactivity surrounding a reactor site may become an ingestion problem lova before ;
it is an external radiation hazard, the environmental survey is directed toward the accumulation of knowledge concerning the radioactivity in the
. air and in the food chain in the vicinity surrounding e reactor. d
.< > /
Air, earth, rain vnter, river water, well water, spring vater, silt, vegetation, fish,rabbitsandpilkwerecelectedforsa=plingas these eleven media are sensitive to contamination or represent elements '
in the human food chain.
' The eleven environmental media are being collected frcn ttanty-two sites which are located within a radius of approximately 20 miles of the reactor site. There are five stations at which air is sampled on a cor.tinuous basis. The filters which collect air particulate matter are changed weekly. Earth is conected quarterly and vegetation is conected semi-annuany in tne immediate vicinity of each of the air sampling stations and rain water is conected and rainfall measured at the three of these stations which are loca+.ed in the valley of the Raystown branch of the Juniata
- River. Surfae, water is conected monthly et five locations; three samples from the Rayc mvn Branch of the Juniata River, one frca the main body of the Juniata River, end one frca Great Trough Creek which is a stream which flows into the Raystown Branch of the ,7uniata River. Silt samples are taken j quarterly at each river sampling station. River flow 10 recorded at the time river water samples are taken. Underg}ound vrter is sampled three times a year at three locations. Two of these stations are private wells and one is
, a spring. The Borough of Saxton drinking vater is also sampled. Fish are collected quarterly frcn the Raystown Branch of .the Junihta River both upstream and downstream from the plant d.ischarge. Rabbits are collected semi-annuany from two general areas; one in the immediate vicinity of the Borough of Saxton, and one approximately 5 miles northeast of the reactor site.- Special pemits have been obtained frca the Commonwealth,of Pennsylvania 'to conect fish and rabbits. Rav milk samples are c.ollected quarterly frcn four farms in the vicinity of the reactor site.
l+ The samples are conected by specially trained Sarton personnel and sent l
to the Pittsburgh Laboratories of Nuclear Science and Engineering Corporation where all analytical vork is performed. This includes gross alpha and beta counting as well as periodic specific analyses for potassium, strontium, uranium, tritium, polonium, and iodine.
A CCO M P 6 Q,v mED ( c,
/27/ 61 5'9
_ . - . ._ , -._y + - - _ _ ,
SECTION 200 DESCRIPTION OF FACILITY 201 GDIEPAL FEAWES 202 FLOW DIAGIW U 203 COE 204 PAIN COOLANT SYSTD4 205 PESSUE CONTROL AND ELIEF SYSTD4 206 C11AIGINC SYSTD4 207 PURIFICATION SYSTEM 2 03 COMPONEllT COOLING SYSTD4
- 20) CIID!ICAL ADDITION SYSTD4 210 SAMPLING AND LEAK DETECTIOc c 14 211 SIRT1'DOWN COOLING SYSTD4 212 SAFETY INJECTION SYSTEM 213 STORAGE WELL SYSTD4 Elk COOLIN3, HL,' TING, AND VDITILATING SYSTD4 215 VDNS AND DRAL'S SYSTD1 016 SECONDARY STEAM CY"LE 217 MAKE-UP PURIFICAIION SYSTDi 218 STATION SERVICE ELECTRICAL SYSTD4 219 RADI0 ACTIVE WASTE DISPOSAL FACILITY 220 RADIATION MONITORING SYSTD4 221 SHIELDING 222 FUEL HANDLING 223 CONTAIIBENT
!,/10/61
201 2".sl - GENERAL FIATURES A. Plant Layout i
The Saxton Nuclear Experimental Reactor Facility will consist of a small nuclear steam generating plant connected to an existing 10-megawatt turbine generator (Unit No. 2) located in the Saxton Steam Generating Station of Pennsylvania Electric Company at Saxton, Pennsylvania.
The major plant areas include space in the Saxton Steam Generating Station, the containment vessel, the control and aupiary building, and the radioactive waste treatment plant. A plant layout showing the arrange-ment of these major areas and an artist 8s conception of the plant are included as Figures 201-1 and 201-2, respectively. The containment vessel, control and auxiliary building, and the radioactive waste treatment plant are located on a 250 ft. by 200 ft. plot of ground which is situated adjacent to the northeast corner of the existing turbine room. The nuclear plant stack, refueling water storage tank, radioactive drum storage area, radioactive vaste disposal facility storage tanks and interconnecting trenches are also located within this plot of ground. The nuclear facilities are enclosed by a security fence and are normally accessible only through the control and auxiliary building. The loading, unloading and other handling of radioactive material at the site will be accomplished within the confines of this enclosed area.
B. Containment Vessel Arrangement The containment vessel encloses that part of the nuclear facility which contains the high pressure coolant as well as certain other radio-
. active suxiliary systems. The containment vessel is designed to prevent the escape of vapor and fission products to the atmosphere in the unlikely event of a break in the high pressure equipnent. The design of the contain-ment vessel is described in Subsection 223 I
The vessel is a self-supporting, vertical, cylindrical steel vessel with a hemispherical head at the top and an elliptical hecd at the bottom. It is 50 ft. in diameter and has an over-all height of 109 ft.6 in.
l The bottom of the vessel is located 50 ft.h in, below grade with the bottom head embedded in concrete.
l l The containment vessel, which ib located out of the plane of i rotation of the existing turbine generator units, is divided into five G gencrp1 areas. These are thel general operating trea,%he reactor compart- b f ment,$the primary compartmer.t,*tthe auxiliary compartment, Sand the control l rod compartment. These areas are formed by concrete walls which provide shielding between the various compartments and all except the general operating area are located in the below grade portion of the vessel. The general arrangement of the compartments and the equipment within than is shown on Figures 201-3, 201-h, 201-5.and 201-6.
The major portion of the operating flocr is located one foot l above the grade elevation of 811 ft. The portion of the operating floor 1
(* that covers the primary compartment is located at an elevation of 818 ft. -
. /3/61 1
-- -.--.-. _ _ .- ~.- - - - - . _ - - _ _ . . - --- -. .. . -
201
- r i
and normal access to the containment vessel is made at this elevatien.
- Access to the reactor compartment and associated storage well is provided at the operating floor level of 812 ft. by means of remorable concrete slabs. A movable bridge is provided over the reactor compartment to facilitate fuel handling operations which will be accomplishtu T long- i handled tools and an overhead 20-ton rotary crane. The equipmu access opening and emergency exit opening are also located at elevation 812 ft.
The reactor compartment houses the reactor vessel, spent fuel rack, demineralizers, and also provides storage space for the core barrel and spent fuel shipping cask. This compartae"t is normally filled to a level just below the reactor vessel seal line with demineralized, borated water. During the r. fueling operations the reactor compartment is completely filled by adding approximately 80,000 gallons of a similar borie acid solution that is normally held in the refueling water storage tank, i
The primary compartment houses the steam generatori main coolant '
t pump and pressurizer. The regenerative and non-regenerative heat exchangers are also located in this compartment. The auxiliary compartment, which is divided into three levels, houses various auxiliary system equipment such as heat exchangers, pumps, and tanks. The shutdown-cooling heat exchanger and pumps, discharge tank and pumps, and sump pumps are located in the a bottom section of the auxiliary compartment. The control rod compartment, which is sealed during operation, is c small roem located below the reactor vessel.
j O. Control and Auxiliary Building Arrangement The control and auxiliary building is a one- and two-story
, 37 ft. h in, by 93 ft. 8 in structure of concrete and steel frame !
l construction. The floor plans of this building are shown on Figure 201-7.
The health physics office, switchgear room,* battery room, .
Variable frequency equipment room, instrument repair shop, decontamination room, sampling room, charging room, auxiliary equipment room, toilets, -
l
, showers, lockers, and monitoring room are located on the ground floor.
The control room, . conference room,: experimental i~ % mentation rcom, 2 i chemie41 preparation laboratory, counting laborat- offices, and-building service equipment room are located on t acond floor.
1
. Personnel access to the nuclear plant will.-be through the contrcl and auxiliary building. The layout of this building is arranged such that e.itrance to restricted areas and egress from them can only b.
made by way of a single control point. This point is the monitor room.
where provision is made for personnel to take appropriate measures prior !
to entering restricted areas and to assure that radioactive contamination l 1s not. spread-by personnel leaving restricted areas.-
D. Radioactive Waste Treatment Plant Arrangement The radioactive waste treatment plant is an "L" shaped,.
( partially buried, two-levci, concrete and cement block structure. The general arrangement of this structure is shown on Figure 201-8. All f-
- % -=--=#4 5*--se=-mmewev-*--*ee=-t--ett-^=w+=="ew--'et-9-*-4t-+7-ae e' t'w*w+**e-* wee"'f-9+w+=-**m'w-Nu'*--eer-*---*
- suw'r =u* -f'N ste,k v'r- em&'1w--W~'*"*-? - + * ' * * -*4e
20) eauipment used for processing radioactive effluents will be housed in concrete compartments. The structure consists of a control room, storage room, evaporation and gas stripper room, pr.mp and compressor room, evaporator concertrates room, and drum shipping room.
The control room and the storage room are of cement block construction and are located above grade. The pump and compressor room is located below grade, and the evaporator and gas stripper are housed together in a compartment which is partially above grade and partially below grade. Concentrates removed from the evaporator are piped to a separate compartment which is located entitely below grade. The drum shipping room is located directly above the evaporator concentrates room.
The control room is t.ccessible when the radioactive waste '
disposal facility (RWDF) is in operation. It is expected that the pump and compressor room, and the evaporator and gas stripper room may be accessible during operation of the RWDF for only short periods of time. However, the control systems associated with the equipment in these rooms will be located in areas where accessibility is not restricted.
E. Existing Station Arrangement In order to isolate the existing boilers, eteam headers, and feedwater system from the nuclear steam system both from the standpoint of possible radioactivity contamination and from the standpoint of carry-over of foreign natter into the nuclear steam cycle, a new steam header I and feedwater system has been provided in the existing power plant. ',-
Because of this isolation which is being effected by,spoo]. pieces of piping, the Unit No. 2 turbine generator will not be available for use on boiler steam immediately after the nuclear plant is shut down for repairs or modifications. It is contemplated, however, that Jn case the nuclear plant is shut down for extended periods of several months that the Unit No. 2 would be made available for use with boiler steam, i
I 1
(
9 s
. da 4 _._.-_ . E _ a s __ iJ . . - aE. e a ~$n._ e . Jim .-.e4 -_ . - en - - _ e EI - . - e "e i 'l i I .' !
l ; . . s, .,..a,,,...
.i,.. .. .
.I^< +- J j.
l_ u - - di _
oi, i
.,+,.
{q; g __ -_
10
,j, ,_ --- _3 .
Nh I
.4, .
{4
'].. q ..!!
j e+
,(
- , dl, 1
' .. ..a.:n ?( . .L, ;l t} i !
l6 C. U
(,, ( .6 t f,I 4-p q.
L~g~*,3f g'j , F*$ _._.n. _ .~. b. -% r 1 4+ _. * , T,
. . .W.
1
.. . +
r ; i
- g. ,. h. ..
, b e_ . _ .-m..,
- i. . .
_.m 4._,, ,_ , ~. a '
1 i.- , . . - .
f f \ _.4, IM
]*, p d . It 2,, _.. . - . .. __ ,, , [
n;. ,- p.= 6 .m .?_n, i e. u ig .iII - ,
- r .
. t e r -
r ,- . ,ial ! g,,,1 :.f<,, ~; y N - l .p ... 7
, ,1y i , ;
i i
j,lej
,i *r I' t Qg;\ \
) o~ 1[u*\q t{
<, r l%5* i ]i ...> - 4 g l i C.-- , . , , ($
tg
(
,t
,;. e 4 l . s; e s.} ..S . 4, ,
,q , i u, i g .. m g
- , '! f e
- s I,
's
'kp '
. U !!al i
^'
,Il ff
) p'
- b. l i b t' 4 .
't a.
j {} I lI h > N.i ,Y, N A it . ,Oka -.
4 q.hi$ .
I i
il i
! 1
. *... ., 44,*r'd ,'L u. A pQpdf, r ,-- #: =,eM'. %
Mi-
.m il i
i (p
r
_ard4j s v- -- N I e ,-
Ih qg 4
es*q, f p
h *. g sI u - :. "*
l p?* . ,9 f .v y .i . .
- C .. I , . -
.'+s" '" !
l
- l [ ' h. jgQ 4f~a' . we ll l t
s , 4 In \ / 0 hJ e
- j i
(
- ,
- 1 '3 ;,,. {4
-) 4. iff ,' t. 's \ j i.
- l Mp" , _ ,,,.be
- jr ;gll. I
' lg.. t' b
...... r 4 b-l !
t \ ' ' :.
}I,\ ,f j
. ,_ ' o
, ---=4.-**-
i s.ia.;,+o.d'QM 8
esj; t'n 5
. ~p ' ,J ' '. h-l or v
i
<% . - .. .1 g , . - .o e , -
- e_ L' ,._.;c- - ; . _m f (. s.g.,b,.A + ', gg. \ p.#~..<;%
. k+ t , _
,, . _ _ g,
~ *,
l .q
,u . -.~ ,,t. g .m4 r ,c N
, ~ -4 l% ,t t:d.g.k*a g
, i 1, , .s', , i. _ y,T .; , 4'e,.. .!1,A. : S -.
/ I, 1 !
/
' .' ", :'.f: $ -
1, ,
..g. .
[ .,
r: -.I
'M 'eb,'L I [ b '\ /
- 8 (1,
. i t' . , . . .+ ,
s -s _/ .j
l ,\l#t ,. ' i. ,f... --
b
'. -i +,D. ' * * ' '.-
e -
-.5 ,1 r '-9
.i 7 a y a b- ..] ~ . .d s
[
i
'.1 l
l
.!',gI (i j ',
' N. x F'(,[. i
%+N ,*- r,f-~'-.}- -_f f . l . , l .,5,p,.i [i ,e 'p'.! T
.].
i
, . ,e d ,
-j . 4 + 3
!,s hp .e-dw] %j,,[ 7,ij ll'e'm -,1) ld.T -Ml y i ].- i i. [ .: , -
I .
- h. -
t l
-..i i.
t ..
- I t ' .. Jr u 2;;tti.ff m
- (.3 q' pag',s v. ,_;% '[ s a s
.I. s
's *
\
14t -
, / .!
q~ s
- 4- -+.
x eN
- - <6._
1 g3 .t * ,'I y\
,. r l
'u j 'T' 4, , f .9.' w-t' . ".-- b.s 7- \
i..g 3
s
...-~-.a__._ p ms, , g g
- h b, \ ., 4 l 'htj \ b cm ,. I i *ftlf,l i , - - .
)sl(. ':},
s l
il' ,' I t .
L
. ,o x
,' (! ,
t!i !gi ,
- tp9 a_
i
\ g I
l ,
j l .J .1 i ,
= mr , N
, , , * ' ,. c' 3
b- 4,743 .- e L '9
.- . - . . -. , h y( .7 7J , 8 w_
g ' , f @Wi!
i .
q, 1y. .,,,f ,
u'I ! ,.%.w [ _, _ - -h._~_ \
g , . k .i i ,l ,l, N1p
.,. s . I i8.N : l .- s 3 s.
- 3 r-- r.T. . . . . j
,^ 4 gii m .
F g
t* ;, a. , e aQ >
% 3 .I {
l
. M \
ITTZ'] N-h '\i.
i m ,
,[
g.n p }m w , \
170 grti ; bf4 b '
l '
I ,__ . / F M r *- i i
\
i
> -s t-pt:b 'M g;
_ w \
{ Al i v }f Q i I
a .
j ,
, , 1 ,
c
/,
ey)1-
,1 pl /
/ ,
, ,j .1 I RP [m tifj H l b'
,a [~.
g \'p &swer \
= .l
- t f _) I
,i j i
l\ fh '
/,
- c i l@ , f l ll s4 / / ,.3 i ..
7,/ =_4 ll%:ib,...N~ff$%&r33 amu __,
p,i 's9.aw' I
) n' 4
q
- ./
/ g
/f .
// 1
' ! /! L.
i l / i -t
/ " 11
=% 1 7 's '
~_-
l C l f G '/
l , l' f l }
.. . L. .,
l l .
/ '
1 i ,
l
\, \ :l ,
l .
- , .i
'i .t 5 !
E w--- . - . . . - _ _ . . . - -
N e
p .
d',_ ?I h ,
4.%
t J i
. ~.
s
=1 r.m!..' .m;3 ..gn; i _.
/ M.A.,
/ f, !
A'f;w.W$ thys-
./ ,/.pp::aj,4p..sg
'#.x' g g;g_
y&p9 1 j
( L __J4 14 E r~ji- #
t.
t u y,
,m-,,;
t
,(
c i
, ., . 4 m, . sn -
~ - pytffc .g2
' **% gs; 7t g_ ..
u e x
~.I .I
. ,.c - .,
MA-A l l 4%i 6(s,q= 'I I -;
k.
i . h, p o f, is f.,
e7
~A.t=.=
w..l.b, ". ,
O. I ."
i
- euwif.'
- 1 i ' rt T., !l
, ; $ I jll '
k fg*'l
}(({
p3 %mr[ihi-
%f wp Jr t . t
/l!
'- J -
yi gj g a.
. -a
.[i y
y ,
e { Av; 4u-
^
R ;. ! I ll l{,
2
.j f{\ p Il-
' I 2 v ,;,* la 1 L 2,:~.(( l wawq ---,----
I .
t )
s S
" $ thm, g o
f r ~_i
, ,g-I I pj ,". 7-,-v .. ; . ,Ns ,' . , a
" .s[..nt3+d.,
m me.-M j .
l
\
l .m_.. M, l
/,/l [3 ru *W
{y s$ ~ _$ '.7- T .g' i
a vi- ,fi* . 2g n
( + {A , .p y b,lJp3 k i i g.._
l . _W +, ~ d __ .
,* amp. . A1 y,.
J ps r .c p <
} [k : z l
f,s,,p <_. . i; ,- -
j i.
- y! ".- t ./
a L v. <
I v 4 ,I e il i
,h. a(r ?, .,osIMl ~[q.Q 'j1. f C{J jJ2, 3 m[p
.,, . l* gv s 1
3- -e. m-ke *
.. i o ,/, ,.-
4 vA l'
\ j- .. -
} ,
r iei t i I
E i s
- n,46 , e' l> i j f
b- -- .
. - - ~ ~ .
' l t t
I
- . l tt f
- h i j ,' It i
l l'N y I'a1.. ]
.n. b:
l i
j, , g -
l i- ,.. .
e s.
4 a .{, p .i. N . s 4
..gm,, a w.- m ,
f 4 I .
- n. g, ,r p't,!
_ . . k
, e -- ),--<4.11
! p i q ,r n, .m- i l I ._
zi g _,1, -/g. . . .,. aW J.,p r 7 b-' a I h' M, l E. i j,,, !
~ a.
4,,. s; (
y, pp3 , j . s, -
a r .ru _d.
- e, j w.=t. '.
t *+n
': t Y, Q. t::: :q 5
'6 ; ,
3 eglg r ;.=, /--
/
Q ;^
.h. ,NA+ [,
,k,,)-). ,e ' Ef) wa U ,
m . +c. , 1 - . .
f).
n ' li i [. ' . < t O .If it :
a.,
{ .4 ; ,
{ ;f.. +[
t I' , e i 4 :
+ 1 1 e s$
a.-w a, --,
.a-A. ,sawa,- ~-4_. -s. e-- Li -A J-a--m, --A --4 ... _ _ , _ . ,,
4 A
' t-.
3 g
(y,4 li wu.
f . _ _ _ _ . _ , , _ .. - -
m 3 g.y _.- 7 *;+ m . _ _ ,9 3
}!y ,1. _. C *
~ - ' "
i . -N. ~" ~ ~~ l .:n __ _
- 2. _. *8
~_. .f .. 5 -
~ . , . ~ .
r
. e x t ,y3.
i
}'
q(, 1::[
'~
- - - )".. i.g y
.:.r~-- j j )),; ':n
[ ,
$ * [lrU'"
l it '. ? .
.* V ,,H t *%C3)(l
~
- n. I1 ;_ . ._ .
t 1-~
f_ jp p.r p e, a g i e1 m
- w.
j _, _ _
1.
- g. ,j 2
. )_ _y. .
. _ . _ _ . _ - i
. m
,,, g .
_y
- P
- = l i j y77 n.~.c i 131_J i
1
, 4 Fx P _. Jt_ i:;
@~ '-
a
[.
v-
,i > gN
(
m
_ fi; .
m y,. n' '\
rp w m' 4 ,= '
),ht,-s ! s a
3 ie a ,,u, ,4
--- .' A pl y ,y
, . . ~ . . . . .
m.
- I I
[
[
L lf ---
u ,
6 h.
et !
Il, .
.]
f f **M f
& ._ . V. , u. u
. x 1 /
/_ '
- s %
ri auso p (
I
[ .
I
- I
- - s ,iifil i
+++4 t c
cy_ '
~4 i; ' '1,,q a e I .- . _
l [
r ! :
l
, ,,, 1b ,,n l, ,
if l g t
l 7R- ; .. %
+j r I
(=1 l
D_m:I.r,J.f.--...,,
i
- a'.
t- . . .
+ ~
. .- {== _
cr=
m -
g ===,e 1
, p; .
mm 3 r ., '~
I i, C. '--
1
,_)
t p Aj $
- ! =
- s. C
~
y{3 . . . -
--% 14 j_- ~ - "i p': .
y
E {i
~
! II-E ' 'r?!c! , ,<
= i hIN ;i B ,1 4 d 2 it !
I'o {l '
O i
- ~ .. .m. e mone %
--._n ,,.a _ , , B Ja,,,- , _ , , ,,,_&n.--- 1 m ..a,,, s,s _,-m^k,,e_-,._a1r.--_--n. - - - -ma n 1 ,m , u -,asa i ,
)
l 4 3
l 7
v:w.]
~'**
l PA r
, (t ((
, 4 i d* i f\ - -
I
[ 4l =w v'g l
a ( I --.f'jf
- /7s,1 ;(4-;l,p
- j i 1 -._.4.___
i
, 9 e:- ,~t_ .p.a_ i
.=._ ~. a .'
l sf t .
i ,I m, - ~3. r- ..
p .
I M . .-
er -l
% t a gn Cjyt* % ;
.i k,,,
- m. rq-
- /- ..cz , . v,
Pf
'I IIIII b
- IT~ f l h' - t 1, r.. ,, ; # ,.7_,37
- .- s .__
. pt r
- - . - e.,
, Q_,y, my+
1--
?< ; Ig
, 7v p. -
.,-j
/y ---- -- - - 7T -
.+
ss
- t.
4 u.
'tw . a_ ,, l ,
w[n, n
g%[ n
_f l e
,r '.?v . '
Vt 'h p t
+ wag
~.
t&
4 l f i-2 %
\g_4,Lf __
y; .6
_l, f
f , I i
.A. .p .-g N
\ l . 3' M 3, _ I l
4} f.Q} h tw] icc z
.b.p
! j ; ~
N s-s = =.mM i ., .
u Q,, ) ' ,,I
j;;e ,
L*J L.j .u. .,..d_I L*4
.a..-.
t
,=.x=_-
M.t
- g
^
f l yEr M' x
a .
l : 'A -
{ ..me s
. , I ,'
\
/.6 h r4 . . ;i 4
\
,'> ./
s
'i l
n.c .J
<,,y ... s t ,
C i.i Ii 1 eg l' LAh P Llylt
.O
.4 ,k a}._f:jLgnl j ..,
u : ::,= u .,
g, _w . .- - -
y.. .\ n U\
l?
\.g.Eu,s.)
. , i r >
t l , }
u.
i h
t y !! P sti j T ;
/
s l l \. .
l
-. A;r.s4
' ^ '
^
msa
,/ -
't 't p[i. J
( ( $1{ '
5 J,! N! }][ \ I Nj' "
l 'sllii3 ~
g ;i l 1
A ,
'y
'M b V 4 li -
r?
- i ,s,V-.
., s 8
1 v l t o
a.
l l
A ; _.
^-- -- ~ - - -
._-.. -___.-_.m . _ . - - . . . . . - _ - . - _
.h.s - . . -~ 4-_...._ . .
..- -u . _,
-a.- 4' E g 66 -- 4 4 se g 4.a.t . A
um . . . ,
h 6
- , . . . , . q, ..~-I~.-.-.~
f-
.Ie
- 1+1- -.4..
k .4 ' .1 1-'[
g A~' f . > . -l... ,a>, g,4 : ' i,$, * , ,C 3 ,
.,, ,;; ,t., , _ .
=i I . .. . .a _ 4.i . ,...s F. 'J
'****F .* .h *P hv lI ~
, lt , '
1r*.
'h :
h '. '-) h- -*% - - -
gJ tb
- t. !d, y 1." 'c .' ; s.
1: < t, y f jl -- __ _ gN _q }'
i' jt ; j - 1*
N ' ,' I I: w 5.,. T + .. .r g .i .
S ;(.- d. i
,( P dd.d.'4..h!.
- i. r :.
c i
.. k. c . ._ ..f . . .
. ' '. = I - .
T T'3 L3 ,.e.= q ; y .. _._ ,;{ . p y ,.
. , , /ay Q; ' '
- .- -a, w.a i s
_ m: . . _ p. . . L
.,]t i b,.
- n.
- ,s. 3 v ., ,,.. 4 ,
1 ,1
." o % e-I i
s , . .s - .. a 4 . . .
- 3.,
1 e . . ,i i
~. ;
$.b, t
y).'s- '1 . . , 13 * 'I .
- l
- V. , l'f**~i.'.' 6 fe
. k' e i 5 i s e_ j (S * * , .
.s .t g ; ., ~ ,
-bq.a L,.r'C . .. _I' 1 T~ m, l 7 } e q
2: 3 ;
l..:
u g........,.
. scene '
ml..)..l.MM,L. s ' . a.
= = a 4 in J:' ' [M a
t
. _d
.t .a...
.J c.'t. ; :...'4.;.__..
s <s
) f
- _ _ . t i._...%.,6.
r ss --...-:-
as. .. __.n-. sm.. . 4 )
9.
1' l .l
( t . . - - . ..
g .,
A e .
h n
- g *. ay - a as . ema_4
.4 . 89 ..m _44 , . . .
...B4...%64..e.,44...~%~,.
, ,, g
! i + 1 p, . .. , . .F
. . . . g ,.. .. . , 3v. ,
I._4,.
4* . w
- g. p il . l i I y+a ,
j - _i t
- ; 3 -- _
,I . ;%.
s
..- o 4. .T ;_/ em.. ._ ..wos-e . . . .: . . . ,
mm T ;h h T e d , !
I i -
n'O. i l * {;
, l ,$.+ [; C : , sj
- l, j % '. I F* * ,
' . . .; *p
. y F' '7-W 7 t t.. t . <..,- ~ - i . n. ,
p V - i> t. ""/"' ,
a p' >e j . .q.
- ~ $'
s s Q :='
~
- s. .: , ' ,
I i . ;
,x
- p.arr- . i N ,
j 1
. I a.
- f. -. . - . +
, ,n f I f
,h.]8 4 i h -
Ii dj . II
'o pl I.
1 ! !
dJ }kr' i;y 0lh$ g i I
g
' i j ; 4
- j t .rg m]
9 N.plj 4
[ tr i
g n1 -
a
- p {C l.
~
, t,*
I ,
yy --
-.4 h
.. .. _ . .. .. ...__ m.._. p . .. _
,[
p* f I' */,:i',yrr- d~
._.- uw ic _ ..
_A i i '
[ e
{r l; . t If i 0 el - . _ ml a __2 x C.?. l . .
1a x, ..
I i
- h
..a._ .._. .-*.*.s. l ,_f%< [ ;
, ,**__.--%.._i_.. ...-
p t. .n. . . a -_ s _ . _
{_
- tv.
.p fl*I (( . au . . -.__._._4.s___.- _
l I
s
- Ar, '
p i c ,, f it p ;7 4
pil
- i. . .. e I "" M hQY '
l n e b; f f i 1l>
o,, 4 1. ;~9 1
, y <
- t.
- i . .ti!
1 4 t 4 . ,
s.
i l
l
' * % Ni j
ase - r e e _,4444Mhu- -me.45-wA . N.5w-i-=Mdb---,au-a - p a p asm e -m..mrm.memws.agm-,.m.ug.ww._-- -------sp -
w4a hhi*dJ4he _._ .
Ee S
I g
- }.- '
I L
.~4*i
, .,n-.
- ~
-- .Cd i l l
, , t, ,-
i .
'.g.mwe ".
- ec
.s ,
) 4,.+ > d E Ol l g 4, --
1 p.. J <
f h{f .
t p ra l^
s k
s# ;
)\ -
! 1- !, ; l .j 17 t 13* ' ' ntW- . :.L,a.) : s. !$ : ,s l . 4 t n ['d, 4;II Ul ! f ..I l 5
1 ' ra
.q ,
[d g
(
tl .. . . a } . .. l '
I' 'ile . e.,
[, *" R* *'
-.h . % l 4W==, 4 o.
t i , .% . g , .
u2 ,
f h a :, i j
d,-
- ,i it i.u.; i 4' L ,p (, ff -
- 1 ,wI r== t X,
) i .
1 m.,m.s
, ~ : .m. =
y' -
sl.m((].
- l fr g f 7 ~** ; f-h .
, 4'g .. t ,
i' e,'
}=' ,g i. si l t* . , !
ly r l
A ', .J
/ e 3 ,;
l.A
..r-3 .
-.a g
f t. 4 q tr
[.M I
~
-J,.
g.ij.1@, .
4 -
c! "'.
) ;i,ch *ih'.l.l . t
- -..--~ . . ,
- N M i I ..,,.. <
I,'
, p ,; -.y - g 1 :p
.,5.. w _ ,, _ :Of.
s
.~ I, ~ ., . . : .
n ;
k Il]* ,R* -
--, i r2 h!I. y N
l.-
p iklIS saa 31 [>gM , k , I M s F P [,!
p [#n.g:..
D7 w lb'I'll'M_j
.y i df<
t ah,,n .
- m. a a . v. t i a- !: I. o, t.
s ","g:e. .. e.,:
li
,1 A, m4
- n ,o ..'m t.1 g 3_ P t*/ . i g l Np ffY k 't h W I f $l- h,, k. $ i'.
u'; - ,farj , 4 ,1 r I,j.-
I k-
- E,,my.>r '
i
- - C.tS--29#'t ', ij 'I y!
l L i li [ .; g t
- f e
!]M} !'
h.r 7
7 u- i
, e. . g.
' ll
.. 8 e!.
k .s:.I!!l o rw .
i-7 l l l eras-wsu1sy4w%=m-M W -? 9 T ***Mt'W4(7%MTb=M'Wfit9w'f'ide*t'*WTT
- '*w?"wW*"8f9P"'**T"" .-'91*"" F'"F Mn i^'F"-' f" F-V'M'P*'FWN'8F#-N '
M
2 '..L 1 l 202 - FLOW DIAGlW U
!. The facility is represented en the fcllowing camposite flov diagrams:
Figure 202 Main llov Diagram '
Figure 202 Main Flow Diagram, Instrumentation Figure 202 3 - Miscellaneous Flow Diagram Figure 202 Miscellaneous Flow Diagram, Instrumentation Fistre 202 Services Flow Diagram Figure 202 Services Flow Diagram, It ~"Jmentation A composite flow diagram for the radioactive vaste disponsi facility is included with Subsection 219 2
4 I:
l
. i$1.
m -- - 2,2-- -
j ,_
l l ( )
1 l '. *
-1, , ,
.l
! l.s * ,
i l t .. l F**( Y l 3 y'
, p tii I,t(-.
~'
'fm _ %_ Q._ t_ lpr.i .
'- :: l l)
- ,, st I G) ~1lE .,
(
'ta 5 -
dkg;isf ~
MN5 'I ' ,
! ,klf 3-1;9 A. p %2 " e ,gP a_
ar' ,-
ii Ih" 4 "R i :
i
- n. ,l'!! i ji m'l ,rI,li .9i *~
e '
1 y
j'P Ed t2 .n ' -
p_._ I u'l (:
- 7"7 !! i ~r i
i (p~
i ~ t ii i
i,' ; 9 ,ji :
__1 .1)~ lJg ;, I, p,i t i ll l
. !'iL
- , , ,c I ; iil,f' I i
- i,i _ ._ ,1 it __
y'11 1 1
i I i
' yi -'p i d,es Mf l I n
~' i l g
.. NI"'lY \h i t .
4, ir < o; rs tifil Ii i '
q
&gd(pi;!.16j-]}'}t J
T!
iul.1 "
G@$'N 'liru r =-
1' i
)n j
ci V ..>, , o
. 4, .L i _
w=$.5-mmen.w'~5m1., A- ,p. C "'
F %AMJ .,.,ENi+hdi a r .#3a.2 -
ijbf ~' r " P * -- ~
y
..rifff^~ - #qi ), tim a 6:
i'E
@'M,n 6
S.u %]@[ n $ frls:i;@4 ,81%]h l
i d
- c- ,i
. A ia i N,, y ,
,.*.4 Q .)t ,
@aa .....t.
fr.Ib g g e nL l
'i 3
- , w:W,hi d'i h i I
_%I l i, , r, hj l 1 v.
l i7i F.
N bu y; h.3 g
!!, w g ~ ,
t r s'mMrr ei;:Nsevq e
' 11 d. ,
t i .
i .pg hk' 3 ~t__.g,;
4 , , ! - .- 1 lI(;P i 41,N[ -[ tin(i}lj d.',',i:!b,gh,.
l E ,9 l '
3' i l
. q r . ,m --,i. m _,,
l
[;
g
[
a .,;
g
' 'h)
~"[
I l ,y II,dif!8. i . il l
- .l l l
v e l
,31, t it, n4ilipl. ill j% ii A.. .%
1,
,*i r
l
.37g : lI W- kI T- '~~
"iii l
I llLiisualii i i ii s -
,il
-,' t i 3' L Y, M, f p\ ~T'lial Jt.
- r-n-il' si* m p il jy"ll[jj iii _, i
,s
)i, in i j g i i r .
( i, i i
. , , m. .
R b, vg ' -Il 4-lpu w a, , i,n WM r l ,j l ! " i N,,h],1111 il.
ti j.
l ! Nil r3_'f i, "' =
[] .
+ i
- 8'
. ).k l
l
e t t J
.!....Aa.-* ,
er a s- .r q _.,
N ,. .__ niJ ]; h; s
.. t ry :i g:p yp .
uv]m,- u,d.-- r-p
- -z,A .
< J d,6 *plfh"l![.h 6
~
i ,,
g,j pe
, .g 1.y .
4,. , , . .,
n g(WI !h (+ fa{i ][
' 1 ' t' 4 +
i
.j.
a ,p
- 1[p[I
. . _ l
- Nd lhJ
- fe/4 g g,' $fM'h8
,, .. e.- .
+
-D l! "1
-+g.g.[hM j!
,,a n=,:::
ln i . - - -- p ;
7 ,. , ] ,
II -= -
! K-1 ;
'b , *thi
- ,s s. -
i llM[p.-
[j-e i-i
,l-t
,i %, jr}ynmtjt ll 4
!?3 e' W $y :l ',
. .'. '.i Ii l f't 2- fl .-%I.'l7 j!
lsi ii.4gwr= v l
'}' *' '
- 3M t "
. 9 T,if,FS%. in p ,, ;>
,=Wp'!."t?!Q twi %:r :
o 7 t u g. 7 g . 4 4. r ,.. ,,,,, s. .
-4 I 1 -.. J l
,;, ~I ' " ~ n ~ ~ l'
-F - - - - = ': ' = -n " qFe~- '
' II : !
l((I, 4_. ' 3
-, M ir F I ii Giu c z. .
' p<
i f1
! l}rf'qf-"I' : J c
c t.. 4*
+P,3l [ -': j:,j: id --( h J.
ji .m .
rf 4 h
':: ga .3
- - " ,,I,,!
x i l' ,. r, u _ _
- ~
jc .a { 3. i
,.,..-~~.9.....r py ; g gg . J ig,;g i' '
- *~l. g g, m(?q,-f?t
g--- w , a* w-~ " _f.gg,...q.1;h,.
ci(
,i I )n;t # iT[_ {e l 7 y M,,( +
.y plw . .y y _-
g4i 22,g$ p; - - -
Lcqj'I r
., w . r
,. - 'L ,3!u'; :i- _
i s A4+--i i o- ' . .a 't ,j i.W+,.:.a ua 1(o 4
_ v--1
- Iqlp_ __ _._, .__ ,
_ ,,1 t
, l- 1r i L .q =
y, lh. ei bI0% e f , ,,
L+--
TIM j +
4 q-11
- lil , i i
ljjJl;i imm in l..ii i
g- ;
-,p%l , _1'i l l t
-k,lO,g wm r v -
L1,g-3 l7 w ...,> n uea p > l. -
i ,. R
?'
tj3 113Iii f
81l -{ ? ~/+6 111l'i y' g3=-4 i}
i g - -l-,, [ . .
l 1 t g l g si . b'7;'j jj,,j g 4
' i 'r i g> : x * ,,
'nD4}i f L7
.n ,
,p q,; ,
- H J' i Q1 ijnig"d]. i > c
! fI llllfl! b "k 'Y U j d -
'l h)slz.h : , .
y
~ pii+
- ,2 I
l
t ( ) !
...-..,.-n-- ...#. = . - - . -
- - ~ . - . . - .
l . . . . .m , i , , . : ;
illilillllill!lll :- - +- .gr 1 . _
l.!
3 l l
9 1_t i m
i , m.
s
- ____._.u r
- _-- , : - 1 I,e r .;i e
r, 1
.i i
,,,m
., 41
'T(-l , , t ALA l tit 47, f'.
I
/
I ,l; g; ,p -
'A -j gjUi ,.
g gjiT -
1 r- -t : uS .' .#
l "i@5k1!xh. . W d
- jln,fl ll fig t ;!li ll t ~.
a ,' - ;--
s.,
'T T I
%,7 l ...i _ l gth
" ""- "" y[.
i 111111111) liiiiii
. [e [i
=
' .i i -r a giy
. .r ,- u, n n ~.+ _.- a. nmmwn,n n.--no, e- an.a.
i l
- ,i ,
j ~_~~' i. , .
gtj
- [iro- ,
[ m ,,
^^
llh!*-1 II t
I
'Ik]5
[L _ 4 I
t pi ll111 Mh , ,
Irj I
- 4 n ina ti i st! , c-
- ...gj.7-q.
i I j ' 'tOi 'Ii i -
I
~
l: I l-- i, T, '4 yyrm c r I.:
I.. v-W -!, : e id
- k, '
[-; 'l1.1J h i
'i H
I+.
8:
~
'. i -
3' IDCs . "I&-^ -
~
k!l' IT.)
I 1* l,
~*iTI
- l
.illl 'I11i [h, I
+r, i, l'
ghp '
i 4I{%ffitg' ;'
ij 73 t
l I 4a,.
hi h ---<f_v&.Jd 7pi -- R : T; lh.I E'l t t '
Y Mi I -
II Y e- t dyri[il*+Lm in ifj i
- r. -l>1 -
1i % i Jll' iT , ,
llI l dI..al.
i_
a,, El .xbm+fi g i lr i ri ' I i~lQldi'j
' I _ _ l$ I l -.i - - - iu
__J_1."v _i~
r .
i n n
if i
rlirlgi isp,*9 ii
! i i ' i ;Ql4 l>
, ,r. s. . . - , , ,!:hr- i
_i i f
i
[ s'Nif i f op ** I::E=_j l 8
l ;!!(
i l') r#'lI g )4dfi :4 I , w 3
- - . ~ . , . ,
A t.t
. , - . , . , , . _ , _ . , , ._,3_. - ,_.y. , . . . , , . _ , _ , , . , - . , , . , , , , . , , , , , , , , , _ , _
t l
6
. . . . u . m i ,, .
i llll 'lllllIli : ,
_,: .QF
_ -- _ s I
i i gh j . I fl
..........._ 3 ,.,i ". -
n
., n e u 4-T .l.,..; 1 l-. ' i j
i .
j i ,)
4ll g
l{ yg _
m
.l i ,
} r ... - .J i
QaM 10 7
' D~; ,..-)L.j.
t c .
i --_ . -
ffll,l Ijl! ~Ek'Al _, t [ ,
' ' f ,
l
.g., _. i i
- e. ig;a.gru.r. i I-
., a 1111111111 1111111 .L .!L
- l%._3L.
1
- . 6%
__ y__ _ -
al lj 'l luo ..
8 . 1 . .
i M y i
h...,$.$k o 3, ij ,
s I a . h y- .
y1,pl[tl:i,N [.
i *,h,,,, _. i . - sje k-3 ' . .__, .bIP ' l._8 l U
f "
J il 1 J l'I; t i su6
'll. .,'.
4 m9_'". !~
[.g E3:
,_c x )))
i, 11 lli fh I*3! _
-- }I; h . .. I ]
l'ZL. ;g3i er i
) t- sii e, O 'j'30 e- i
- ac- i~ ee-4 > i
( si i tt i FdiZt}1 -
&i'/~
u hrT;,
qll1 I- ii i# '
ll l
p_Ll- C .--
l __
I #% g Y l}
IL, ,- di1 4
- Y
.@'." i i
i
!U __
-> l i
)
) - - - -
i___ _.._ . .__ _ __ n__ ~I I .
l yl182__ Igl%
3 I l . . ,
pli )- ---l Ii g
1 Lf I m
If yZ.p-- j I
- ,l il.i i ;yi Li,!,
T 4lll J i y i ,t if y
._,j, appy-i 'l @,341'l i i t -
.i.p._. g% J g i ! g"p ip p rp
' il t n. i ! i dW
.u a
g g g p p7!nu t ,. -
i 4 i g
[ jff {'
lE l')
rf{ 'I']
l
,.- . , - '",1*
I.
,,#- gyw_, ,
-..J A 4a 24 a - ..L.a 4 __._w# _._h_ d -ma
..o . ___J - L .- -a 9
)
.n clWm f:=lf tf J 7d r 2
- lI b l?$1$[}!h~7,, ,'T"hh;'
I 1
jij* 7 p
- T. % ,
=
'hlhi,Ep,Oh]
u, .
L +i j tj
% a,u,
, ( Vpp , '% H E}
I*f*
d ii
' ' W I I llllY Vk ik
,,. Y k k t! $
i s' L sy; < % I LFi It I
b' it
y? I'
, g l &- ,,lif l
j ,.s
.. ~_ ... _ , .,
?Q) $f36? ,
- [k f!kh n N .7
!IllI!lll[lI pt "y g f h'h hf f 1
if' i '$
4 =, 4 u s ;; h l T ljillljl -
u N , hN'l!f #,~
i wim .f'o, mnj w$:!"(v5 u gt, ,
l,,
IfJiT, fg'
,,kf1j! *,
5, .
., c Am oog
- m. ,
'( -
ll -I
' 1 - t ,'
lifll j, , tr~. ., l
,, ,' ,i ,
t , re .% _~
1 'i Ij l)f I If d ,h .ip{
g ll i I ' llI li = p _' ' u, ) , \l,' t
- t gij4@dyQ+%Q,_ i ,, T!pr#38'I i p,, t
, J l
1 i '8Dg I5 l ['lJTFiprt _T$i!!i ~il I-ij$
' 1 d'
yg"' Vg!!,,3fln'j p .-
g([,m8 I'k)
l' !
bp' I ,f f i
b
- s, l
m $ li!
L V-4 h ii $e @' R E yo 6: "U &3;lh,'Ihc '
j ,"' w $
l 11 ljrj i "
? 'p .5u, j #lMlif,7ji I,kl!fj!
y r ,
s -! -
l l
l l
l .
o I e )
( $
y- w y-k_
~ '
3 lbr * .
- ll 'l{
5 t h - 1: -. l 5 .t. i;, I L_ _. . _y ,
- ,g l . p, l
5 lI,fI t
, t s t [ [e[lpr.- l. It .
l
~
4 f) %;
j .p.
l , it
" l . [, l
<lj E ' '
[h lQ bI(
i L_ L, i IR
" " #_ 'l ,l (!,(mN i s Ji,1 ],. 'hp - ],I.g a' ~..
i w' (....
ll' ti, ggi lI t ^.
7 s
a_a -
i%s - --
I 18; 4
,1 lli i\' ll l lg ? I I -
g- , si ,
e _4 _
1p, '
- f ' f[-
, g__,
j g 7-3
~~
g IFl!gj W,g
- g7 ;gg g l /.
L" ,. 8I e" M l
111 111111 liiiiii, T-(
i
}l, , ,
f=
Ni h
ye a 11
-, !l f1 2.]hC s 7 pl-o . %. .. J -- > . ;
3 g 4,'g, ..g,ug._
m -
. a
-fII - ?y,
~
P f ij @. .., _i A,
. - ~ . . ~ , ., k,pg ,
c c:
fr#1 1
t
- J;
- r
. . . .n 2.i.w .s ,% l i Ni m 4llNf6.g' 4
- - .v n . - - - -
e
.; ffF@
s j "jr,$7 -
I E1 Q,'
dl'Sq!'p,T !s l
- i. ,
if shii p" <,.-- p- t, . I d LMN' 5
m U
'jl -1>
e
, l g, _
s- I TN k , .,R ,
I
.tj
(
! $ l- , g gg - itj" 'I ) ,
g
!T p4-} s ' , f.,, .
-a in
% j,...,f w iij
- E m _n i , ij %-
4' l !i!WlI ,.
1 gdj
_h- ; ,,.
-7"--
- - - -,m .
- w^_ _
m -
[' s?g Je
203.1 203 - cent A- General The nuclcar fuel in the water moderated und cooled core is contained in 1572 fuel rods. Each rod consists of 50 "02 pellets inserted ~
in a stainless steel tube.
The individual fuel rods are grouped into El fuel assemblies et ;
the spring clip design. In this design the fuel rode are held in positien '
by small netal clips which are part of the spacer crids. Thic allows axial metion of the rods and the use cf cold-workea cladding caterial.
An assembly cross section is shown on Figure 203-2. Mine redt are removed from one corner of each assembly to allcw slots for contrcl ro ds. By use of offset cruciform control reds, the cuter configuration of all of the assemblies are made identical and thus an assembly can be used in any core positien.
The cross section of the entire core is shown en Figure 203-?.
The active core of 21 assemblies is controlled by means of six centrol rods -
and a solubic neutron poison, toric acid. The L-shaped spaces, which occur due to unused control rod slots at the core edges, are filled with L-shaped fuel subassemblies (shaded pieces en Figure 203-2).
The core contains space for a total of 31_ fuel assemblies allowing j a larger core to be inserted subsequently, if desired. The el_even unused spa:es are filled with dunny fuel assemblics which consist of stainless steel boxehr having the same weight and handling connection as the normal assemblies.
To leave the top head free for experimental purposes, bottom entering control rods are used. The poison section of the rod is positioned so that with the rod withdrawn it is above-the core. Failure of power to the magnetic jack mechanism thus results in gravity fall of the poisoned section of the rod into the core. Nine penetrations in the reacter vessel are provided so that three additional control rods can be added if a 32-asschbly core is ever used.
The top head of the reactor vessel is pierced by eleven penetra-l tions. Six penetrations provide 3-inch diameter access holes and the remaining penetrations p2 ovide 2-inch access holes.
Five of the 3-inch
. a:;ess holes are directly over active assedblies. These ports are large enough te allow nine red subassemblies to be inserted inte and rencved from the core without removal cf the vessel head. These ports are arrarged so that the removable subassehblies are in.as many geometrically different positions as possible without. violating the spadng. restriction:
l imposed by the vessel head design. .The removable sitassenblies had their l instrumentation will be mechanically connected to tha vessel head so that- ,
they can be easily handled. The remaining 3-inch poit provides the access which will be used in the future for insertion of a sugerheat loop.* The 2-inch access holes will be used fer insertion of instrumentation-leads.
t
- The superheat loop experiment is discussed in Subsection h10 - Component '
and_ System Development - of this repert. This experiment will be covered
'3/61 in more detail in an amendment filed at some future date.
- . - . ~ - _ . - . - - - _ _ - - _ - _ - . - . - - - . - . ~ . . - _ = - . - - - _ _ - - -
203.!
D. Puel Ascembliec
- 1. General Deceription Each fuel accembly hac a total maximum length of 50.25 in.
vith a nominal fuel length of 36.6 in., and approximates a 5 386-in.-'
~
square in crocs cection.
The fuel rods are compoced of stainless steel tubes which contain uranium dioxide fuel in the fom of cylindrical ceramic pellets.
Tne rode are arranged in a pquarelattice with a 0 580 in. center-to-
- center dictance. The pelleto are 0 357 in. in diameter and 0 732 in, high.
These pellets are produced by sintering a powder-ccrapact of 5 7% enriched UO 2 . The diametrical tolerance of 1 0.0005 in. is obtained by centerless grinding after sintering. The end of each pellet is spherienlly dished to provide axini cpace for the differential expansion occasioned by the radial temperature gradient. Tne length tolerance of 10.050 in is obtained in the compacting procese. The total pellet column- tolerance of 10 366 in. (one half of nominal pellet) is obtained by pellet selection. The clad inside diameter vill be 0 3610 + 0.0005 in. The resulting diametrical clearance between clad
~
I.D. and pellet 0.D. is 0.004 1 0.001 in.
Becauce of tolerance buildup in tube length, pellet etack length, and end plug lengths, the poscible large gap between pellet stack end and internal plus cnd is filled with sintered aluminum oxide (Alp 03) circular hollow dit es. The fillers are added to provide a 0.174 to 0 352 in, end gap and thus provMs a pellet expancion space as well as fission gas i release space. The moisture content of the pellet stack is controlled so as not to exceed 75 p p on a veight basis. The fuel rod ends are hemetically cealed with end plugs velded to the tubing. ,
Two basic materials are used for the fuel rod cladding. Those rods which require no further velding are clad with 0.015 in. vall Type 304 velded stainlecc steel 10% cold-vorked with a 0.04% (400 pp)maximumcobalt content. Tne end plugs are Type 304L. !!ovever, the fuel rods whic.h require cubsequent brazing (for the L assemblies) are composed of 0.028 in. vall l Type 348 moairied carbon, annealed stainless steel with a 0.05 (500 pyra) maximum cobalt content. The end pit:gs are from selected heats of Type 304 or 304L chocen to obtain 5 to 10% ferrite in the veld when velded to the above Type 348 cladding.
- 2. 14ain Fuel Assemblies The main fuel assemblies are of two basic types. Group 1 is a 72 rod assembly arrrnged in a 9 x 9 lattice with 9 fuel rods in tlir outside rovs removed frcra one corner in order to fom a recessed corner. t The adjacent recesses of two fuel russemblies, when positioned in the core, fom an offset crucifom slot for the control rods. Group 2 it, similar to Group 1 except that the center 3 x 3 fuel rod cluster conszitutes a removable subassembly, alloving special test subassemblies to be inserted in the future.
Hence, the Group f main subassemblies contain- 63 fuel rods.
i
/13/61 .
y ws w w-y ~ v w- w -yT--*w -P F - , - - =
--og e . * - *-*sy---- y- g -_.t-y-,--e- & w
203 The main fuel assembly cans consist of perforated 0.028-in.
stainless steel enclosures each with four speu:cr gr W _pance Lo(10_ inch centers. Tne spacer grids are velded +,o the enclosure in p rallel planes perpendicular to the length of the assembly. The grids are 'omed by ;
brazing straps which are interlocked in the manner of an egg crate. The i straps tee provided with fingers which project above the egg crate and are bent to fom spring clips. The fuel rods are assembled by inserting them through the grids and are given radial supportthrough the individual spring clips. Tne fuel rods are free to expand axially without restraint and thus themal boving cf the fuel assembly is prevented.
Nozzles at both ends of the assembly position the assemblies in the core support plates. The nozzles on the active assemblies serve as coolant inlet and discharge ports. The nozzles of the du=mies are blocked off so that nearly all the coolant flows to the active core. The top nozzles are machined to provide engagement surfaces for the handling tool.
The end plates of the nozzles retain the fuel rods within the can. The end plates are perforated with holes located and sized so as to produce the necessary pressure drop and flow distribution of the coolant.
3 Special Removable Fuel Rod Assemblies Two holes on the sides opposite the recessed corners (one in each side) are provided in the nozzle end plates of the main fuel assemblies for insertion or removal of two special fuel rods or instrument probes.
The special removable fuel rods differ from the other rods in the fuel assembly only in the configuration of the end plugs. The top end plug is shaped to accept a handling tool and serves as a stop to prevent the fuel rod from falling through the fuel assembly. (The instrument probe must pass through both nozzle end plates. ) The top core support plate prevents the special fuel rod from moving upward and out of the fuel assembly. Where an instrument probe is required, the special fuel rods are removed and the
- instrument prot 2 is inserted.
4 Special 3 x 3 Removable Subassemblies The center 3 x 3 removable ' subassembly is similar in cor.struction to the main fuel assemblies ~ept that the enclosure is 0.020-inch thick perfo-
- rated stainless steel and t% 2el rods are spaced on a 0 535 pitch. On asse:nbly of the 3 x 3 into the 63 fuel rod assembly, the end caps of the 3 x 3 are consistent with the surrounding nozzle end plates so that the coolant encouters a flow path identical to that which it encounters in a 72 fuel rod assembly.
5 Special L-Shaved Subassemblies
- The L-shaped assembly in composed of 9 fuel rods spaced on a 0 580--
inch pitch. The pitch is maintained along the length of the assembly by five parallel rows of fomed tubular ferrules brazed to adjacent fuel rods. As the f na:4e implies, its cross sectional shape is an L of two equal legs. The top and bottom of the brazed assembly are velded to two L brackets. The bottom L bracket has a pin velded on an extension so that the pin fits into.a nozzle plate hole. The top is identical except that the pin is replaced by a special screw. Thus, the L assembly fits into a fuel assembly recess and is clamped
.gg over th end plates so that the combination forms a- square fuel assembly of
~N
- / y 203
, g.
~
E* *
,- rods. 'the L asse:atly can only be installed manually; bovever, as
[h ph
.' 9. -
/
'b} ( m y net unis is in ,
r special screw at the top permits remote renoval while
.1 storage rack.
Q_
' d'
" c upport Structure
- 1. General D9 t tien
,Q The reactor core support consists of an upr r and lover core W)?%if suppnrt plate, an upper and J over core support barrel, a braffle structvre and nine control rod shroud tubes c.ircumferentially tie-rod-clamped between the lover core support plate and bottces core support spider..
4 The entire core support ccructure rests as an integral unit on the support ledge of the vessel and is restrained by the compressive load ths.t is applied to the top radial toothed flange by the vessel head.
The teeth on the f. unge act as centilever sprin6s whf ch are desi5ned to have a greater forc 2an that vbich resulta from the pressure differential 3
across the core. Four guide pins integral with the structure assembly orient it to the vessel. Tne arrangnent of the core support structure is shown on
- Figures 203-3 and 203-4#
The major functions of the core cupport retructure are to support the core weight, naintain the orientation of the fael assemblies and the control todo, and to provid2 +.he circuit channe 9 for the coo 1 Ant flow.
i
- 2. Core Support Plates Tne upper and lover cove support plates each contain the same pr2ttern str.d hole size for orienting the 32 fuel assembly nozzles. (Twenty-one are f or the active fuel assemblies and the remaining are for via 11 dummy fucl assemblies. ) Similarl , each conte 4s o nffact erucii'orm slots ,
for the control rods. Since or/y 6 control rode are necesse.ry 1'or this core, the remaining three c lots are plugged with reytely removt.cle plugs. Tb slots 11 the upper core support plate are larger in area than those in the lover core support plate. "'hese larger slots with additional perforations present more ccclant flov area and less pressure drop for the higher temperature exit water. Since the lover core support plate must support part of the core weigat, its thickness ..
inch versus a 1 inch thickress for the upper ,
y; core support plate. Safety-A.sek bolted and develed control rod guide blocks ,
are an integ-al part of each w e plate. The guide blocks are mounted
( aro"nd the fuel nozzle holer in he core plates. T:tose on the bottom core plate have attach?.1 shrouds 5.ich fom a square channel for th .*uel asse=tly :,.colant entry.
3 Core Support Barrels The upper core support br rrel supports tLe upper core support plate and- hangs fram the top of the lover core support barM1 bupporting flange. The inside of the upper core barrel provides space for the instru-g mentation frame and the abscrber section of the c antrol rods when the fuel follover sections are in the car at. The top flange is an externally open
- ooth-gu.sse t.ed rirg;. The open tpaces between the teeth provide the coolant 11cv area into the spue between the upper core supper;. barrel O.D. and the
'.over core support barrel I.D.
1/13/61 .
- Figure 2034 also shows the in core insi.rumentation vLich is distmed in Subsection h0h.
203.!
Aside frcra being the main structural support member, the lover core support barrel with the attached baffle separate the vessel P .et flov frcra the outlet. Tne lover core support barrel is oriented within the vessel so that its two outlet no:cles are alir:ed with those in the vessel.
- h. Baffle Structure and Support Spider e
The baf"h structure, safety-lock bolted and doveled to the bottcc flange of the - er core support barrel, is a form fitting enclosure of 4 the reactor core which ccnfines the upward coolant flov vithin the fuel bearing zone. Eight ax'el parallel pipes velded between the top and bottcra flanges to the outer ba cle valls serve as irradiation sample locations as well as structural baffle wil reinforcements to 'rithstand the hydraulic pressure differential. Gussets velded at strategic positions serve as additional vall reinforcements.
The lover core support plate of tne lower core support aesembly is safety-lock bolted and develed to the baffle lover flange. The cast support spider of t- ) assembly is the main core load support member. Part of the core veight is transferred frcn the partially flexible core plate through the shroud tubes to the spider. The eight tie rods serve as' tension load transfer n.mbers to the baffle structm. To limit the upward travel of the control rod dr!ve mechanism shaft,1nternr1 stops are provided in the shroud tubes for the stop shoulder of the control rod connection.
D. Centrol Rods and Drive Mechanisms
- 1. Control Rods
- a. General Description As was previously noted, the cross-sectional shape of the control rod is an offset cruciform which readily passes through the recesses of two adjacent fuel assemblies. it is composed of two assemblies, and absorber or top assembly and a fuel follover or bottom ansembly, which total a 99-inch length and are locked together by a T spring-loaced joint and a fixed o
center alignment pin. The control rod is shown oh Figurm 203-Sa and 203-5b.
- a. Absorber Assemoly Tne absorber, or top assembly, is composed of three main pieces riveted together.
The topnost section is the stainless steel leader, part of which always projects above the upper core plate. The projection is machined as an inverted cutavay T vhich-provides engagement surfaces for the same handling wool used on the fuel ascamblies. .
The center portion is the silver-indium-cadmium elloy ~
(80% Ag, 15% in, 5% cd) absorber section whi c h is ii prix 1Eity with the fuel in the core when the control rod is fully s.:re=med. Both sides of the blades ner.r their outside edges are groove -machined along the length to accept 9/16-inch vide by 1/16-inch thick stainless steel rubbing straps which serve as the rubbirg surfaces on the guide blocks mounted to the core support
,ates. To increase the corrosion resistance, th" absorber section is
< f nickel plated to a 0 5 mil thickness. It is subt,;quently heat treated to
~
diffusion bond the piaMiis T6 the base ally, to anneal the Ag-In-Cd to give maximum creep strength, and to stress relieve the materials.
\.3
[ /10/61 ,
_ _ . _ - . - - - - - - - - - - - - - - - - - - - - - - ^ ' ' - - ' ^ ~ " ' ~ ~ ' ' ^ ' ~ " " ' ^ ~ ^ '
. 203 6 The bottom portion of the absorber assembly is an inverted stainless steel T vith a countersunk hole on the centerline to fom the male portion of the joint between the absorter assembly Lnd the fuel fonover assembly.
- c. Fuel Follover Assembly The fuel follover portion of the control rods are made up of stainless-clad fuel rods so as to minimize flux peaking when the absorber portion is withdrawn from the core. This fuel follover or bottom assembly. is co= posed of three main sections velded together. The pre-operational devel3 ment vork ascociated with this assembly is described in Sthction LO5.
The top of this assembly is a Type 304 stainless steel cutavay inverted T which provides a close fit for the bottom absorber end.
A conical pin is velded on the centerl M of the' cutout to mate closely with its counterpart's countersunk hole. An elongated C-shaped Inconel-X spring is rivet assembled vith a keeper in a center alot cut into the top of each ,4 blade. Each spring ia positioned with the cvrve of the C toward the outside {h;h edge of the blade. A raised porticn of the open end top am of the spring is Qd an inverted V shape which protrudes approximately 0.045 in. above the top end of the control rod blade. The bottom r16ht hand cdge of the absorber spring mating surface is a tapered lead. Tne center of the mat'ag blade end is V-grooved to accept the spring projection. Thus, the two a.semblies are aligned by mating the conical pin and recessed hohe. The fuel fonover assembly is held while a right-haad 40 pound foot torque is exerted near the joint on the absorber section until a built-in stop is reached t.nd thus the two assemblies j-are ali6ned and locked together.
The center portion is the fuel bearing follover rods. These are made in three compartment secti6ns with stainless steel pl va velded t i the 0.022-in'. thick wall cladding at intervals of apprnximately 12-1/8 inches.
Each compartment separator plug has a small hole d2ined through its length to equalize the fission 6as pressure throu6 bout the length of the fuel rod.
Grooves on the outside of the separator plugs are Nachined to accept cruciform-shaped tie straps. Fuel rods are slid into the slotted tie straps and spaced en a 0 578 in. pitch and fusion or resistance velded together. Thus, an offset crucifom of 18 fuel fnnover rods is fomed.
The bottom of the follover assembly is an offret crucifom
. Type 304 stainless steel section with a centerline hole bored up from the bottom to accept the plug of the control rod drive shaft connection. In the proximity of the cored hole, each blade is slotted to accept a latching ,
finger. The plug is composed of two separating camed surfaces which maintain ,
a locked position on the latches so that the control rod is fimly connected 5 to tM Nive mechanism ior all but approximately the last nine inches of scram travel. Thw in the funy scrammed position, the con;;rol rod is unlatched
(
from the drive shaft and can be removed when the situation demands i.his operat'.on.
The positive connection in any position above the last utne sches of travel insures the use of the drive mechanisLi as a pulling device in evcnt of a stuck contro~ rod.
- 2. Cc itrol, Rod Drive Mechanisms
- a. Function The control rod drive mechanism! provide the motive power
.. . ._ . . - _. . =.
203.t for moving the control rods as required for regulating reactor power. The o mechanisms also provide a signal for determining the position of each rod.
- b. General Description The control rod drives are Westinghouse friction grip macetic jack type mechanisms. In this type of mecharism, magnetic fields established by operating coils outside the pressure housing exert forces on the pole pieces and drive rod bundle .inside the housing to hold and move the control rod. The general arrangement of the operation section of the mechanism is shown on Figure 203-6.
b/5/61
203.'
Tne following is a description of a typical lift cycle of the mechanism:
(1) The movesble gripper coils are energized causing the drive rod bundle to expand magnetically against the bore of the moveable gripper pole. The magnetic force exerted by the rods on the pole nultiplied by the coeificient of friction between rods and pole represents the gripping capacity of the mechanism.
(2) The lift coil du energized raising the moveable gripper pole, along with the drive rod bundle, upward until stopped by
. contact with the bottom of the stationary gripper pole. The strokelengthisapproximately1/8ofaninch.
(3) The stationary gripper coils are energized cc.using the drive rod bundle to expand magnetically against the bore of the stationary gripter pole.
(4) The moveable grippar coils are de-energized allowing the drive rod bundle 'to contract in the bore of the moveable gripper pole thus lesving the drive rod bundle held by the sti/ionary gripper pole. /
(5) The lift coil is de-energized and the pull down coil is energ$ zed to p'ill the moveable gripper down against the top of the puli down pole ready for the next stroke, k An auxiliary dash pot is incorporated in the lover end of the mechanicm rod travel housing to assist the main shock absorber located in the reactor vessel bottom head adapter.
- c. Design Basg The pressure cor,+r.ining shell of the mechanism is d: signed and fabricated in accordance with the recommendations' of the ASME Boiler and Pressure [
Vessel Code, Section 1, Power Boiler, Special R,. lings 1270N,1273N and 1274N, and bears a Pennsylvania Special Number.
Upon loss of power or in the event of a scram all coils are de-energized, allowing the-drive rod bundle to contract and fall freely by th effect of gre.vity only. Release of the drive rod bundle vill occur within a maximum of 0.150 seconds following interruption of the c'; rent to the operating coils.
e The design parameters are given in Table 203-1, telow.
TABLd 203 '
ROD DRIVE MECHANISMS DESIGN PARAMETERS Normal length of travel, in. 40 Maximum le:.gth of travel, in. 42
(. Design pressure, psig 2500 Design temperature, OF 650 Normal load attacited to drive shaft, lbs. 125 s Maximm load on anye shaft, lbs. 250 2/1/61
203 6 Operating.: peed,in./ min.
Increment of movement, in. 1}/8 1
Operat!ng coil voltage, DC 125 ~+ 10%
Position indicating coil voltage, 60 cycle, AC 230 E. Reactor Physics Calculations In the nuclent design of the Saxton core, a multigroup diffusion theory technique has been employed to compute the neutron tuultiplication, The basic assumption of this technique is the separability of the energy and spatial dependence of the neutron p<.pulation within a multiplying region.
- 1. Fast Neutron Constants Fev group constants are obtained for nonthemal neutrons from the 54 group IBM-704 spectral code MUFT/1. For a given homogeneous mixture of infinite extent, this code computes the spectrum of neutrona from the energy of fission down to the themal cut-off which is usually selected to be 0.625 ev.
The effects of leakage on the neutron spectrum are approximated by the inclusion of a geometric buckling. From this spectrum, neutron-flux-averaged crc.,s sections are obthined for as many as three fast groups which can later be used in neutron spatial distribution calculations. '
For nonthemal neutrons, the effect of heterogeneity is negligible in a light water moderated lattice except for the occurrence of absorption resonance bearing materials. The principle contributors to resonance absorption are U-238 and U-235 although the structural material of the *:re does contribute I
LJpreci. J .
The MUFT code does contain all the important resonance parameters sind, h r nomogeneous mixtures, computes the proper absorption rate. The
.nly account which can be taken by the MUFT code of heterogeneity effect of m onance absorption is through the inclusion of an L factor which is analogous to a dicadvantage factor $n themal utilization calculations. This factor is an input constant and must be detemined by some means external to the MUFT calculation.
WAPD has modified the MUFT code se that an input parameter a) could be used. u)is the ratio of resonance absorptions in a given material to the neutron themalizations in a mixture containing that material. The modified fom of MUFF thus searches for the value of L which vill reproduce this rc.tio. _
The input value of a) for U-238 absorption is obtained from a semi-e=pirical hand calculation of the resonance escape probability in U-238 which is in good agreement vith Monte Carlo calculations.
~
For all other resonance absorbing materia.1 3 in the core, the value of the L factor is taken uo be unity.
- 2. Themt.1 Neutron Constants The themal neutron spectrum (E<D 625 ev) is obtained by the IIM-704 code SOFOCATE /2 vhich obtains a solution to the slowing dcyn equation.
I for a hydrogen gas in the presence of absorbing materials. In this a nner, the hardening of the spectrum in the presence of heavy absorption is considered.
Neutron-flux-averaged cross sections are obtained from this spectrum. Although
</13/61 .
-g e -
= - w m- , - . ,- ,,,_e.- m
203.-
the model based upon a hydrogen gas does not appear to represent the situation in a reactor sys tem, comparison of neutron spectra by this cceputation with
{
experiment /l irdicates that little error "esults from this simplified approach.
The SOFOCATE code detemines the spectrum for a homogeneous mixture.
Because the effects of heterogeneity are important in the themal group, a correction for the effects of heterogeneity is obtained by flux veighting the' material number densities which are used a* input to SOFOCATE. The flux veighting is based upon a method developed by Amouyal and Benoist /h which agrees well with experiment.
3 spatial Distribution The fev-group constants which have been obta?ned by the spectral codes are used in one and two dimensional, diffusion theo>y, distribution computer codes. These are WANDA /9 and FDQ /6 , respectively. An integral part of this calcu]ation is the detemination of the neutron multiplication.
- h. Effective Neutron Multi 211 cation The effective neutron multiplication can be obtained by means of a fev-group hand calculation for simple geometries and uniform loading. In tvc groups D2 B +E k= A k
o Dy B+Eg+E Y = neutrons per fission f =
g macroscopic fission cross section (cm~1) 1 7
A = macroscopic absorption cross section ( ~
r = macroscopicremovalcrosssection(cm~gm-) )
l S D = diffusion coefficient h B2 = geom ric buckling
- 1,2 = refer ;o fast and slow group, respectiv?ly.*
If a nonunifom loaddr ? or a ccep .icated geometry is considered, l this analysis is not adequate and af wh distribution codes must be used.
t
- In the case of control rod vorths, for the Saxton core, a two dimensional analysis (PDQ) is necertary because of the trucifom shape of the rods. .
Beron poison vorths are obtained by inserting the boron into the MUFT and SOFOCATE calculation. Usually the hand calculated multiplication is adequate.
f The multiplicati n obtained by the hand calculation as well as the t computer distribution calculation is the static multiplication. That is, it is the numberical value which must be divided into the number of neutrons produced per fission (9) in order to make the system critical. '
( :/1/01
203 2 5 Comparison vith Experiment A detailed ecmparison of the computation techniques with experiment has been perfomed by W. H. Arnold, Jr. /7 In the 2eference of Dr. Arnold's, a more complete deceription of the computational methods is given. In general ,
it is indicated that a high degree of reliability can be associated with the design procedures which have been developed at WAPD.
The comparisons given by Dr. Arnold are for relatively simple geometric configurations. A ecnparison with measurements of the completed ER-3 core in which crucifom rods are used has been perfomed by H. W. Graves, Jr. and P. W. Davison /8 . This reactor is quite sir.ilar to the Saxton cora and illustrates the ability to compute reactivity effects in a complicated geometry. In general, the comparisons are quite good.
- 6. Reactivity Coefficients Reactivity coefficients have been computed by selecting two points with a small finite d.tfference in the parameter of interest and performing a neutron multiplication computation for each. The reactivity s. Icient is obtained from the difference in neutron multiplication as obtained.
The effects of plutoniu:2, xenon, samarium, and poison control are evaluated by including these in the calculation ?f neutron multiplication.
- a. Moderator Temperature Coefficient The moderator cogfricient was obtained by computing the multiplication at a temperature 50 F above and below the operating temperature,
- b. Moderator Pressure Coefficient The pressure coefficient is based upon a computation of the multiplicatien as a ft.netion of moderator densities which differ by five percent.
From this, a density coefficient of reactivity is obtained. A pressure coefficient of density at operating conditions is used along with density coefficient of reactivity to obtain the pressure coefficient of reactivity.
- c. Moderator Void Coeffici'ent The void coefficient is obtained directly from the moderacor density coefficient of reactivity.
- d. Power Level Coefficient The power coefficient of reactivj cy is a consequence of the broadening of the absorption resonances in U-238 as a function of fuel temperature.
This broadening has been ec=puted by W. H. Arnold, Jr. and R. A. Da:ulels $_
and agrees closely with valueu which have been measured by E. He11 strand /10 .
Tne change in fuel temperature with power level is then used to detemine the power coefC,:1ent, f
]1/61 y g = -
y, + gy -f..y , rr -=w
203 1.
7 Core Lifetime The calculation of the core lifetime is detemined by the one dimensior,al burnup fuel-depletion code CANDLE /11. The fue) nuclear charac-teristics as a function of burnup are detemined to be used in reactivity coefficient computations.
F. Core Characteristics The reactor core is nominally designed to provide 20 Mvt heat output.
0 0 Atthisheatoutput,thecoolangentersat520 F, and 1: aves at 540 F, and flows at a rate of 2.8 x 10 lbs/hr. The minimum ratio of burnout to computed actual heat flux at any point $', 2.4 The nomir.al design generationperunitlengthoffuelatthehottestspot,is133kv/ power ft .
\
which is safely below the accepted safe operating limit of 171 kv/ft. The first reactor core is desi6ned to have a lifetime of approximately 2} years of 20 My operatic.n with a 50% load factor. Sufficient excess reactivity at the end of core life is provided to compensate for voids, poisoning, increased power density, and increased average ' temperature, as may be introduced by the experimental program. The pertinent physical, thenaal, hydraulic, and nuclear characteristics of the core operating at a power level of 20 Mvt are listed in '
Table 203-2, below.
TABLE 203-2 CORE MRISTICS
\
Total heat output, Hv ?'s-Totalheatoutput, Btu /hr. 6.83 x 107 Coolant Flow:
Totalrate,lbs/hr. 2.8 x 106 Heat transfer rate, lbs/hr.
2 2 52 x 10 6 Area in fuel rod cross section, ft 2 75 Velocityalongfuelrods,ft/sec. 5 32 Pressure: -
System pressure, nomal operating, psia 2000 + 50 Reacter pressure drop, psi 15 Cc:. pressure drop, psi 65
- Heat Transfer
l " Active" surface crea, 2 498 Averageflux, Btu /hr-ft{t 137,000 Maximumflux, Btu /hr-ft2 444,000 AnIMefilmcoefficient, Btu /hr-ft.0F 2 2400 Bumout (DNB) flux by Bettis Correlation, Btu /hr-ft2 1,030,000 l
DNB ratio 2.4 Power densities: Kv/litercoolant ~ 83 Kv/ liter,Qre 54
, Hot Channel Factors:
Heat flux 3 24 l
Coolant rise 2 30 Temperatures, OF:
Average coolant in vessel 530 i{
Average coolant in core 531 Average coolant risp in core 22 l
Average coolant rise in vessel 20 l/6/61 r .
203 Average film drop 514 thximum surface (at nominal system pressure) 642 Outlet of hot channel 570 Inlet to vessel 520 Outlet from vessel 540 Fuel Rod:
Outside diameter, in. 0 391 Tube vall thickneen, in. 0.015 Pellet diameter, in. 0 357 Pellet length, in. 0 732 o Number per cross section 1569*
Fuel length per rod, in. 36.6. 7 Rod lattice, in. 0 580 (
Equivalent diameter of unit cell, ft. 0.05' r Rods per assembly 72 Rovs per assembly 9 Total number of fuel assemblies ?.1 Control Rods: '
Number of slots in 21-assembly core 6 Center-to-center distance, in. , 7 6622 ,
Span, in. 5 616 Thickness, in. 0 3925 Fuel rods in follower:
Outside diameter, in. 0.40)
Cap, in. 0. 00!+
Clad thickness, in. 0.022 i
Pellet diameter, in. 0 357 Fuel length per rod (pellet stack), in. 36.6 Rods per follover . 18 Total rods per six followers 108 Control Characteristics: (Calculated)
Keff cold and clean. 1.250 Keff, hot and clean 1.168 Keff, full power & equilibrium Xe and Sm -
1 . 1 21i .
Average negative terperature coefficient, (FO)-1 See Subsection 503 Contro'. re.d worth, f (Average) II Boron Conce7 rd wons: (Calculated)
Coldsh" clown (k-097 -2700 Hot shutdown (k-0 97)), no rods, ppm 2>00
, Delayed neutron fraction, %,.no, rods, Mn 0.63 ,,5 Promptneutronlifegime,sec. 1.6 x 10 Total core area, ft -43 Equivalent core diameter, ft. 2.35 Maximum core diameter, ft. 2.64 Length to diameter'(equivalent)' ratio' of core 13 Water to uranium ratio (unit cell) 4.6 -
Water to uranium ratio, actual 5'. 0 .
Weight.of UO2 : ~
> Fuel assemblies, lb. 2092 Control rod follove.r, lb. 136
(' Initial conversion ratio (Calculated) 'O.31 Initialenrichment,vt% .57 Full power lifetime, hr. 7800 Avenge uischarge burnup, MWD /MIU' 7300
- Includes 81 rods in 9 stationary L-stiaped subasskblics' and elite 23 rods removed for flux vire thimbloa'.
4/6/61-R
203 4
- 0. Nuclear Instrumentation and Control
- 1. General Control Characteristics The excese reactivity of the core cold and clean vill be controlled by both neutron absorbing control rcos and a soluble neutron poison, boric acid. At power, the control rods alone vill maintain criticality and provide sufficient vorth to scram the reactor. The soluble poisen con-centration vill be controlled by the chemical addition and purification systems.
l In designing the initial core, the design and experimental infcr-mation which was developed for both the Yankee and Belgian Thennal Reactois was utilized to the fullest extent. Both of these reactors have stainless steel clad, UO2 rol type colts and control their excess reactivity by a ecubination of neutron absorbing control rods and a soluble neutron poison, bc,ric acid. Experiments conducted by the Yankee Project and the Saxton Project indicate that boric acid solution has good themal stability and adequate solubility when the temperature and concentration are controlled Thus, it is j expected that hideout, plateout, and crystallization of the boric acid chemical
, neutron absorber vill not be a problem. ~ ~ ~ ~
i l
The basic design philosophy for reactivity control is to shut the reactvr down by at least 2% A K vith the most effective control rod stuck in a
- partially (preset) vithdrawn position.* When the reactor is cold and clean, the control rods vill not have sufficient reactivity vorth and a solable neutron poison munt be injected into the main coo] ant loop. Boric acid which vill be used for this purpose vill be ztmoved frcn the main coolant by a biced and feed system and a final clean up demineralizer after the coolant is up to operating temperature.
The kerr in the clean, cold condition is equs' to 1.250 and decreases to 1.168 in the hot, clean conLtion due primarily to the decrease in water density and the corresponding d.-creases in water to uranium ratio.
In the clean, hot condition at power, kerf is further reduced by approximately I l-2% because of the uranium Doppler coefficient. The lovest initial keft of the core corresponds to operation at tbperature end full power vith equilibrium Xe and Sm poisons anti is approximately.1.124. The equilibrium Xe concentration is reached within the relatively short period of apprrwwtely one day and Sm equilibrium concentration is reached in four to six weeks. The core is designed so that the mechanical control provided by the six control rods is sufficient to control the res.ctor in the hot, clean l condition. The initial reactor core has a design zwactivity lifetime of 7800 full Iser hours. This corresponds to an average fsel burnup of 7300 MWD / tonne. It in expected that the initial conversion ratio is 0 31. The I
1 initial enrichment is 5 7%.
- 2. Nuclear Instru=entation System
- a. Function i
The nuclear insuunentation system is pravided for the g pse of giving continuous information of reactor pcnter level conditions l .
cs related to neutron flux level frcn startup through the useful pcnter range i of operation. The system also initiates reactor shutdown signals if limits are exceeded.
- A circuit, which vill work in conjunction with rod position indicator coils, 4/7/61 is being designed and vill be provided to give an adjustable rod withdrawal 1i limit stop.
. 203..
- b. General Description 7 The system consists of startup and power range equipent as shown on Figure 203-7 The startup equipment is made up of dual sets of source level and intemediate level channels, while the power range equipent has three identical power level chauels.
All the equipent with the exception of the detectors is located in the control room; no pre-amplifiers are used at the detector locations. The detectors, each in a' separate sulnersible container, are located outside the reactor vessel support structiire~in' the storage vell water.
The container assemblies are placed in brackets that are attached to the support structure. One spare bracket is provided for the possible future addition of experimental instrumentation. The brackets are-made so the center line of the detectors can be positioned anywhere from 50 inches to 68 inches 1 out from the pressure-vessel center line and also raised or lovered 6 inches I from the reactor core horizontal center line.
The equipent located in the control room is housed in tvo equipent racks with the exception of several control board and desk-mounted meters, recorders and switches.
- c. Components (1) Startup Source Range Channels - NI-l and NI-2 Each startup source range channel consists of-a BF3 proportional counter, a pulse integrator. chassis, a lo6 nicroammeter, a level indicator, and associated lov voltage and high voltage power supplies connected to a ecumon source range startyp rate indicator and level recorder by means of channel selector switches.- A control desk mounted high voltage disconnect switch is provided to manually remove the high voltage fra:n the source range BF ""t*#" "h*" th' "*"t" "'l*V*1 ** "h V' th*i" #*"8
3 (2) Startup Intemediate Range. Channels -- NI-3 aad NI h Each startup. intemediate ra'nge channel' consists of r.
compensated ion chamber, a log microammeter, a level indicator and associated lov voltage power supply connected to a cocanon intemediate range scartup rate: indicator and level recorder by means M channel selector switches.
-(3) Startup' Range Auxiliary Equiinnent
- a. Bistable Panel - NC-1 This circuit' receives startup rate' signals frart both intercediate range ...og microammeters and supplies a rod'stop sigan1,to -
the reactor control system in tka event a fast rate of change of zwactor power exists. Tnis rod stop Mpal is adjustable between 15 and 8 decades per minute. In addition, tnt rod stop signal is_ backed up by separate- scram '
i signals to the reactor control systcm scram circuits. This back-up is _..
acccumplished by adjustable t. rip (15 to 8 decades per minute and set higher
-( than the rod stop sign 6 0 hastabic magnetie amplifiers. The panel provides separate signals to the plant alam annunciators _to_ indi: ate the -rod stop condition or scram due so fast startup rate and the _ channel involved.
'13/61' ,
-. --. - .- ~ . . . - - . . . _ . - - _ . - - . . , - - . - - -. . -
203 2
- b. Startup Rate Disconnect Panel - Part of NC-1 This panei disables the fast startup rate scram and rod stop signals above.10% pover.
- c. Startup Test Panels - NC-2A and NC-2B Two startup test panels are provided, one for source and intemediate range channel "A" and the other for channel "B". These panels provide for local indication and test circuitry for the startup egrj pent in the equipment racks. A panel vill pemit a complete calibration check ci tne asso:1ated channels.
(h) Power Rcnge Channels - NI-5, in-6, and NI-7 Each power range channel consists of an uncompensated ion chamber, a power range amplifier, and a level indicator connected to a co::non power range level recorder by means of a selector switch.
(5) Pover Range Auxiliary Equipment ,
- a. Coincidence Protection Circuit - NC-3 This circuit receives the three power range trip signals as inputs. The circuit is so arranged that coincidence must exist between any two inputs in order for the circuit to have an output. .The output of the circuit is fed to the reactor control system scram circuit.
I This coincidence feature is used to eliminate unnecessary shutdown caused by a faulty channel.
A switch is provided in one of the equipment racks for single channel shutdown so that coincidence is not required if one channel, for some reason, is out of service. The coincidence circuit also provides signals to the plant alam annunciator to indicate the channel or channels initiatin6 a trip cignal. -
(6) Fquipmcy, Su: mary The function, range, and sensitivity of the nuclear instrumentation system detectors is listed in Table 203-3, below.
TABLE 203-3 SUM!ARY SPECIFICATIONS - NUCLEAR INSTRUMENTS
, . Channel Function Sensitivity _Ra g NI-1,2 Startup, source range h0 co 2 5x10-2 2 to 2 5x1 4x10 gts/ rec nv
/nv v NI-3,h Startup, intemediate range amps 2 5x10 to 2 5x1 v 3x10-13 amps r hr i NI-5,6,7- Power range amps nv 2 5720* to 2 5x1010nv 4.1+x1{14 5x10- amps /r/hr
/1/61
203
- d. Design Basis The system is designed to cover the complete range of reactor operation from source levg through 150% power. Because the upper level.of the startup range is about lo; times as great as source level, a single startup range requires two overlapping channels; these are the source and intermediate level channels. A power range channel, as implied, covers the useful rance of reactor power op ation. Multiple chennels are used in each range to further increase reliability and reduce the probability of operation with erroneous information. Metering and test circuity are provided for calibration and trip point adjustments. To reduce the flux to within the operationt.1 limits of the BF, proportional counters10_ (y/hr),
r .1.J inch.es of radial lead is placed ardund each of the two source range . detectors. The design parametera are listed ir Table 203-4, below.
TABLE 203-4 DESIGN PARAMdTERS - NUCLEAR INSTRUMENTATION SYSTEM Neutron Flux * '
Average,-nv 9 4 x 109 Mnv4 = m , nv 6.i x 1010 Minimum, nv 5 0 x 109 Gamma Flux * 'y Maximum,r/hr 4 9 x 10 5-Meximum Storage Well Water t Temperature, OF 130 i
\ ,
l
- Flux values given tre for the reactor _operatirg at 20 Hvt and at a j_ distance of 50. inches fra the reactor vessel center line. The reactor core is approx $mately 2 7 incheL off center with respect to the reactor-vessel.
- 3. Reactor Contral System ,
- a. Funetion The_ reactor control system provides the.means for regulating reactor power manually or autcunatically and .affecting reactor scram in the event operational limits are exceeded. Reactor power is controlled-by-.
-maiata$ning a constant Tavg (the aversge of. the main coolant loop hot and cold leg te=peraturea).
l
- b. Generel Description The system consists of six control rod drive mechanisms (previously described - see subsection 303-D2), a scram circuit, two scram -
amplifiers, two scram circuit breakers, a manualE control circuit, an automatic-
,. control circuit, a mechanism cycling circuit and a rod position' indication
- o circuit. The system is shovn-in block diagram form on Figure'203-8.
1 t
! /13/61 k .
I a --;,.-.-_. . - - ,.-....-.a..~.~.--,-~~..-~~.-----,- >-.~ -
203 1
- c. Components (1) Scram Circuit The scram circuit receives input signals frce the various plant instrumentation systems. Several of these signals are in the fom of bistable magnetic amplifier outputs while others are in the fom of contact operation. Upon receivin5 an input signal the scram circuit acts to cause the scra= nmplifiers to trip the scram (control rod drive mechanicm supply) circuit brenkers.
(2) Scram Amplifier A scram amplifier consists of a bis +able ma6netic amplifier with sufficient output capacity to directly control a circuit breaker. Two scram smplifiers are used and they receive duplicate scram signals from the scram circuit. The output of each amplifier is fed to an undervoltage trip coil of a scram circuit breaker. Upon receiving an input scram signal (energize to scram) the amplifier output is de-ener61ted thus tripping the circuit breaker. " Energize to scram" is required by the scram amplifiers. That is, an input signal must be present in the fom of either an output of a magnetic amplifier or a closed contact. Upon loss of control power, however, the output of the scram amplifiers vill N de-energized resulting in serem.
The output of each scram amplifier affects one of two circuit breakers; the main contacts of both breakers are connected in series.
i Scram is accomplished by interrupting the mechanism power supply by either.
breaker, thus insuring a scram in the event of failure of one scram amplifier or circuit breaker.
(3) Seram Circuit Breakers The main contacts of these breakers are connected in series such that open!ng either breaker vill interrupt the power supply to the control rod drive mechanisms, causing scram. The' breakers are equipped with mdervoltage trip coils independent of the nomal trip coil circuit. These ndarvoltage or scram coils are controlled by the scram amplifiers. Manual se_ ram and loss of main coolanty:m,pover, vill operate the brnaker trip coil circuits directly.
(4) Manual Control Circuit This circuit is made up of control svitches and relays to enable the operator to select and opezate a control rod or group of control rods.
(5) Automatic Control Circuit This circuit, TEC-5, detects the recctor hot leg and cold les tempereures for detemination of T and supplies an on - off rods "out"or on - oft rods "in" signal to the mecE. ism cycling circuit. The (I set points for rods "out" or "in" si6nals are adjustable over a range of 500 to 6400 F. By positioning the inditidual control rod selector Ovitches the operator can select. any rod or grc,up of rods for automatic control.- Figure o 203 9 1s a red control schematic diagram.
/13/61
203
- (6) Mechanism Cycling Circuit This circuit consists of rheostats, contactors, relays, and a ca
- n svitch assembly. The circuitry is arranged to properly sequence and adjust the level of the DC supply to the individual control rod drf ve mechanism to achieve motion. This circuit receives inputs frca the manual or autcmatic control circuits. The power input to the circuit is through the sort.m circuit breakers.
(7) Rod Position Indication Circuit This circuit consists of indicator coils (primary and secondary transfomer coils) mounted on each control rod drive mechanism. 'the voltage output of a secondary coil is detemined by the mechanism drive shaft position (thus control rod por.ition) within the indicator coil assembly.
Position indication is provided for 42 inches of rod travel plus 2 inches below the bottczn limit of travel. In ortler to obtain a more accurate indication of control rod position, the kh-inch secondary coil assembly is tspped to provide eleven equal coil sections frce which the output voltage of any two adjacent taps can be measured and used similar to a vernier. A sensitive meter relay is ,
connected across the tottcan 4-inch section of each control rod position coil stack. This meter relay is used to actuate an alam upon accidentally dropping i the particular rod. Figure 203-10 is a scheuatic diagram of the rod position indication eireuit.
Cor. trol rod position indications are provided by
( control-board-mounted indicators with one indicator to cover the complete 42-inch travel of each control rod. More accurate control rod position is pro-vided by a single indicator that can be switched to acy 4-inch section of any control rod position coil stack.
(8) Beactor Control Rocan-
- Ccanplete supervision- Qf the nuclear plant is obtained in the nuclear plant contro3 rocan. This - rocan contains vertical control- boards, cabinets, and a control console arranged as shown on Figure 203-11.
Alam lamps, mounted on the control boards vill 1ndicate when any abnormal condition exists or when individual control rods have reached their limit of travel.- All important plant parameters, such as pressure, temperature, coolant flow, and. neutron level, will-also be indicated on the control boards and control' console in clear vision of the reactor operator.
- d. Design Besis
'Ibe system is designed to be operated manually or auto-matically. When on manual control, the control- resds st.y be positiened individually' ,
or in groups. l When on automatic control, a selected control rod or a. 1 selected group of control rods ~ may be positiened autcmatically to maintain _Tayg l
{ at a consta? value. While un autcznatic control with a group of control rods, l
$ an individual rod may be positioned manually. Also, While on auttune. tic control -l vith an individual control rod, a group of control rods may be positioned 1 manually. - l 1
h/7/61 l
203 1'
- A scram circuit is provided to rapidly insert all the control rods regardless of whether the system is being operated manually or automatically. The acram signal car be initiated manually by the operator or automatically by loss of power to the main coolant pump or by signal from the scram circuit. The scram circuit receivea inputs for automatic scram from the various instrumentation and control systems. All scram inputs are listed in Table 203-5, below.
- An all-rods-in circuit is provided to insert all control rods while the system is being operated manually or automatically. The signal is to be initiated and tenrinated manually by the operator.
- o. A rod stop circuit is provided for use during plant
- startup. The circuit vill block the removal or control rods in the event a o fast startup rate exists. The circuit is lacked up by a scram signal.
'i TABLE 203-5 -
1 REACTOR SCRAM SIGNALS _
hst Startup Rate - Channel A NC-1) e Fast Startup Rate - Channel B NC-1)
High Power Level - Channel A NC-3 .
High Power Level -ChannelB(NC-3 High Power Level - Channel C.(NC-3 Lov Main Coolant Pressure (PIC-3,5).
/
Lov Main Coolant'Flov (FRC-1)
\ Lov Water Level in Prescurizer (LIC-2)
Loss of Main Coolant Pump *
, Jiigh Main Coolant Ta.nperature (TRC-2)
Hanual*
- Dir-et t
1 _
- 1. H. Bohl, Jr. E. Gelbard, G. Ryan; " Fast Neutron Spectrum Code for the -
I1H-704," WAPD-TM-72, (1957).
l
- 2. H. J. Amster, R. Suarez, "The Calculation of Thermal Constants Averaged l over a Wigner-Wilkens Flux Spectrum; Description of the SOFOCATE Code,"
l WAPD-TM-39,(1957).
1 3 H. J. 'Amster, "The Wigner-Wilkens Calculated Thermal Neutron , Spectra Compared with Measurements in a Water Moderator," Nuc. Sci. & Eng., 22 394 h04, (1957).
- h. A. Amouyal and P. Benoist, J. Nucl. Eng., 6,79,(1957).
5 O.' Marlove, C. Saalbach, L. Culpepper, D. McCarty, "WANDA - A One-Dimensional Fev Group Diffusion Equation Code for the IIN-704,"
WAPD-TM-8,(1956).
l( .
- 6. G. Bilddeau, W. Cadvell, J. Dorsey, J. Fairey, R. Varga, "PDQ - An IIM-704 Code to Solve the Two-Dimensional Fev Group Neutron Diffusion Equations," WAPD 'D4-70, (1957).
l /6/61 l
y y4.
203 20 7 W. H. Arnold, Jr., " Critical Masces and Lnttice Parameters of H 0-UO2 Critical Experiments: A Comparison of Theory and Experiment," 2 YAEC-152,(1959).
- 8. H. W. Graves, Jr. and P. W. Davison, " Proof Test Critical Experiments for the BR-3," WCAP-1556, (1960).
9 W. H. Arnold, Jr. and R. A. Dannels, "A Monte Carlo Study of the Doppler Effect in UO2 Fuel," WCAP 1572, (1960).
l l 10. E. Hellstrand, P. Bloomberg, and S. Horner, "The Tempo miure Coefficient of the Resonance Integral for Uranium Oxide and Metal," Nuc. Sci. & h 2 Vol. 8, No. 6, pp. 497, (1960).
- 11. O. J. Marlowe and P. A. Ombrellr.ro, " CANDLE - A One-Dimensional Fev-Group Depletion Code for the IBM-704," WAPD-DI-53, (195'T).
t 1
1
(
/1/61 ,
. - . - . - - . . -.. ._ - .- - ..-. - ~ . - - . .. - -. - .. .. - -. .- .- .
/
/^
= '+ n - - - - s
.. . . O.' . . , ,
f . 'N
,'s
/ /
\N s fx
/ h1 / '
[ . o: ?MC m Wq4; ti.\hliX)eg${MMM)()O()(*k) f O- -~
() ~ =_}x~~_. .
f.
'O O g ()_
-0 0 0
.,()
)
}
m O- / D00 - -00 O' O h 00 0 O9 '
s
/ lC :
m f_Z -t.G., i 0
()
..N()()() , q)
,t)() !-
O '(D G: -/- h :-- O @
, O- -4) 6 (' , O, --
'l.? -
gQ _], t E f j -
OGf:Hi.R= m > p O Q joO O G/G. 2-4 .$ '
i)ogeboechusaloowci"
~
T i 1 1 liu y j g_ _ . . . .
_.. (y'- tyfg g) '
p q. g d / g- .
() (3 , -_ _
(p _g
- 2 -()
" 2' -()
!j/ - *00()_.. . __.
s
'i .. _. _,
,() , gO ,j_ . 1
() .... , ,p -
/ II"" .
O,_ _. .._-_ g {)g., _. _
- ()
/ i *
($g wI 7 2 --
$ () .- -
-'h 4
, gQ hd()-- - () () --
-h O O GOD 0,0 O Q l
l
'N ? M1hg{(itGMOGOO eq)c c>gege6 .
t - 4/
h l -N N; _1 .
s-f -
%,. /- : "'
/ . . - - -n ,
/
'N, / %;
s-i I
t
_FIGUKE 203-1 t
- .r-,-,-=,- w #, m s - w . . ,.*e-. rv~w +*w,v.#re, ..>,w.- 3~,-<--,y-. , , +v- -w e- - ,,-e . re- + - - , - . + ,
- 4
> 1 i t' !
Sf.e.*
p
, I
+l, .E,t*!l v f !
5 ll$
! I! hs i
!!!if ao o ; di d nb bb"jl*8
[ g il1,,1Tj 5 i 81
$j t i .;;;,11 ilill r h
,/
.e <" l e g / 5 S' $ et / C
/ ld
%, ~$)
m N
l './ - '--
=""* o l 7.:r- 'k '
j: , sq
/p / p~ ~'h] g ,
g / rn -
. u
-s ,
wy a=_
'1.
l lj!]\_/r,N t i g- N l1 lis % FL' ' kegi% 1
- a ,e .
12.
c.- t' I
- .t e. % tf/ 1
/ / y -l W X M % - J's/ y.:./_ f,/
i g i[ lj f Q / l p -. 2.--.-
- , .s "p
Mkf[iJ %,
s ,/
-s
/
"/
\/
fx
+ t
'N
/ 9^
j.' s
\
"mca . FIG m :203-2 i _g .
REACTOR VESSEL ASSDSLY WITHOUT CORE I?;5"fUMElHATION
$I8,yNDyNbTRUMENTAtl0N g Urtiwo LUGS I,. I*a -s_. --
ll w l REACTOR VESSEL HEAD U 'd
~k 4
' c' ,N (y
I-. [ CLOSURE N UT sutot Pih -, c
-TI i $[ g CLOSURE STUD HEAD CASKETS 3 f LOWER CCRE SUPPORT 8AR REL \
}. )> {p h3 Tj
/
{
[ gUUS ASSEW8LY SUPPORT TUSE CONTROL RCD RAISEC PO$1780N
$ /
s i
UPPER CORE support PL ATE f I CONTROL R00 OUIDE BLOCx INLET [ ! ,
l# ,
(pyyLgt NO22LE -' NorgLE
.g FUEL ASSEW8LY 4: l '
FUEL ASSEMBLY REMOVASLE sWP =SSEMELY h , ,
REACTOR VESSEL BArrLE STRUCTURE h
'~
(m l '
g g .. . ;J " MPPORT SKIRT THERMAL SHIELD ; i@i ij
-- -b e pp gp6clAft0N SPECIMEN SPACE g\ @!:
/
/
s
- !4 cowTROL R00 eviOE eLOCx LDeER CORE SupM4' PLATE TIE R00 -\
{
p REACTOR vtSSEL ht-A ' /4 , SHROUD TUeE CARBON STEEL 9; >
/p'I fl WULTblAYER SHELL % { '
l p g "F QQ ji CONTROL ROD FOLtDWER BOTTOM CORE f SUPPORT SPIDER g: j.,h +
/H,' 1 fA .
CTAINLESS STEEL LAYER
) y' F
ll I
l?h i .
l '.
g'l-l [; d '
11 CONTRot t09 DRIVE SHAFT -
/
I uWil
- g. p!'-
~
eI i r ,
I p[I t - ;4 i ! CONTROL RCD drive
~
WECHANISM ADAPTERS r, Jt & .
I gr 1-l :
i y
t l
l FIGURE 203-3 APR 6 1981
- _ . . . - . - .- _ . = . - . - - .._ . - - . - . . . - - - - .. .
"CCTOR VrSSEL ASSDSLY WITH CORE IMSTRUFENTATION
~1 ~UWER INSTRUWENTATION T POM SEAL ASSEMBLY ACCESS A)OINSTRUWENTAT)
PORT AQAPTERS f, 1 If (d, !- ~. 4..
bs3 SUSAS? EMILY SUPPORT k C s a Q
'& fO' nm:ANENT
& WEASWWENT THW8L .Qb" #_ .
[lN5TRUMENMTION f8SER N _# }
~
3 STER istSTRUMENTATION fN -
SUPPORT FRAME N
' % I k i I'-
\lN
/
PERuANENT INSTRuMEwTATioN l
" s MQN I g
l p#k,[MTUT TUGE PRESSURE
,, s .' A j CX2sNECT10NS
'ig,,
3, A
1 T
.u s co t OUTLET jT1y[
%S THF.RMON TieWLZ
- c LOWER INSTRUMENTAff0N M 4 j( _ . 5%
SUPPORT FRAME _pi n[\ '
f]
i
. ylg/
l co*C ouYLET MYoTTvet a
L - 'W ftERWDCOUPLE N, N 3
'! l 8"T 7 1 vEu. AsStunty
- y. ,-- t p I p s 9"l'
.A
! s A._ - t _
~4 r
Sa3 esSTRVWENTED i H "/ f .
REWonAsLg namammidst I ! :p gl? #E y! ,
Nlil ! C A + UDI j.[!
lj i t N, s . . .
3 -]7 ! O
+l9 +
a ,C_ ORE INLET PfTr .
A,,,..~
~ ~
x l
/ N M MN CORE INLET PN 'fUBE l , i P4ES$URE CONNECTIONS 11 lh / i;[jjj'll 1l!: 8 4 . v i,,,,
o ;
? / . l
\ '
L [ '2 'f.
fl. 1 s l
'u' ,id N
@f fl
-! i
'h l x ! !
u _
u si ,
l .
[
),'
% < v' q sq l - g_;N L: <g: ,' LOWER IM5TRUWENTATION PORT SEAL ASSEW8LY -
i s
i i ,f l
1 i
9 l
l l
1
(
l l
l FIGUFI 203.h l snn ggi
,,. ,. ,,-... ___ _ - .- ,---,..._--, . ,. --. . _ _ . . _ _ - . - - . _, -~:---- - _.
/EddO[iO5$b i ,
1?-mi ?*:t 4 !! '
O..,.t. i _ _
tl, e ' /[
3
[
l .i ' i,p y, *4 . )1 v, a, "v'1l,\
, -3 :
gn
- !ll 8
l l[ '
f,
' _%L_
q pIlL 1, ! . yjj/*x Pu-
!E fj' i : i s ,- t n p jb-d- e-m ,. l $ l,! s-
,llCN. P 1 l '
=rs%'Lq If [ e 1 9 e\ n u jf w
s i j a
%rt %9.P4,
..J 3
u t3 p\ , [y. h"N>.. "
3 p
fx I :A. -4. 4 o -
6T4 -
P G -e i f, ,.7 1 __
e .- -
u...
ll _.o
=
\ll;- ii a i .h: !' S t t e j! }yd $ L , ., ,
il l Ift __. _Jli i
__ II
,,2 M
l! h !! jI h q $}!j; l- - +
ajj) !E @
i l
g\(@ A6 N _.1
- !l
_j._ jj'f ! @
w =
- . =
3 ,
(
Q . EN ll 3.h4 g l d
.! \m!$ !!'j a
->}l ,j ,3 u e
. .. pi 3 N -
Q efa ;j rf h qp+Ls+
[jn g+ +-}e' h 9
% ~ ,cs : i. -
)
9 f,\ BQ )
,13 8 1 M
![) I\ x. ); 2 i j i
l /
w]
hyN'g
.g t In ll 0 1s W \\
\
5 1 i
- l W 1 -q3 s,,, l ++-+- I -_ vt l *3 l
c t
FIGURE 203-5a
._ . ___;__... . _ _ . _ . . ~ . _ . _ _ _ _ . - . _ . . _ _ __ _.,_. _,--
,i
-N m
\'}
ilkMNdiU3M Vf h. d,.
hurr@yv- iilijl d /~ , pp s m ! a.)
Mp &
it l i :.
ml!lil.l!NUi{:l;r: s I *:: : :p+r i: . ,
l',.
_j La: ;_: , L.
L, - -
, ; f t u }lU;h l'
{ ;i[)L , q , y is l' !.
)'}r.0 h:tE ll 'j,i '!m!'I) f" )Y(p.plM m UJ e dil!;iP/eli
! 1 : lD- ___ .;
i iya
- 1'.{tii Ilp,PjI;{tj s.
at gN T ? , ,i, 7 7 n m n-; --
mm9m Ilr 7' n n 1!f 'i f.A
'95 -'*
rm ' d% j)*ikgd] it! I pl i !
- 4TTT a.
L .
n.. _ _ _ ,
.j
',. v_ , L t' -.. s. n
- Q' ; q'O.., -- !uj gl.
j s
e,:. B8 jn a +
9' .n 3 e_ ,m cu _ s_.s_ =_ : =_ : s_ : s_
n t
/ u
, h
, Fg g x-m
(
i Jd} $1 h 1
i g I. };
f l- '
d ji d!:i idr F J;l. .l .l l J l I I D:t i i . . . :. a ., . + k C 19: a
( ... .. ; l 6!
e 7? Q_ E,-w%, ig M+
- Y Y ,' #3 ei j!..is M
- ..
- e
- -= - .u : {
s
'a aa
- n -
!_ g i u = :
,e A :dij M ,
M KN L, p.y.u .
u_ d._q 4 Y, ,1]t @
o s,
p.
_ j} y - jp . '. , s,
.. ., .,.. r:
4,6
,s d s l w,il l . _ u ;; ,i i 1. II y: p,
} !Fhi dI jp n
1 -
's
-9 s N ,
8 E s g. "{ n $
LD g, .!]
'g .}LAh 1*
pm 'g ~- % g;5lc{
p ; ,, ,i
,1 sur if t -a,. ,
7g G
y +- p
- I i.
l (,,.,
- Jgg o=
~2 " ' [j')d 1 uM
- m . .. .
4' 2/29/61 nGURE 203-5b c
n b
_ m , mi .h
. - - _ . . _ _ _ - . . .~ - -. .. . .-.
[%[G
~
s'> g&Q:'
O ': IMAGE EVALUATION /> V gj/;f,/
Q////7 1 4$h* TEST TARGET (MT-3) /'c[S %
V
%/ggl$# k", f l
l.O tM M a BM g!! 2 2
- u. , u M :s
$ $ 1112.0 l,l { r" l!i]zes j l.8 la --
l.25 --
1.4 i 1.6
==
l 4 150mm - >l 4 6" >
h %s ;k+ sA 4ffy ps ,
6 Y N
, Q ' [#//// jfs'7p } b, \//f7 :[' %k TEST TARGET (MT-3) e 4 gg;p { < Y9 %% $,Q l !.0 ES M b " 0!M l,l U { "" . [C lit lllll=2.0 ll 18 e lA ll1.6 h
- 150mm >
d 6" > s I* ef *p
- g
/p 4> 4#k S' ,% %+ & 6 s e, \ PHOTOGRAPHIC SCIENCES CORPORATION *e4a hp 770 BASKET ROAD sfAh P.O. BOX 338 Ek +(tb WEBSTER, NEW YORK 14580 Y (716) 265-1600 , 7% ^ %e. % [ l
- g i .
g l - 'N NN' : _;---. Segrsong y s\ \ GMiPPE M
- .::G '
}}, o3 -.w . j t --+ 3 . , , s ,}- - I / \ \ - - -- / , psrerioneshee anieren \ %gd,d i /. . n I'wN-9~: x E / \ l ' f ierL Cois ~
- \ ,
N ; / ~~~ _..j~ / / A /, ; / / ' ? - . - ' / , - -/ Gnier:n . .oits / u x: p_< . , r _D N VE A .+ l//,q@I , , , -. - - - , GO N / O. 7 ? [\f~,--- / l '7 / / ,.y . y ~ ~~~~': MovrasLr f niverk )%r i , '^ G - ? - - y--- -- s t I I I I ^ / YS$ WN /' , " s.ois Down 7
- b
& bd
- /c.=-
--.~ n . l Q FIGURE 203-6 ,,,m ,us s on,. .m.'!*.*?.!., U. D.','k r ---- t .A f ( it. 4 _ ._., < 1, -..__, -_ . ll .q
- i
- l. - . . < , -_o.
.f -!. , 44 , o
- r a
o,'- _ _ . L . i 1 k.. --:- .: :-~~;'~ :4 - o w e' c; F h! i -4
- d -
w ::, it _ is .J , ' [. - I '._d, a v'3 3- , , t z ;_ 1 ' e i 1 i tr . :::::::...., . r l 7-1 I ca-w .-m . i, i o " , I.' - I ~ ~
- '. I Y. 'l j
l'l- ?M .____.....___..--..; F 7--l,q! it,?! g l [ , 7 y
- , U l> 1
,.:5 a- -2s l: ,a, % c:=J g _:< . . _ = i e
- 'T_,_.. C k L , < ~
,i a _J, , :a y is i
- u. s i
e u g , 's ! , Of ,,g _ . - . . . . . . - g - -y .; E A l _f ,, .t .u-- h M [l i r-l ' [ h a i ;L' = l ,t2 o i -+7 8 32 4] l ..;-. . q ..... .. .__ ..._..j i .___ ../I t, g. ~ 41 . . . . . . . . ._.. , . . _ , , IV O: -l: t ., F, l t i g. j y
- y. _ .. 6
-l*!. +t - ', l ._f " l*1 i 'I., p i - j } , a g L I ,1 r- e . t ' i $ .- i 1(. ;- Sh ---..__s+ $ l [ I 3._. - 5 y - ~~ 1 .j '~~ ^- -*--- ~' E' *ll 7 l .. . '~ 5 o } } h --=7 _JL--;. - ~ 2 ._ g . . . . . . . - . . . . . . . . _ ! ! ) q s'. i hl t },.. I y 3 i J. [y : lk { . l rp -- L - { d,_(. C..._6 - *
- f. l i 'j 'l ij i i -' '
{ p[a a. _ a: _ i. '- l : e i a*( I i i e, , t__............ ... .. . .i -_ :/ y,...._...,....._..-...., g j , r- . j _
- l .
4.u= - - =4e i N: p%-. - }, , T~ i (. .. ..-r._ 3 .....--.......J {d : g FIGURE 203-7 -w r aL ..Jaa, .1 , e - &m. - . - . - _a4 am w. !!! vi kg! -- . . _ _ _ . .. g V h T !^ - d . II - gj . .,
- [5 i
0 bl' i ,n. m JL t$ 8 yfl f ~
- , d M o E
!{i ff 3S h!! -_ $ 8 gl 'r m ! p' u_ S@*< l\s ' ij'j, _Fl N '_-13 l>l 9j - -~ a C a 5
- ggL u -
- llf
~~ ~ gf -. I i: : #J - O f 4 .. a . i SDI Jj ; .g- j 3 I IIf - e-Ilfil{! I i Hil I c ( FIGURE 203-8 e - ,, y- ,....n. m-. ., , , . , . , - , j T** Sf2. ~y (,), E ; ;1 ; ?'A,9. i ^; oa. t. a c n n .. ---t( t(~TG.m iL a I -- El.*N,2 Cl' **'f.'.d $ h l Q : ~_ _ J 1 1 l Mg,! : t N._ f.-} -. - . _=n. *
- y. - .. -- -- - --
-9 / j i- - + N (t ~ I a_[ )(J,_ h;,.I Ili ' l{EUElW . c t '- [' E 2_ ._f t*1~ ihJ;.q__3aM,,,,}) 'IIh1l( ~ Cl \s pu',Ii -U . u i @, .'t r lid" l PMI." Q - i Mi!" ~ , l::h h q- liSkV.$E-m; ~ rnhf - - l ~6 -- , _ . - *_,r_. ___. H < I,mN. g ]e[i.~%.m , _ = e [p.mi. l c ..... r ] - - ~ 8 ir _
- tpElla i
._r -$- pq ljl , e K. C: lg T -JfIh1. _4.-- - . (( - ['l 3 y fi !] / $e $ a @ gjgaz , ! gi d w t p="E 1 t;. w i ft ur 1 1 u i i Ur a 5 a t r a[.t. L.g': oJ {?] < o fi I~ j I'*U{~ jIe -;g p i , -Y
- t 0 . _J +---d -b -
l ,3 y M I l ybi : 'f_..u:, ._m . *--wl-- e t, n __ u - . u j g g ... - . .-- --. - lf g i ni da p% l 55 y.l 4 9 *g - ) j. l J~ut i!- f'-r*.- , e g liitil l11.1 s +-m I _ ' gh !, a a) JlI ll - : k'b+ ..<! - ____~] f M'N ~ }; g n - j* { ORR lfD "_ 'l R.-l ,* _ })J i 7 l o t*, ;r' o g l g gJ i. . g ggo. . . q re ' m,e- T g' . - -h - - . . - - f' s' 8 ,wr=, l rn4.+- - @-- [cw " , f_;_ __ ; ~ A --s-A' g a ,,+-.n., 1 ~ji'ui;. : L ve- ' 11 l -- ~ ~Tigi_ , . . . y' , 1 }, -ys + l @~3 @ & sw;: s :t gl A ,g r- 1 .. h 4gsp!f~ ~ ..-9 g il [' f ~' .M is f,,g_M i+ lL ;; ll!.!I i Ag 8@d.4 ~~ s b ,' . t F ".I - , -)! .,j.j ...'g" m .i t igi 1' , A 1.-- .i .- t t N43 '1 r'; m l e-h;l [$:_: 3t g$;i ht , ., 'f jWM 1 b d I I i l +p%,M
- g l
.... I A i ,p,3j u . Jua- = l g ' ilIII A ; : 2 p I. h u [q7,A_,,2 3 i (1 igloseaaitttijd. -. I pi , p ! 3.-- h= 3 -c . --*--.u-dl [ $li ly:, a -*i-i r, .... , ) .. .w ; FIGURE 203-9 ) ;l}8,
- sa i DU .
l SL_ {, (of*gb Li pin l .1 'l .- f? b , - -i --------l-g---- l T} l! ll I j ' 7- e T lllf +f 1IliIt i i i '9l , a F ,1 l' s 'II ErTr = rr 74 a T, . f, , .. m, () .-e
- p i
0 I q g-l
- --- ,ii I.
lsp tg. l g i , !},g -;c l p::::::=-.=::rd *) l: jij$1-": I ii u, , "T I, -. , '- 8 N. l :;:?,2 t 3l e -w' -'- - ' o ' 11 g II f >:::::-__ _::::::Q("l - g ,_,_'g I ZZL ii ll ~ Ir m --t *.. i l' i
- l l i I .!.-
-, r, r r t_ .______.._______.; gg . .I i. a i r- ---- - - - n------ , , rp . , --i m, .a, -[- ) 3 ~ 7 ,l [ je l) hif.a1.lN:c @ ,, 6 i cl- e I N_. i- _ ,, h ,- . . . ... . - . .i :- y ,p .. ePJ.. ,i l 1lL4:~~ 7 y , - -h {d ........ JJ d A n (p d -- l' .4 rE tp . '. I ' m ' ' 3 wyru n o 2 ll 1 bM....>.. @.. 4 ,{I , :a -- i, .y...., ......... 7 M.S .... . U S g ii i _. s 1 i' .L. ..- 8 i . i . **-. .ja- o A g l l \. * ;f A % O i .
- i. '
, i '* ljr -(D - Eg- . .rit i k .' . bI j, ._ e .g . .. . . , ...--,. . .'.' ~ ~ l , g p .r- ____ 2 i p ,= _ _w i ),} i== ,= .. W. . . . m ._ i i ; li -p .. - w . _.- o ! i o _J 3 _. __, r.b OIlOg 5 - ._ c. Ii [ '.-_ . s. 3i i l C I . i ~ ; ' i v p. ,. ..... . . : .. ,. . ., i ,f ! .y,g .. < ,,....; 3 D edu - l qs cfa j hurt i , ,1 ( ll
- v. . e
~ (kl$s! .?) W
- ' FIGURE 203-10
. . . -. , - , - u_ - m.n__ _a.m a * - . _ . - .mu.J . u. .-.w 3 ma. a. .35 .LS .-.-..w_z.e.4 ,a,__ ,_ ..m___._c as .$e. u-*wem& . met g E "*****N*W*e-eMe4 s -~. I #" c + Al *; i % ** 1 ' t 73 ;1 e J'- -, *** ,- M*'m*
- n '
- .g,'
L b 4..hus.u i enw.
- s. .w.u a
, 4 Y a i 0* i y% ** ! l , a ( j e,. _1 ! lj i ,e sa ! i ' l fp l ' u' '1 e i -t- ., a, ,, <, l .= - , - _ . - . ~ . - . . .,.,_. . I I m g[ Ts 's l, -
- . < ss
' ~ l . s ,- t: s 3 . . . O , >g- @Ikh \ 1 9 n .-'s , Z Ey I** 'w.... . 8 eIt ,i DtI - e t m .-1 4 l @, 8 6 = ,et -. I 4 i S '.- DM~. a ^' f e i s i . 5 % f ( .-,,,**--. f 3 ( FIGURE 203-11 20%.3 l 204 - MAIN COOLANT SYSTEM i i A. General Description ., i The main coolant system consists of a single closed loop containing j the reactor vessel; a steam generator; a canned-motor type circulating pump; ; loop piping; and temperature, pressure and flov instrumentation. A surge line connects the loop to the system pressurizer vessel. Auxiliary system piping connections into the main coolant system are descr bed later under the appropriate auxiliary system. Variable speed control has been provideC for the main coolant pump. The main coolant sy. w 4 has been designed to accommodate a reactor heat cutput of 28 themal megawatts and depending upon the result of the research and developnent program that vill be carried out, it is conceivable that the main coolant system may 'acco=modate reactor heat outputs in excess of 28 thermal megawatts. The system is also designed to pemit a rate of load change of one electrical megavatt per minute and in emergencies vill safely handle full load rejection. The main coolant vater purity vill be controlled within close limits during power operation by means of a purification system, and chemical addition systen. An overpressure of hyirogen vill also be used to control the oxygen content of the water. A lov concentration of boric acid may be required in the main coolant as a neutron poison during cold shutdown. It is also planned to use boric acid for shim control experiments in the B&D program. ! The pertinent design data for the main coolant system are given in I Table 204-1 below. TABLE 204-1 I SUFMARY OF MAIN COOLANT SYSTEM DESIGN System lkninal Operating Pressure, psia 2000 l System Design Pressure, psia 2500 System Pressure Control Range, psia 1985 + 50 System Power Operated Relief Valve Setting, psia 2200 opens) . 2150 closes) System Spring Loaded Safety Valve Settin , . psia 2500 and 2575 System Maxim m Temperature Rise Rate, OF hr 200 System Maximum Temperature Drop Rate, OF hr 200 TotalCoolantFlov,(Naminal),lbs/hr 2.8 x 106 520-ReactorOutlet Reactor InletTemperature Temperature (20(20 Myt Mvt)h,(Nominal)h, (Nominal OF F 540 Average Coolant Temperature, (Nominal), F -530 Main Piping Size, in. 12 - 14 ' Main Piping Material 316 cast stainless' steel CoolantVelocityinHotLeg,ft/sec. 26.0 l CoolantVelocityinColdLeg,ft/sec. 251 (12'in. pipe) 20.1 (14 in. pipe) f System Nominal Pressure Drop at 20 Mvt, psi- 3h.5 'h/61 204.1 Equ1Inent is designed in accordance with applicable portions of Section I of the ASME Code with the reactor vessel and steam generator having Pennsylvania Special Numbers. The entire main coolant system is located within l the containment vessel. During operation, the water level in the reactor compartment is maintained at the level of the reactor vessel head flange. Figure 204-1 is a main coolant system flow diagram. B. Reactor Vessel The vessel which contains the core is a right circular cylindrical container with a hemispherical bottom head and a flanged and gasketed removable l top head. The flanged head has a monitored leak-off connection and provision ~ for seal velding. The vessel has a 58-inch IIf ahd an over-all height of 18 feet. i
- Thetopandbottomheadsare5)inchesandbyinchesthickrespectively.The main cylindrical shell course, like the shell of the SPERT III reactor vessel, is made up of relatively thin plates, individually fomed into barrels which are vrapped and velded one to another to the required total thickness of i 5 inches. This type of construction known as" multi-layer" construction is shown in Figure 204-2 and described in WCAP-1391, MULTI-LAYER CONSTRUCTION FOR THE SAXTON REACTOR VESSEL. This report describes the background and history of multi-layer construction and the reasons for its use in the Saxton vessel including economy, operating safety and flexibility of design.
Westinghouse Report WCAP-1620, SUPPLEMENTARY TECHNICAL INFORMATION ON THE SAXTON REACTOR VESSEL, su=marizes additional technical infomation requested by the Atomic Energy Commission, Reactor Hazards Evaluation Branch. g This report gives additional infomation in the areas of multi-layer vessel history, fabrication, quality control, service stresses, and operating limitations. Tne inside surfaces of the vessel are clad vith stainless steel. The 1 cooling vater enters the vescel through a 12-inch pipe in the side of the j vessel and flows downward past the themal shield into the plenum at the bottcu of the vessel. It then flows upward through the reactor core, removing heat from the fuel elements and is discharged through n single 12-inch outlet. The cylindrical themal shield is made of stainless steel and is concentric vith the core; it rests on support lugs attached to the vessel vall. The core barrel also serves as a themal shield and has a water annulus between its outside diameter and the inside diameter of the themal shield. The shield vill absorb gamma rays emanating from the core, thereby reducing the heat generated in the vall of the reactor vessel frcn this source and the resulting themal stresses. The fuel assemblies are held between two heavy stainless steel support plates which are penetrated-by holes to Accommodate the assembly extensions: The support plates are attached to large thin-valled stainless steel cylinders provided with mounting flanges at the top, which support the assembled core frcn a ledge ,)ust below the vessel closure. . The six control rod mechanism thimbles are velded to adapter parts in the bottom of the vessel. The top head has eleven openings for the insertion + of test elements, instrument leads, and a future superheater test loop._ A su= mary of the reactor vessel characteristics is given in Table 204-2 below. 3/1/61 %, . M .) TAELE 204-2 REACTOR VESSEL CHARACTERISTICS Vessel Incide Diameter, in. 58 Wall Thickness, in. 5 Hemispherical Bottam Thickness, in. 44 Hemispherical Top Head Thickness, in. 5h Over-all height, ft. 18 Design Pressuve, psia 2500 0 Cold Hydrostatic Test Pressure, psia 3750 / C. Steam Generator o The single steam generator, shown in Figure 204-3 is of the vertical shell and U-tube type with integral steam drum and three stages of moisture separation. Althou6h the core is rated at 20 Mvt the steam generator has been designed for operation at 28 Myt. All surfaces in contact with the main coolant water are -either stainless steel or Inconel. The characteristics of the steam generator are shown in Table 204-3 I TABLE 204-3 STEAM GENERATOR CHARACTERISTICS Number of U-tubes 736 Tube Material 304 stainless steel Shell Material carbon steel (ASIM-A-?l2 Gr. B)- Tube Outside Diameter, in. 0.625 Tube Wall Thickness, in. 0.058 Shell Outside Diameter, in. 52.25-Tube Sheet Thickness, in. 95 i 12 Inlet No::le Size (Nominal)h,in. OutletNo:leSize(Nominal in. 14 , Steam Line Size (Nominal), in. - 6 ' Over-all Length, ft. 20 Effective Heat Transfer Surface Area, ft2 2300 < Shell Side Pressure at 20 Mv, psia 605 Shell Side Design Pressure, psia 1800-Feedvater Temperature, F 250 Steam Generation Rate G 20 Mut, lb/hr 69,000 6 28 Myt, lb/hr 97,000-OutletMoistureContentat28Myt,f 0.25 The main coolant flows into the inlet channel at the bottom-through a12-inch (nominal)inletno::le. From the inlet channel the coolant flows up o through the U-tubes and back down to-the outlet channel _and leaves _through a
- 14-inch (naminal) outlet no::le. The inlet and outlet channels are separated by a velded Inconel partition plate. . Access to the underside of the tube
+ sheet is provided by a manway in the bottom of each channel. These manvays 'are sealed with boJ1ed double gasketed covers with leak-off conne.tions between gaskets. These leak-off connections are mcriitorecf for lt akage I past the liiner gasket. See Figure 204-4, a typical double gasket and leak-off arran6ement. /1/61 204.4 Feedvater enters above the tube bundle where it mixes with recircu-lated water and vater from the separators. This mixture flows down between the shell and the tube bundle vrapper then into the tube bundle at the bottom. The mixture of water and steam rises to the top of the tube bundle o and is directed through the three stages of moisture separation and dry steam 0 flows out the steam line at the top. To pemit control of the total solids concentration in the shell side of the steam generator a blovdown connection is ~ provided. . D. Main Coolant Pump The main coolant , ump is a single stage centrifugal pump of the canned motor type, as shown in Figure 204-5 The pump consists of a sealed motor and centrifugal pump impeller mounted on a single shaft, self-contained heat exchanger, volute and hi 6 h pressure motor teminals. The characteristics of this pump are shown in Table 204-4, belev. TAL E 20k-4 MAIN COOLANT PUMP CHARACTERISTICS PUMP o Flov (Nominal), gm 7250
- Total Developed Head (Nominal), psi 34 5 Suction, Design and Test Pressure, psi 2000, 2500, 3750
^ . NPSH Required, ft. 60 I Suction No: le Size (Nominal), in. 14 Discharge Nozzle Size (Nominal), in. 12 Pump Type Vertical, Single Stage Radial With Bottom Suction and Horizontal Discharge MOTOR . Motor Type Single Speed, Class H. Insulation Pressure ' Tight Teminals Bearing Type Radial: vater lubricated sleeve Thrust: self-equalizing, self-aligning pivoted pad, water lubricated Cooling Fluid, sp , OF Demineralized Water, 30 1:ax., 100 Frequency Range, cycles 30 - 67 Speed (range), rp 900 - 2010 Voltage Range, volts, AC 220 - 491 Power Requirement, hot, KW 150( Power Requirement, cold, KW { 190} 5 -/1/61 204 5 The suction and discharge nozzles and pump casing are pemanently velded into the main coolant piping. The motor end plate and motor to impeller casing closures are bolted and-double gasketed with leak-off connections between the gaskets. These leak-off connections are monitored for leakage past the inner gasket. The rotor and stator cans of the pump motor are Inconel, thrust and ~ journal bearings are Stellite-graphitar and all other parts 1n contact with the main coolant are stainless steel. The pump support is designed to pemit horizontal motion of the pump and minimize load on the main coolant piping due to expansion and contraction of pipe. Flov in the main coolant loop vill be controlled during some experiments by adjusting pump speed. This is accomplished by varying the frequency and voltage of the pump electrical supply. An alternate source of power to the pump, consisting of a variable frequency and voltage motor generator set, vill pemit operation of the pump at frequencies between 30 and67 cycles /sec. This power source vill provide a range of main . coolant flows from about 50 per cent to 101.4 per cent of the r.aminal rate. E. Coolant Piping and Fittings The main coolant piping is fabricated of stainless steel and designed in accordance with Section I of the ASME Boiler and Pressure Vessel Code. Centrifuga11y cast pipe and cast fittings are utilized, as pemitted by Nuclear Code Cases N-9 and N-10 of the American Standards / Association Sectional Committee B 31.1 Code for Pressure Piping. The lines \ connecting the reactor vessel to the steam generator and the main coolant l pump to the reactor vessel are nominal 12-inch pipe. The line connecting the stess generator to the main coolant pump is a nominal 14-inch pipe. This ' 14-inch pipe is necessary to provide suitable velocities for flov measurement and to improve flow conditions at the pump suction. The steam generator is suspended from the operating deck above by adjustable solid rods in order to i provide for flexibility and expansion of this piping. Where water at temperature lover than primary coolant temperaturb flows into the main coolant piping, such as water- from the charging system, themal sleeves vill be used. -The flow measuring element located in the line between the steam > generator and main coolant pump is a venturi-type insert. This insert is of 316 stainless steel and is velded to the inside of the main coolant pipe. Elevation-of the steam genert. tor and pump are above the reactor l vessel nozzles to insure that the core is covered with coolant _ at all . times and to aid in inducing natural circulation in the event of loss of power to the main coolant pump. This arrangement vill pemit the steam generator and piping to be drained for inspection and maintenance without affecting the cooling of the reactor core. F. Instrumentation and Control
- 1. General The instrumentation and control system is provided to measure temperature, pressure and flow, and to provide the necessary indications, alams, and control signals to operate the plant safely and efficiently.
/h/61 204.t All controllers, converters, amplifiers, etc., are composed of static magnetic elements to insure maximum reliability and durability.
- 2. FRC-1 This is a main coolant loop flow channel which detects the flow by a differential pressure cell conngeted across a venturi section. The channel has a range of 0 to 3 3 x 10 lb/hrandprovidesacontinuousflow indication on a control-board-mounted strip chart recorder, and lov flov alam, and lov flov scram signals.
3 TRC-5 This is an average temperatum channel which detects the hot leg and cold leg temperatures bg resistance-type, short-time-constant elements. This channel has a range of 500 F to 630 F and provides a continuous average temperature indication on a control-board-mounted strip chart recorder and a " rods up" or " rods down" signal to the reactor control system.
- 4. TRC-2, TR-4 These are vide range hot and cold leg temperatum channels.
Temperatures are detected by resistatc ;-type short-time-constant elements which have a range of 50 F to 650 0 F. The hot leg temperature channel provides high tempenture alam and high temperatum scram signals. Ibth hot and cold leg temperature channels provide continuous indications on a , control-board-mounted dual-pen strip chart recorder. 5 TE-6, 7, 8, 10, 11 l Six resistance-type rapid response temperature detectors are i provided at various locations in the main loop for future experimental work. { They have a range of 5150 F to 615 F.
- 6. PIC-5 -
This is a cold leg vide range pressure channel. Pressum is detected by a flexible tube type element tapped into ,;he main coolant loop between the pump and reactor vessel. The channel has a range of 15 to 3000 psia and provides a continuous indication on a control-board-mounted strip chart recorder and low pressure alam, high pmssure alam, lov pressure scram, and low pressure safety in,jection system signals. A switch is provided i on the control panel to override low pressure scram during startup. \ 7 PR-7-1, 2, 3, h, 5 Five differential pressure detectors are installed across various components of the main loop for future experimental work. PR-7-1 and PR-7-3 have a range of 2 to 10 psi; PR-7-2 has a range of 5-30 psi; PR-7-4 has a range of 10-50 psi; and PR-7-5 has a range of 25-100 psi. ; 8. Main Coolant Pump The fixed frequency and variable frequency supply to the main coolant pump and its control is described in Subsection 218 - Station Service Electrical System. 4/5/61 l , t ! JI . ! .l"b ; I u sv s o] i w j ~ t----O h l -- s l] i .a 1 j ., l e
- s== . , , ..
i ,,,j *~ ' ' [9 .3 60 f)m Y r- -- ' 4.... > 8 e-I I 8 I 4 ! T ! !}! 1 d %,. .li t. a 2 , i !-- (#A. 5 y! l le (, L.:_.(F,#p - ' i i ,A o ... t , It 1 it 4] p ', ' GTt$ . ^ I T ft = l *j l y: ,l i lI l J: g RIl---_. p.G7 @ R. . . P '.'. .g.. . . . . _ . _ . ' , ~ @ l j '\ f g j }I y g ,4 : - .eo- , ,.n n i f ' ' g.M.' . .l @' @ g d [ $ I g .00 i d d O.z & * , g j'3 -.=.t i f M il ,/ ,! e -, t A h- S e (\ xj ). "- I il ! l I d1 .
- N J .;>.i .
ti. l J. i e l 2 4 i w - g _si o!. t1 3" tr. i i I I. I i i l . -- tm _ .O O - r g_ _ . y i-- -- -- ~- 3 I ,, I C ,d ' x i iL I 1 1 I._ J -!! k s - * -e,.re. ::::d l
- 8) I
\ G--O L . - . .. . 4:':' ON\ p)l -- f: 'I # y ' g . . ._.*F=JG-@ - .y l t? < .I .... w..P I ;p- , 7 _. V9i ' Jj! g l , I j, ji ! yN "' 'sl 1; 7 -} }l @ "'(" 'sN %I
- 8) I *[-Q i
d It y 3 5 N q --
- 1. 1 1
. j f..T- J) i t R FIGURE 20h-1 l l REACTOR VESSEL CROSS SECTION ACCESS AND INSTRUMENTATION PORT ADAPTERS lM .- D 'O 2- S* 2 O C wur REACTOR VESSEL HEA $43i : [ CtosuRE 7 - . r$PHERICAL WASHER CLOSURE STUD HEAD GASKETS 3 iN l wa ' y'"g e si J 4gi i ;lL e N0ZZLE egggm;] " 7589d4h f p MOZZLE .- = =. = = r I " ' ' ' ' 4NX4S%Wx T (ggy REACTOR VESSEL ~ # .d T # 0 SUPPORT SKIRT \ # THERMAL SHIELD j l h 4 ! 1 i s s S { REACTOR VESSEL 2 x MULTI-LAYER SHELL N gs ' l g x y ! !5 i \I i 1 2 1 x I 3 4 g ., Ik as a :> f, l ,Y:$ I's' CONTROL ROD DRIVE I MECHAMSM ADAPTERS , M ,/ s FIGURE 20h-2 h l _ _ ___ _ _ . _ .- . . _ _.- _ . _ . _ -- _ _ . .-._= .. __ ._ .. . . ___ ___ .. _ _ .. _ . . 7 6' STEAW OFFTAKE F M VI lM PURIFIER % , CHEVRON $EPARATOR % . g $WIRL VANE %. 1. ^ /vN ~ L - 01 l 1--3' FIEDWATER WRAPPER m i ! I , , i _ 2. - TURE SUNDLE l 1 l I I . I I ; I ^ IB s ! t 1 ! .G P ., i . ! 0 k 3 I 30y TUBE SHEET ~ l l i PRlWARY CHANNEL HEAD g$. ygg ,gy, .g"[ (ONE EACH SIDE) 12*lNtti l r, .. H'0VTLET
- STEAM GENERATOR l
FIGURE 204-3 .- ~ -,,yg .v .,,,y,- .#y,,-- e q. g. , - ,._g-ywyg<r ,y w wy vry e p--w. g- e yp-y ywy, CL . . . PIPE FLAJGE 09 , tW MAY CCVER r ,;, / / / / /j' 's CO TOJDIT PCZZLE CR PW MAY PAC '/ / , 'i i ,/ .vi /, /
- 1. ,j -
it- - *f ' s 1 a.: . - , ~ . {:i ...' . LEAK-CFF M: ' 5:-I , CONECTIDI f-5 h5 i HIG4 FPESSJPE GATET LOW FPESSJRE GASET .s , .m H O DltAL GASKET CESIG4 ' h . a u. n - e a W - - - . . . . _ . - . - . . - - . - . . ~ - . _ . - - - . - . . - - _ _ . . . - . . . . - . . - - - - . . . - - - - . . - . . . -. l i ,y N %% I gr.. 0 4, * , t .- g,>
- l m .
2, ' Q i C.'s ~ .4 (h,1/ 1 .. b . - , . A (y .$h j, i it t, (#. ig j r
- t. i 'x
!f , i> a e i lx .T > . ;' ! 2 - i I :, ( i4 k .' ! ,. 1 .. ?! ';; j 1 14 ' i[' ' .y 'l I y eg he:';h<k 5 l yiq 1 *., N( l f t1 f f ,,( $ k[v *}$* g(>f s t t hr- ./yi; 1y/h"lp A p% \ n ,b ~ l N $,'figJ7 l r , s v,-# &,;px)m'f)mf'qi l - s ,,.~ WESTING HOUSE FIGURE 20k-5 CANNED MOTOR PUMP 205.. 205 - PRESSURE CONTROL AND RELIEF SYSTEM A. Function The functions of the pressure control and relief system are to maintain the required main coolant pressure during steady state operation, to limit to an allovable range the pressure changes caused by main coolant thermal expansion and contraction during nomal power plant load transients, and to prevent the pressure in the main coolant system from exceeding the design pressure. B. Description The pressure control and relief systm consists of a pressurizer vessel equipped with replaceable electric heaters, safety valves, a relief valve, and spray system; a discharge tank equipped with a spray system and rupture disca; two discharge tank pumps; and interccanecting piping, valves, and instrumentation. The pressurizer and its associnted components is shown on Figure 204-1. The discharge tank and its associated equipment is shown on Figure 205-1. The system is located entirely inside the containment vessel. When in operation, the pressurizer contains saturated water and steam maintained at the desired saturation temperature and pressure by the electrical heaters. The charging system maintains the desired water level in the pressurizer during steady state operation. During nomal operation the external electrical network imposes small load changes on the plant turbine generator. These load changes cause temperature changes in the main coolant system. Since the reactor control system, which controls main coolant temperature, does not respond instantane-ously during a load transient, the pressure control and relief system is designed to absorb the main coolant volume surges and limit pressure variations during the initial transient period prior to effective response of the reactor control system. - During volume surges causing pressure increases, the spray system injects subcooled water into the pressurizer steam volume to condense steam and prevent further pressure increases. During volume surges causing pressure decreases, flashing of saturated water in the pressurizer and generation of steem by electrical heater operation maintains pressure j above a minimum value fixed by 2 tactor core heat trr.nsfer design and j safety requirements. ~ Volume surges are trancmitted to and fram t pressurizer by a 3-inch pipe which runs from a point near the steam generator outlet nozzle into the side of the pressurizer. Connections at both ends of the surge line are protected by themal_ sleeves in order to minimize themal stresses due to the rapid temperature eldnses accompanying volume surges. A 1-inch spray line enters-the vessel at the top and teminates in f a spray nozzle inside the unit. This line is connected to the main coolant system at the discharge of the main coolant pump. A solen.J.d-operated valve is provided to control surge spray flovc An orifice in a bypass around the solenoid-operated valve pemits a constant flow of water through the pressurizer. This circulation spray flow prevents the surge line and spray. j205i 9
- line from cooling below operating temperature and provides water recirculation and interchange with the main coolant system. An additional function of the circulation spray is to meintain equilibrium saturated temperature and pressure conditions between the water and steam phases in the pressurizer.
A nozzle is provided on the pressurizer for connection to a power-operated relief valve. The valve is provided to prevent or reduce the possibility of operation of the self-actuated safety valves. The safety valves are provided to accommodate large volume insurges which are beyond the pressure limiting capacity of the pressurizer, its spray system, and the relief valve. The design and performance of the safety valves are based on the requirements of the applicable sections of the ASME Boiler and Pressure Vessel Code,1959 Edition, as interpreted by ASME Special Ruling Case 1271N. The safety valves are capable of handling the most severe volume insurge transient. O The discharge tank is a closed tank which will receive steam from the pressurizer relief valve or safety valves and provides temporary storage of liquids and gases from various vents and drains inside the containment vessel until these wastes can be pumped to the radioactive waste disposal facility for treatment. The tank will contain sufficient house service water to condense the steam resulting from the lifting and subsequent reseating of the safety valves. Two discharge tank drain pumps are provided. These pumps operate automatically when the discharge tank level reaches a predetermined value. ( Normally, the discharge tank will operate at a slight negative pressure l (apprcximately 6 inches wg.) maintained by the gas compressors in the l waste treatment plant. Provision to sample and nitrogen purge the atmosphere in the discharge tank is also rnde. In the event the discharge tank water level falls below a pre-determined value or the water temperature exceeds a preset value, an l alarm will be sounded and house service water can be manually added to ' - i the tank through a spray nozzle in the tank. - - - l l- C. Components l 1. Pressurizer
- The pressurizer is a cylindrical pressure vessel which is
- installed with its longitudinal axis in a vertical position. The pressurizer is equipped with a bundle of electric heaters composed of 18 stainless steel sheathed immersion heaters individually welded to a stainless steel dinphragm which is backed up by a heavy carbon steel blind flange. The heater rods thus extend vettically t up 1nto the vessel body.- The pressurizer shell and heads are fabricated from ASTM A-212 Grade B carbon steel clad with austenitic stainless steel.
All internals exposed to primary water or r;eam are constructed of austenit't stainless steel. The pressurizer is shown on Figure 205-2. The pert . sent characteristics of the pressurizer are listed on Table _205-1, below. /9/61 205 3 l l TABLE 205-1 PRESSURIZER CHARACTERISTICS i Maximum working pressure, psia 2500 Maximum vorking temperature, OF 668 / Normal operating pressure, psia 2000 /- Nomal operating temperature, OF 636 / Maximumheatingandcoolingrate,OF/hr. 200 Free internal volume, c'u. ft. 100 Liquid volume, at normal operating level,cu.ft. 30-
- Liquid volume, at minimum level, cu. ft.(approx.) 20 Heatercapacity(total),KW 120
- 2. Discharge Tank This tank is a right circular cylinder with both ends' closed by standard ASME spherically dished heads. All vetted surfaces are adequately protected by .a corrosion resistant lining. The tank is equipped with a 16-inch circular manhole vith bolted and gasketed pover plate.
The discharge tank is designed in accordance with Section VIII of the ASME Code for Unfired Pressure Vessels, Nuclear Code Casee 1270N and 1273N and all applicable sections of the Pennsylvania Department of Labor t and Industry Regulations. A sparger is inst,alled inside this tank to ~ l properly distribute the flow of cteam at a minimum pressure drop and to p provide the most rapid rate of steam condensation. Two rupture. discs y are installed on this tank to relieve excessive pressure to the containment l Vessel interior. The pertinent characteristics of the discharge tank are l listed in Table 205-2, below. l TABLE 205-2 DISCHARGE TANK CHARACTERISTICS Construction material Carbon Steel Design pressure, psia 75 Design temperature, OF 300 Design vacuum, inches of water 10 l+ Tangent length, ft. 6.75-Diameter, ft. 5 lt Nomal water volume, % 50 3 Discharge Tank Drain Pumps Ivo discharge tank drain pumps are provided. Each is a single stage pump capable of delivering 25 gin at a discharge pressure of 45 psig. 7 The pumps are equipped with mechanical seals and provided with special covers ) to insure ths.t water leaking through a failed seal vill be contained in the l frame. //61 3 b 2vy.4
- 4. Safety Valves Each of the two self-actuated safety valves is capable of
- passing 20,000lb/hrofsaturatedsteam. Both valves are equipped with seals which prevent leakage to the atmosphere.
5 Relief Valve The relief valve is air-operated and designed to pass 25,000 lb/hr of saturated steam. D. Instrumentation and Control
- 1. Pressure A narrow range (PRC-2) and a vide range (PIC-3) pressure channel is provided to measure pressurizer pressure. Remote indication of discharge tank pressure is also provided by PI-21.
The narrow range channel, PRC-2, provides an "On" "Off" pressure relief signal, controls the pressurizer spray valve, and provides a continuous signal to a motor-driven variable transfomer which controls the pressurizer heater power, and hence the pressure. This channel also provides a Di6nal for continuous pressure recording in the reactor control room. The vide range pressure channel, PIC-3, is a backup channel for ( the main coolant loop vide range pressure channel, PIC-5, and accomplishes i the same functions. This channel also provides a si6nal for continuous pressure indication in the main control room.
- 2. Temperature Temperature detection elements are provided at various locations in the system. Three elements (TE-10,11,12) are provided in the surge and spray lines for future experimental measurements.- Two elements (TR-20-10 and TR-20-ll) are used to detect leakage from the pressurizer safety valves and one element (TR-20-6) is used to detect and record discharge tank vater temperature. TR-20-6 also provides an alam, shuts off the discharge pumps, and clmes a pneumatically operated valve on the discharge side of +he pumps
\ \ on high vater temperature. 3 Flow Two flow detectors (FE-5 and FE-6) are provided in the surge and spray lines for future experimental measurements.
- 4. Level Remote level indication is provided for the pressurizer water level and the diccharge tank vater level. The pressurizer channel (LIC-2) is a vide range level channel which provides signals for continuous level I
indication, "On" "Off" hi6h and low level alams, low-level heater shut-off, and low-level scram. The discharge tank channel (LIC-21) provides a signal for continuous level indication, a signal to operate the discharge tank drain pumps, and high and low level alams. /28/61 205 5
- 5. Discharge Tank Drain Pumps The discharge tank drain pumps receive power from motor starters located in the motor control centers. Each is controlled by a control switch on the main control board. These svitches have " Auto" e "Off" *Run" positions.
With a control svitch in the " Auto" position, operation of the selec'ted pump is controlled by the discharge tank level indicator - controller (LIC-21). An auxiliary contact on each motor starter opens the valve (LIC-21V) in the pep discharge line whenever a pump is started. If, the discharge tank level indicator - controller (LIC-21) signal,s high level, and both starters are open, an annunciator point on the main control board vill operate. Red and green indienting lights are
- located with the control switches on the main control board. The pumps are interlocked to shug off autcraatically when the water temperature exceeds the limitation;of the.vaste disposal system.
- E., Design Basis Nomally, 30 cubic feet of the pressurizer volume vill be filled with vater. The pressurizer and reactor control system is designed to accomodate step load changes of + ten per cent and a, ramp load change of 1 Mwe per minute without pressurizer heater or spray operation. System transients greater than this vill be controlled by pressurizer henter or spray operation, or by operation of the air
- operated relief valve. The safety valves will accommodate k
a volume insurge rate of 1 cubic foot per second. This ig %e surge rate which could result frcn an accident condition in which genen. tor load is lost and the reactor is not shut down by autenatic scram. Persistence of this condition vould reeult in rupture of the 60 psia discs located on the discharge tank. s /6/61 - - - - _ __ _ __ i i! Il 'lI I ; l {! If h 5 W d> J. -.J 's l , s , , l @- ! -@ l ^ l ~ A!}D})i 9 t , ~ pl g...mg ? rha ;! e y gg g g _______ -_________ l ' , c.; f }/ h h ' i l lf' i r :i A , llf : j' ? ~i: I ! !" @ l3 r 4,,,1,?x _a _ - . 4' d, ( Lt - , l .-- ,.----- di h ;>> ;
- , pr> .+ a E
l [ ri l , c -- . 7_-_- . ._ a II r- d l o ga E la}s y 13 s k l. .e . l I4 1 h na EE ( FIGURE 205-1 TO PRES $URE -, SAFETY VALVES 'N thh i} fjt , -TO REttEF VALVE %%, - -u + -1 s / f \, x\N '-SF1 AY N0ZZLE Q f / \ s 'sx \ q (5 WINIMUW WATERm LEVEL 9 3 h t 2' DISTRIBUTION RING > 2 ~3' SURGE N0ZZLE - - - - - - '4 . l-.L[ 4 JQ i- :$
- E 1NU .. m.
Y ~[ N 3' I \ HEATERS-7# , HEATER SUPP00.T .%:. s h, ,.! _.-u d.,y'I s- 15' WANWAY 4 34 j ~ j%hl( / DRAIN 38 PRESSURIZER ( n.GURE 205-2 - _ _ _ _ _ _ _ . _ _ . _ . _ . . _ _ . _ _ _ _ J 2CT 206 - CHARGING SYSTEM l A. Function The charging system is designed to receive and charge into the main coolant system decasified demineralized water from the secondary , plant, borated vnter and decontamfinan solution from the chemical addition system, and main coolant system vater from the purification system. The later condition thereby sets the purification system flow rate. In addition, the charging system is designed to provide 3750 psis pressure for testing the high pressure systems. B. Description The charging system is located in the control and auxiliary building and consists of two charging pups and the necessary valves, piping, and instrumentation as shown on Figure 206-1. The system is initially filled with degasified demineralized water frcan the secondary plant, and takes suction from the purification system surge tank during nomal operating conditions. The charging pumps are nomally operated on an niternatin6 schedule with one pump available as a spare. However, when increased purification flow rate is required, the two peps are operated in parallel. The capacity of the charging pumps may be varied according to the operating requirements- of the plant. 1 C. Components
- 1. Charging Pumps l
Each of the charginr rumps is a motor-driven horizontal, triplex, reciprocuting pump. The -paetty of each pump is adjustable between 3 and 15 gpm at a total dynamic head of 2500 psig at 15 gpm and 3750 psis at 3 gpm. A pneumatic control positions rubber belts on cone ! type discs to control the pump capacity. All leakage past the plunger l packing is carried to vents and dmins through connections from the l stuffing box which has a flushin6 connection for diluting leakage. l
- 2. Valving i
{ Relief valves are previded on the discharge side of each ! pump to protect the system piping frcn overpressures. Tne valves discharge to the suction side of the pumps. In addition, a relief valve is provided I on the pu=p discharge header to protect the system during hydrostatic tests. This valve discharges to the vents and drains system. l* Valver vhich handle radioactive water with system pressure on the packing gland are provided with leakoff connections. Vent and drain valves which are normally closed and do not have system pressure on the packing gland are not provided with lenkoffs. (
- Valves smaller than two inches have back seats and are not provided-vith leakoff connections.
l 3/10/61 206. D. Instrumentation and Contrnl
- 1. Pressure l
- o 'Pwo locally-mounted pressure indicators (PI-22 and PI-23) are provided. These channels also provide signals for high pressure alarms.
I
- 2. Flov j A flow recorder channel is provided for each charging pux:rp
! (FR-24andFR-25). These channels provide signals for a control-roca-l mounted dual-pen recorder and the purification system let-down flov control FRC-22. 3 Charging Pumps - l The charging pumps receive power from motor starters located in the motor control centers.' A control switch and red and green indicating lights for each pump are mounted on the main control console. The control svitch has " Start" "Stop" positions. \ control-board-mounted pneumatic control station is provided for manually adjusting the output of each pump (HC-24 and HC-25) by controlling the set ing of a variable speed drive. E. Design Basis The charging system handles radioactive vater and the various chemicals received from the chemical addition system as mentioned above. i Therefore, in order to maintain the purity of the demineralized water i and to decrease the rate of corrosion, Type 304 stainless steel is used for all piping, valves, and component parts which are in contact with the j vorhing fluid. The system is designed for 150 psig at 4000 F on the auction j side of the charging pumps and for 2500 psig, 4000 F on the discharge side l of these pumps. l l Normally, the purification flert rate into ed out of the primary system is 10 gin; however, it may be desi?sMe during plant operation to vary the purification flow rate to provide increased or decreased purifi-cation rates. In order to meet the above flow rate and flexibility requirements, two duplicate charge pu=ps are provided, each designed to l deliver 3 to 15 gp at a discharge pressure of 2500 psig. The two pumps, l vhen operated in parallel, provide 30 gpn for the feed and bleed . operation, l and during normal plant operation one pump provides the required flow rate l allowing maintenance to be performed on the other pump. l The ASME Code for Unfired Pzusaure Vessels, Section VIII, requires , thatpressurevesselsbehydrostaticallytestedat1-htimestheir l maxiran operating pressures. Since the vessels in the primary system are i designed for 2500 psig, they must be hydrostatically tested at 3750 psig. The charging pumps are designed to provide this 3750 psig test pressure for the high pressure systems. J 2/3/61 g 206. All of t!- min piping of the charging system is steam traced in order to provide :ssurance that a sufficient temperature vill be l maintained in these lines to keep the boric acid in solution during those periods when it is being charged into the main coolant system. k b .d g --~& em. a ,au.w -.-- _ 3.A - m a---a. .A_ w .A _,,___e 4- .A .6 A ,-- - r J 14 i 0 h l) i" a I . I i En r-l . ;y \ I . . . . 5~ ;@ 19 D i T, it+ ',g1 i O<,' i t. . $ j!9 A r i :
- l5
}1 *. '} 5 !! ,, ~}1} e' ' d '> i l' . i. y >s e 1 >,. ~ '.g I $r3y 1, - tsi 1. r i i t r8e 9 g . g /} - + - a p ;a l e:i t ' #3 . s g .q f'.. . ..h. .$,N@j' h e p,* ..i. g 1.;;e.. m Xu g . . . . . . s ' . .'f.1' . . . .gg 13 , . e 8 g 3 ?( ,, g i ! i;) 5 f, ,i .. 7a, 4(l' I 'd j' < on- R t l !. I 4 l l , 4 I' ir i l' l l l - t i 1 < APR 619B1 1 I ji) ;5) l l f- f. \;
- d. + l@ .\..5,, .n.- h TAllr.!, 16 j[i d,t!!j q.) IF } .[1 1t,' 2 3
e - P ,3, y ,9 ' 8 5ll f' ,3, - i . h g . .- 3 a 6 y ft, f_ ,!$, y. > ~y p \ g> > . a A p g , j, d . . . . . . .k::hf,k bh h 4:!i k C! ..q.....f.1....g ; . t.. . . . . c s ,, . , ,. II . ; f ' 1( r b i , .. . . . . . . . . &74 ^ ' Il, L E a..1, ' ( c n [er,, g ! I b I i ) h 6 1 1 lt I ( FIGURE l:06-1 , APR 61981 207 207 - p0RIPICATION SYSTEM A. Function The funetaon of the purification system is to establi6h and maintain vnter purity in the main coolant system to provide control of hydrogen concentration in the main coolant system vater, to provide a source of main coolant system vater for both sempling and for fission ' product detection, to remove boric acid frm the main coolant system vnter by a bleed and feed operation and by ion exchange, to provide a cource of make-up "ater to the main coolant aystem, to regulate pressuriter water level during normal operation by bleed or feed, and to remove decay heat until the main coolant system t; wrature and pressure have been reduced sufficientiv to pemit operat' ** the shutdovn cooling system.- B. Description The purification system consists of a regenerative heat exchanger, let down flow control valve, nonregenerative heat exchanger, parification demineralizer, borie acid demineraliter, filter, surge tank, accumulators, nitrogen and hydrogen gas supply, and the necessary valves, piping, controls, and instrumentation as shown on Figure 207-1. The system is lo,_a,ind eg 4ntirely inside the containment vessel vith the exception of the surge tank, the gas Tupply station, and piping leading to and fr a the surge tank and charging pumps. The main coolant syatem provides th= iriving 1'orce for moving vater ( through the purification system, and the charging system provides the menna for returr tne the water to the high pressure primary coolant. ~ /rportion of the main coolant system vnter is continuously by-passed through the purification sy: tem during nomal plant operation. The high r.ussure, high temperature water enters the purification system through a take-off connection upstream of the main coolant circulating pump and is passed through the tube side of the regenerative heat exchanger where the water temperature is reduced to prevent flashing in the let-down flow control valve located immediately dovnstream. The charging pumps charge water into the main coolant syste.n at a constant rate and therefore water has to be bled fra the main loop at a 4 constant rate in order to maintain the level in the pressuriter. A liquid relief valve is provided devnstream of the let-down flow control valve to 'yp ' ' protect the low pressure .ystem fra overpressure if the let-down flow control {' valve should fail open. 1 ) The purification stream continues to the nonregenerative heat j exchanger, or to the shutdown cooling heat exchanger whicli is a duplicate of and which it. piped in parallel with the nonregenerative heat exchanger, where the yhter is reduced still further in temperature prior to its cntering the demineralizer vessels. Since the performance of the resin in the resin vessels is impaired at ten.peratures greater than 140 0 'F, a temperature indicator and alam are provided downstream of the nonregenerative heat exchsnger, in addition to a temperature-operated three-way valve which by-passes the flow past the demineralizer vessels upon sensing high temperature. A , portion of the purification stream is by-passed immediately downstream of the ( nonregenerative heat exchanger through a fission prcduct d6tector. The i ._ , o effluent from the riscion product detector is returned to the system at the surge tank. ;3 1, /6/61 207 The water passes through the purification demineralizer during i nomal operation, or through the boric, acid demineralizer after feed and bleed. The soluble corrosion products in the vater are removed by ion exchange, ! and the insoluble products are removed by the filter action of the resin bed. ! The demineralizer vessels are instaued as permanent units with provision for sluicing spent resins to the radioactive vaste disposal facility. Sa: pling ; lines are provided both upstream and downstream of the demineralizers so ! that an indication of demineralizer efficiency can be obtained. j From the demineralizer, the purification water flows through the system filter which :emovec any resin fines or other insoluble corrosion products which carry over fra the demineralizers. The water leaves the ; filter and is piped outside cf the containment vessel to the surge tank
- located in the control and amiliary building. A hydrogen gas supply system is provided to maintain a hy1rogen over-pressure of approximately 15 wig in the surge tank. The surge tank spray nozzle sprays the incoming water into the hydrogen atmosphere in the surge tank, where the hydrogen gas is
, absorbed by the water thereby providing corrosion inhibition. In order to prevent an explosive mixture of hydrogen and oxygen frcan occurring in the M (, " e sarge tank, a nitrogen gas supply is provided to sweep the tank. yV Make-up vnter frcan the secondary plant is added at the surge b Q teak through a valve that can be operated from the main control rocen. Chemicals ' required for plant operation are also added at the surge tank through the make-up water line. During the feed and bleed operation, water is discharged to the radioactive vaste disposal facility through a manun11y operated valve. , ( I The water flovs frcto the surge tank into the charging system when boric acid may be added fmn the chemical addition system and where ,he vnter is pumped into the high pressure line to the main coolant rystem. When the reactor in operating at power, the pressurized water is passed through the shell side of the p generative heat exchanger where it is heated to prevent themal shock on the main cooTeInTWing connection and it then is returned to the main coolant loop at the cold leg downstream of the main coolant circu-lating pump. During hot shutdown, the purification system nonregenerative heat exchanger is used to remove decay heat. In addition, this heat exchanger is used to reduce the main coolant water temperature to 3000 F prior to placing - the shutdown cooling system in opsration. During these shutdown operations, the regenerative heat exchanger can be partially by-passed by three-way valve TIC-24V which operatea on a signal from TIC-24 to automatican y maintain the regenerative heat exchanger tube side outlet water temperature below 300 0 F. C. Compor.ents -
- 1. Regenerative Heat Exchanger This unit is a horizontany mounted U-tube and shen type heat l exchanger. The- tubes an velded to the tube sheet and the end closure is of a I velded cap design. The tubes and all other material in contact with the main coolant water are Type 304 stainless steel. The a generative heat exchanger is designed for 2750 psig pressure so that the relief valve provided on.the shen side of the lent exchanger may be set at a higher pressure .than the main coolant -
safety valves, thereby anoving the pressure of the main loop to be ccntroned from' the pressurizer. /7/61 . 207 The unit is sized to rennve 4,500,000 Btu /hrwithatubeside inlet temperature of $20 F, a tube side orttlet temperature of 2450 F, and a shell side inlet temperature of 125 0 F.
- 2. 1,et-Down Flov Control Vaive The let-down flow control valve is designed to control the flov through the purification system so that a constant average level is maintained in the0pressurizer. It is a diaphra6m operated valve designed for 2000 psi at 550 F and a maximum open flow rate of 38 gin.
3 Nonregenerat$ve Heat Exchanger This heat exchanger is a flanged head, horizontal, U-tube and shen type unit. The tubes and all other surfaces in contact with the main coolant are Type 304 stainless steel. The shell side and tube side of this unit are designed for 150 psig at 3000 F. A liquid relief valve is provided on the shen side of the unit in accordance with code requirements. , The unit is designed to transfer heat at a rate of 1,800,000 Btu /hr0 with a tube side inlet temperature of 2450 F,0a tube side outlet temperature of 125 F, and a shen side inlet tempersture of 100 P.
- 4. Demineralizers I!cth demineralizer vessels att constructed of Type 304 f stainless steel aiid contain 6_ cupid feet of resin. The design pressure for the
\ vessel shens is 150 psig at 3660 F. The purification demineralizer contains a mixture of cation and anion resins containing one equivalent of lithium ions for each equivalent of hydroxide ions. The total exchange capacity of the unit is 72 kilograins expressed as calcium carbonate. The boric acid demineralizer contains an anion resin which is in the OH form. The total exchange capacity of the unit is approximately 26 pounds of borin acid. 5 Filter TheiglterbodyisofTypt 304 stainless steel and is designed for 150 psig and 200 F. A flanged head with a flexitanic gasket is provided for filter element removal. The filter media is a porous, sintered stainless steel sized to remove 5 micron particles and larger.
- 6. Surge Tank This tank is constructed of Type 304 stainless steel- and is designed for 150 psig and 3660 F. It is of all velded construction with the e exception of the manhole which is flanged.
The tank has volume of 'Q cubic feet and is designed to contain that volume of water which is accumulated there during the maximum temperature I rise in the main coolant system during normal plant operation. ?/1 0/61 h(%%WAfWWQX D. Instrumentation and Control
- 1. Pressure Provision is made to measure pressure or pressure drop at three points in the system. The surge tank pressure channel (PR-21) provides a signal for continuous recording of surge tank pressure and fc actuating a high pressure alam. The pressure drop across the filter in monitored by a channel (PI-27) vhich provides a signal for pressure drop indication and for actuating a high pressure drop alam in the main control roam. The pressure downstream of the let-down flow control valve is monito ed by a channel (PI-23) which actuates a high pressure alam.
- 2. Temperature, Sensing elements are provided at numerous points throughout the system to measure temperature and provide signals for indication, recording, alam, and control. The shell side outlet temperature of the regenerative heat exchanger is recorded (TR-20-1) and the shell side inlet temperature is locally indicated (TI-21). Tne tube side outlet temperature of the regenerative and nonregenerative heat exchanger (TR-20-2 and TR-20-3) and the purification l
, surge tank vnter temperature (TR-20-9) is recorded. TR-20 3 also provides an override signal to close the let-dovn valve on'high temperature. Associated alarm points are located on the main control board for each recorded temperature. Three te=perature-indicating controller channels provide signals to regulating valves. The nonregenerative heat exchat.ger cooling vater discharge temperature is regulated by a signal from TIC-21 to TIC-21V. The demineralizers are protected from excersive temperature by TIC-23 vhich provides a signal to TIC-23V which can operate to cause the flav to by-pass the demineralizers. The tube side outlet temperature of the regenerative heat exchanger is regulated by a sign-1 from TIC-24 to TIC-24V. 3 Flow The let-dovn flow control valve (LRC-21V) is actuated by a signal from a flow recorder control % (FRC-22) to maintain a constant average , coolant volume in the main coolant system. This is accomplished throughout all phases of the plant operating cycle by first comparing the in-flow to the out-flow rates and adjusting the difference by the preocurizer average level. The integrated flov of make-up to the sur6e tank is indicated (PI-21) and the flov rate to the surge tank is recorded (FR-22).
- 4. Level The surge tank level is measured and indicated (LI-22) by a channel which also provides a signal to actuate an abnormal level alarm (IA-22).
E. Design Basis ^ In order for the system to be compatible with the pressure temperature conditions of the main coolant loop, the purification system is designed for 2500 psig at 6500 F from the main coolant take-off connection, through the re-generative heat exchanger tube side, up to the flow control valve. The flov 17/61 ( v 207 control valve is designed for 2000 psi and 5500 F. Fro:a the flow control valve to the charging system inlet, the system is designed for 150 psig at 4000 F. The return line from the charging system up to the check valve at the containment vessel is designed for 2500 psig at 4000 F. The check valve is a standard 1500 poi valve. The system tom the check valve through the regenerative heat exchanger shell side to the connection on the main coolant loop is designed for 2500 psig at 6500 F. Since the purification system handles radioactive vater which contains a 1% by veight boric acid solution and vill at times also carry a corrosive deceptaminntQsq1ution, the system piping and equipnent which nomally come in contact r.t Mhe primary water have a corrosion resistance at least equal to that of he 304 stainless steel. The system piping is designed in accordance with the American Standards Association Code for Pressure Piping, ASA B-31.1. The regenerative heat exchanger, nonregenerative heat exchanger tube side, demineralizers, purification filter and purification surge tanks are built in accordance with the ASME Code for Unfired Pressure Vessels, Section VIII,11.cluding Special Nuclear Code case Rulings, and neet the requirements of the Ccunonwealth of Pennsylvania Department of Labor and Industry Boiler Lav and Regulations for Uarired Pressure Vessels. The two lines which penetrate the containment vessel in the purification system are valved to insure that the line fluid is contained in case of a rupture outside of the containment vessel. Lenkoff connections are provided on the packing glands of all valvenswhich handle radioactive 9 ( vater and which have system pressure on~tne packing gland. Valves which lead to the vent and drain headers are installed so that the system pressure is under the seat thereby eliminating the need for leakoff connections. , Connections are provided at various points in the system for adequate flushing, venting and draining of lines containing radioactive water. The flush, vent and drain lines which are connected to high pressure equipment contain double high pressure valve to ensure that there is no leakage of high pressure water into the lov pressure systems. It has been established that a purification system flow rate of 30 gpm is required to inhibit the deposition of crud on the main coolant loop. De purification demineralizer is sized to maintain the impurity level of the ma4n coolant water at less than y1 based on a corrosion rate of 10'milligrea/ dm'/monthwhichhasbeenestablishedasthemaximumrateofcorrosionfor stainless steel under the operating conditions. The boric acid concentration in the main coolant water is reduced to 4 5 veight per cent of the initial level by feeding and bleeding an amount of water equal to approximately three main coolant system volumes at rates up to 30 gpn. The boric acid remaining in the system is removed by the borie 1 acid demineralizer, also at rates up to 30 gpn. Since these flow rates are available and it ray be desirable to operate the purification system at increased flow rates prior to shutdown for polishing 3the purification demineralizers are also designed to remove fission products and corrosion ( products from the primary water at flow rates up to 30 gun.
- Valves smaller than tvo inches have back seats and are not provided with lenkeff corn etions.
3/10/61
- Aa-4 Ju=B-4 4.A4-M.,44 4 hW h h h M h AA A4b hAA-sad--S 2 A e-w.e mM6 4 M45a>- "hsh A a s 2- 44+5=l=-44M*S*81MM-*s43 h+ e m""Mahb h 3 M mm. J A 4WA.2eAJ 44w
'Id k ' L l 'I 8 ; hh e
- .m .-
l i h -o i t[fn"1 e ' .,i D, Mi"' ).14 , q (, ![ d _:l' d l"il! d:d.i ' i l a 'A;' - ,6 s k. &* 3 , t , gia .t > l ,......_.._~...r...v.L.ytsi 'I . . ...T ,. Nw!;h,t:j,!' dj f, , ut . . _ l lf, i ri . > 1. ,. ~ , L . . .lb f,_. i - + q _e 't 1! ! '~ I. a l fut It _ - . . _ _ . a, J y#agp :l['A[l fr - il p l f { .Iy ,,I , 41 3.. $. . - ,4 . u8.: p,j c.a . u i w ._- q, ;g i i - a e sl.y si i b ;:---4 Q. p- v$- ) n i, : . I } i - - i ji . 4., 1 au.t [4 (..1s e 5 I y .fI ff gf ,ift m h < 1 ' r I il t ul Lg. I < -+> Tr -g. -.~}J - in , i . , .i #'b. I,U I ' [gw)4 *' -- g M 4 ~ th* 9 Es g l * ~ l, l 4 , lill .%. a 1 5 m i l i l - - - , .- x l l } y)V ,Ll IQy Om>~&:::::.--- y e i, s -c=t c 11 f}!N, . .N g =- .. s c eei i L i 2.' i -.4 y ,y' ,- , .. = I .wl l. 1l 4A' jl i 7.k' J I} , l [ l El 1d e g-.!rp; 8 . T f* - 1L111 nr :q) J -- +; - *~$ LeJlit i . j g i e4 e + ei b'* h " l) . i 6...___.. i3._._ i, A , m.m .i },, 4 r.=- 2 g, .[ 1"~g/ ---k [.Is N.)U$h1\l[ l ,i . o i , i ,1 - ga o ,f i . .. ihi. e !. .,i * 'pi Lp ._l- *
- . > 1 ,
.- 1 3 4 A-y% ih-% 7.. h d H, ,I 5 1! y*r , F,p'r k < "~n !pi "i ; e \ I t t n,3ll. ! .
- 1. l _1 pa 0 r! i
-1 e i j i 9 4' , FIGlmE 207-1 208. 208 - COMPO! TENT COOLING SYSTEM A. Function The function of the component cooling system is to remove heat from the shutdown cooling heat exchanger, main coolant pump, and non-regenerative heat exchanger. B. Description The ccmponent cooling cystem is located entirely inside the con-tainment vessel and consists of two centrifugal circulating pumps, two heat exchangers, a surge tank and the necessary piping, valving, and instrumenta-tion as shown on Figure 208-1. The system is initially filled through the surge tank with demineralized water fron che secondary plant. Chemicals required for corrosion inhibition are manually added at the surge tank. The water is continuously recirculated by the component cooling pump through the eouipment which requires cooling and then through the component cooling heat exchanger where the absorbed heat is transferred to the river water. Only one pump and heat exchanger are required, hence the second pump and heat exchanger serve as spares to insure availability of cooling water in case of equipment failure. Make-up water may be added to the system through a remotely operated surge tank fill valve. O. Components
- 1. Component Cooling Heat Dcchangers These heat exchangers are flanged head, horizontal, U-tube and shell type units. They are constructed of carbon steel with admiralty tubes. A relief valve is provided on the shell side of the heat exchangers
! in accordance with code requirements. Each unit is designed for a maximum heat transfer rate of 2,055,000 Btu /hr with a tube side inlet temperature of 131DF, a tube side outlet temperature of 1000F, and a shell side inlet l temperature of 800F. The shell sides and tube sides are designed for ! 150 psig and 2000F.
- 2. Component Cooling Pumps Two eingle speed, end suction, vertically split casing, centrifugal pumps are provided for circulating the component cooling water.
Each pump is provided with a single mechanical seal to minimize leakage , and has a capacity of 155 gpm at a total dynamic head of 70 feet. .The design pressure is 150 psig at 200 0F. The pumps are of cast iron construc-tion with bronze trim.
- 3. Component Cooling Surge Tank f .The component cooling surge tank is a 3 cubic foot, 1 cylindrical, corrosion protected open tank.
l ._ .-- _ _ . . . . . , _ _ . . - , . . - _ _ _ _ . _ , . _ _ , . ~ . _ . . - - - 208.:
- 4. Component Cooling Strainer This is a "Y" type strainer which uses a vire mesh screen to collect foreign particles. A flushing connection is provided for cleaning the strainer.
D. Instrumentation and Coatrol
- 1. Precsure The pressure in the discharge line of the component cooling pumps is measured and recorded (PR-22) on a dual-pen recorder located in the main control room.
- 2. Temperature The component coolmit pump outlet vater temperature is measured and recorded (TB-20-4) and the component cooling heat exchanger -
component cooling outlet water temperature is also measured and recorded (TR-20-5). The recorder and associated alarms for thece temperatures are located in the control room. A temperature indicator - controller channel (TIC-22) provides a signal to regulating valve TIC-22V to maintain the temperature of the shutdown cooling heat exchanger cooling vater discharge temperature. Eight vells (TW-21 thru 28) are provided for the placement of j local temperature indicators. 3 Flow Remote flow indicator controllers with associated alarm points are provided to indicate main coolant pump coolant flow (FIC-24) and house service vater flov (FIC-25). In addition, a flow recorder controller (located in the main control room) with an associated alarm point ic provided to record corponent cooling pump flow. Interlocks are provided so that a lov flow signal or opening of the operating pump starter vill start the standby pump.
- 4. Level, ,
n s -- F (LI-23) is provided. lo' level. Remote This indication in main channel actuates an control alam (LA-23roomto varn of sur)4e of h' ' leve tank V 7Irk 5 Component Cooling Pumps 'j/ 3 7 The component cooling pumps receive power from motor starters in the motor control centers. Each is controlled by a control switch on l the main control console. These switches have " Start" "Stop", plus a pullout " Standby" position. Vith a svitch in the " Standby" position, the pump designated as " standby" vill start if the motor starter for the l ' g running pump opens, or if the flow recorder-controller FRC-21 signals lov flow. l l 1 l 208. Green, red, and amber indientin6 lights are located with the control switches on the main control deck to indicate "Off", "On" and " Disagreement", respectively. "Stop" " Start" pushbuttons are located locally in the pump area. An annunciator point on the main control board in the reactor control room vill operate to cause an alam if the motor starters for both pumps are open. E. Design Basis The cooling requirements of the component cooling system vary according to the operating conditions of the primary plant. During nomal full power operation or hot shutdown conditions, the items which require cooling vnter are the main _cnolant pump and the nonregenerative heat exchanger. During cold shutdown conditions, the only piece of equipment which requires cooling water is the shut.down cooling heat exchanger. The component cooling system acts as a buffer to prevent radioactive main coolant system vater from leaking into the river water, or prevents river water from contaminating the main coolant water. The system also mduces the fotling of heat transfer surface in equipnent being cooled since the component coolius water is of a higher quality than the river vater; / therefore, maintenance time on vessels which are radioactive is reduced considerably. The component cool,ing system handles non-radioactive water containing che.ieals for corrosion inhibition. The system equipnent is not constructed of stainless steel or other materials having high corrosion resistance with the exception of the surge tank which is corrosion protected ( to prevent corrosion at the air-vater interface. In general, carbon steel piping with carbon steel, cast iron,or bronze valves is used for this system. During nomal full power operhtion or hot shutdown, the total cooling load on the component cooling heat exchanger is 687,000 Btu /hr.at a total component cooling vater flow rate of 67 gpn. During periods of feed and bleed or during periods af increased purification system flow rates prior to shutdown, the total cooling load on the component cooling heat exchanger is 2,055,000 Btu /nr. at a total component cooling water flow rate of 133 gpm. During periods of cold shutdown, the total load on the component coolirig heat exchane;er is 1,000,000 Btu /hr.atatotalcomponent cooling vnter flow of 130 gpm. f 1 e @ 3 o: a}!c a i js} l l . !} n {l i I - ); , j 2. . - . < r .1 ._ -- -- .,~..,_,,.~v,..,~. ..-. ~ _.. ..........., , , ,. G -4(, { ! $ g g . . '...,.. . .},g 3 I : t _...............-.3 ! h I - @-i L-@ ! O :l!.- fu. j l. ,.l ! ! ?i (h , { El - E' ! v,t t i i i, t v,x ].1I I *aw b, yt'. t 4.** y 2a .<.<. s"g g.: r- - - - -- U. l a :l ;),p; , o { g ,3 ' t(4419 tahr , Y g
- I lf,9J9 *(a,d i
' i3 . et j I, i - Fkl t... ..,.p g e g t . . . .;t.,p 3 i g ,i ._ a <f lg ra'.jef h:et ~4 ,t11 lhre 1 f<. +ee H1 pi g ) r f g, a o E, . A a 1 8 i - L1UI.1 jr4 - .3 o 1 e p g t. 'b !:! g s- ~ + g . .. *g . f3 l (.' [ I
- i 5:J.
3<l j$ , .I
- . o
.t**] e ** ** ****' 7 us_ e .tj , (1>***."8; .s v.s . ? Q- . .O <
- 4. . .s
) L i* d2 "I e . ' : -+e [.",o] 3 p g- @.- ((rt'*' p . [ . u {' & D'ktg ,s + l H , $ b b DO-- .1 .x-.-F.i a m+ y1 t -9 {3 ~, 7.~[ 5 FIGURE 208-1 9 .. .. . l 2v 209 - CHEMICAL ADDITION SYSTEM A. Fbnetion The chtmical addition system is designed to prepare and supply a source of boric acid as a neutron poison material for the main coolant system during cold shutdown, to prepare and supply borated water to the storage well system, to add hydrazine and lithium hydroxide or potassium hydroxide as required to maintain the oxygen content and pH of the main coolant water, and to add, if necessary, decontaminant solutions to remove radioactive corrosion products from the various plant systems. B. Description The system consists of a steam heated boric acid tank, a centrifugal pump for mixing and circulating the boric acid and decon-taminant solutions, a chemical addition tank to supply other chemicals, and the associated piping, valves, fittings and instrumentation. The system is located outside the containment vessel. Figure 209-1 is a flow diagram for this system. C. Components
- 1. Boric Acid Tank The boric acid tank is a right circular, cylindrical vessel
( of 5,0,cu.ft. capacity with a dished bottom and flat top, half of which is binged to give access to the tank interior. The tank is a welded vessel of Type 304 stainless steel except for the steam jacket which is carbon steel. The jacket is designed for 10 psig and is protected by a sentinel relief valve. The boric acid solution is heated by low pressure steam ' supplied to the tank jacket by a manually operated valve.
- 2. Boric Acid Tank pump The boric acid tank pump is a vertically split, centrifugal pump with all wetted surfaces of stainless steel. The pump capacity is
+ 30 cpm at a total dynamic head of 70 feet of water.
- 3. Chemical Addition Tank The chemical addition tank is a 15-gallon cylindrical vessel with hemispherical heads. Piping is provided for filling this tank with oxygen and pH control chemical solutions. These chemical solutions are fed into the purification surge tank by degasifiedjpake-un_ water which is bypassed through the chemical addition tank.
D. Instrumentation and Control A locally mounted temperature indicator (TI-23) Lis provided , for the tenperature of the contents of the boric acid tank. The boric acid tank pump receives power from a motor starter in Motor Control Center No. 2. The motor is controlled by " Start" - 3/10/61 - . - . _ - - - _ . . - - - _ . , - . _ _ . . - _ _ ~ _ _ - - - - . . . - - - _ _ 209. "Stop" pushbuttons located at the pump and by key operated pushbutt.ons located on the starter unit in the motor control center. E s key is remavable from the pushbuttons in the " lockout" position only. hed and I green indicating4'1ghts are also located rn the starter unit. E. Design Basis The system piping and equipment is designed for two pressure temperature conditions. The degasified make-up water line downstream from valve V-lh to the purification system, and the piping associated with the chemical addition tank downstream from velve V-311 to the junction with the degasified water make-up line to the purification surge tank are designed for 150 psig at LOOOF. All other piping and equipment in the system, with the exception of the boric acid tank steam jacket, is designed for 75 psig and 2000T. All connections between piping, fittings and valves carrying chemical solutions are of welded construction except the pump which is flanged and the chemical addition tank till pipe which has a screwed cap. Threaded connections are used in the steam heating piping. The piping and ecuipment carrying chemical solutions is Type 30h stainless steel. Steam piping to the boric acid tank jacket is cerbon steel. The piping between the boric acid tank and the charging an6 scorage well systems is steam traced to provide sufficient temperature to keep the boron in solution, l g (bj' ~ r. A .] Y l l l l
- f
Aw r,- A-sum'.A-+w4. m--.---__ 6 $A s %4MA-A-.L------Geaw . - - , - LA-ps 44- --oom meb He--4os . k-.- 4,a,- .,_.m - - mo s s+_ - Lae a wL -m--,a. -Ar --,Ar-A. 4 i til *i a, } ; N , ; 'Ijt f l 4 4 ,9, t e- .r 1 ) , f * .. o k l / t' % 6 h* . i p t* ~ '1 Hl c3 h y ~ N { t .5 kN ~~, L \ ,:.k '_ ,i a e - \( n t{ I + f f \ S' ( 4 g 8 I g h - a 8 \ I Ise < () g 1 I- t , M,- * ,-- +,. !" 1, ,
- u Q
( {3 ! N.el # O-4M
- Tj i t s y I.f,j
@i .'< - n'.f , y ., /gl .x,'a g' l wpfj'. ; , si t ; b $. h 1 t : 5, y-r {$[ /--- b. M e d +}- . .> .s - . N I--4.a. .w w bi, .. t, et ; o l t I f ' 5 .. .I k. i, [ E.- f !
- n. . . . . . . . . . . . 4.u_ _._. .; 3 ..... ,
58 - } gg .{ 1 , FIGURE 209-1 210. 210 - O}& LING AND LEAK DETECTION SYSTD1 A. Function The sampling and leak detection system is designed to provide a source of main coolant system w+sr for analysis; to provide a source of pressurizer vessel vnter for analysis; to provide a sample for determination , of boric acid and purification demineralizer efficiency; to provide a samplet for determination of storage vell demineralizer efficiency; to pvide a source of storage well vnter for analysis; to provide indication of leakage past the inner reactor vessel head gasket; to provide indication of leaksee past the inner gaskets of the pressurizer vessel spray flange, pressurizer vessel heater flange, main coolant pump end plate, main coolant pump casing flange, and steam generator manvays; to provide indication of leakage thmugh main coolant systm and auxiliary system valve leakoff connections; and to provide an indication of reactor vessel shell leakage. B. Description
- 1. General The system consists of piping and equi}nent located both inside and outside the containment vessel. The sampling portion of the system is composed of piping, valving and instrumentation necessary for transporting the sa=ples from the source to the sampling station. Two sample coolers are provided to cool the high temperature, high pressure sample bomb effluent, y and a vacuum m is provided to evacuate the sample bcubs. The leak i detection portion of the system is composed of piping, valves, and instrumen-tation located entirely within the containment vessel. The flow diagram for the system is shown on Figure 210-1.
- 2. Main Coolant Sample This sample line is connected to.the main- coolar.t loop on the l pressurizer spray line takeoff and provides a source of high pressure, high temperature main coolant for analysis. Thelineisconstructedof{-inch stainless steel tubing and is designed for 2500 psig at 650 0 F. The sample is piped through the containment vessel into the sample room and returns to the containment vessel where the samnle line terminates in the purification system ahead of the nonregenerative heat exchanger. A flov-through type sample bomb, along with isolation valves, is provided for obtaining the sample . A sample cooler is provided downstream of the bcab to insure that the vnter vill not flash to steam when it returns to the purification system.
3 Pressurizer Vessel Sample This semple line is connected to the pressurizer vessel below the lov vater level line and provides a source of high pressure, high temper-ature pressurizer vessel water for analysis. The sample line is similar to the main cooleet sample line above. Purification Demineralizer and Boric Acid ( Demineralizer Inlet Sample This sample line is connected to the purification system piping upstream of the decineralizers and provides a source of demineralizer influent //61 7 , 210.: l Tnis line is designed for 150 psig at k000 F and is vaterforanaly} constructed of -inch sis. stainless steel tubing. Flov through a bomb type sample bottle, along with isolation valves, is provided by the sampling pump. The sanple line returns to the demineralizer's inlet line downstream from the take-off point. 5 Purification Demineralizer and Doric Acid Demineralizer Outlet Snarle This scmple line is connected to the purification system piping downstream of the demineralizers and provides a source of demineralizer effluent water for analysis. Tnis sample, when ecrnpared with the demineralizer inlet sample, gives an indicgtion of demineraliier efficiency. This line is designed for 150 psig at h00 Fandisconstructedoff-inchstainlesssteel tubing. A flow-through bomb type sample bottle, along with isolation valves, is provided for obtaining the sample. The sample line returns to the purification system dovnetream frcrn the surge tank.
- 6. Storage well Domineralizer Samples These sample lines are connected to the storage vell piping upstream and downstream af the demineralizer and provide a source of ,
storage vell inlet and outlet water for analysis. These lines are designed for 150 psig at 4000 F and are constructed of }-inch stainless steel tubing. The lines teminate in the sampling room. 7 Reactor Vessel Shell Leak This sample line is connected to a pipe nipple protruding frczn l the reactor vessel shell and provides indication of leaka6e past the inner shell of the reactor vessel. The line is constructed of f-inch carbon steel tubing and teminates at the vapor container cold sump. A relief valve is provided on the line to prevent a buildup of pressure above 50 psig in the outer vessel layers. A local sample 1W is provided at the inlet of the relief valve for obtaining quantitative samples. *
- 8. Reactor Vessel Gasket Leak This line is connected to a pipe nipple leading frczn the space between the inner and outer gaskets at the reactor vessel head closure. The l
line is constructed of atainless steel and carbon steel tubing designed for 2500 psig at 6500 F and terminates in the sampling room where quantitative sampics can be obtained.
- 9 . Reactor vessel Seal Weld Leak l
This line is connected to the reactor vessel between the outer l, gasket and the seal veld to provide indication of leakage past the cuter gasket at the reactor vessel head closure if a seal veld is required. The line is constructed of stainless steel and carbon steel tubing designed for 2500 psig at 6500 F and teminates in the stunpling roam where quantitative sanpas can be obtained. 7/61 ._ - _. ~ -__- .-. __- - _. _ , - - _. - - - - - . - - 210., l
- 10. Gasketed closure Leakoffs These liner are constructed of 3-inch carbon steel tubing designed for 150 psig at 400 0 F. Each leakoff line leads to a relief valve which discharges into a common header. A leak from any of the closures vill open the relief valve and trip a flow alarm.
- 11. Yalve Stem Leakoffs Leakoff connections are provided for auxiliary system valves which handle niicac11rc_yalr.r_,at system pressures on the stem side of the valves.
The leakoff lines are constractalof d-inch carbon steel tubing and are designed for 150 psig at 400 F. The lenkoff lines inside the containment vessel are collected in a valve lenhoff header which is connected to the cecnon leakage vent header closure lenhoffs. Excessive leakage from the leakoffs vill trip the flow alam. At hot shutdown, a throttling valve in the lenkoff header can be closed and the local pressure indicator observed for indication of leakage'into the line. A relief valve is provided in the line to insure that the valve packing is not subjected to high pressures when the throttle valve is closed. C. Components
- 1. Sample Coolers _
The sample coolers are tute in shell type coolers. The shell is '- constructed of stainless steel and the tubes arg of Inconel. The design conditions for this cooler are 2500 psig at 650 F. l
- 2. Samnling M y The sampling pump is a small canned rotor pump with a capacity of 2 gin at a totp dynamic head of 70 feet of water. The pump design pressure is 150 psi at 120 F.
D. Instrumentation and Control
- 1. Pressure
' Pressure gages (PI-29,30,34,35,36,37,38,39 and 40) are provided on leak detection lines to give an ir.dication of leakage frcn the ccuponent being monitored. In addition, Ir ally-rounted pressure gages (PI-28,31,32, and 41) are provided to indicate sample bcub presuure. Provision is also made for the remote recording and alarming (PR o3 and PA-25) of reactor shell pressure. Pressure evitches (PC-21 and PC-22) are provided to close an associated valve in case of abnomally low pressure in the sample bcub lines.
- 2. Flov Amored rotameters (FI-23, 24, 25 and 26) are provided to indicate the circulation rate through each sample bomb. Provision is also made for' the remote recording and alaming of leakage flov from the reactor vessel shell I and the leakage vent header.
/7/61 y0 210.4 l l E. Design Basis Since the sampling and leak detection lines cczne frcrn oyste:ns having various design pressures and temperatures, each line is designed in accordance with the pressures and temperatures of the sample source. The piping, valves and equi}rnent for sample lines that are recirculated are constructs d of material having a corrosion resistance equal to that of Type 3t% stainless steel. The piping, valves, and equipment for leak detection lines 3 and quantitative sample lines where the quality of the sample is not important are constructed of carbon steel. 4 \ l I h/61 , . , . , - .*.. ;e.. .i L.. $5b > u.., .. l f !",lt;bg 'v0 g r%4. ! rilllF j)j ILh qlpI W{ 4g Nll * ' ! L C:/ t L- -- !I n 53\ \l ., . t 3 ; ij- , ' i , ..i 'l l ,,j i g: i,. s.- ' g O' l, if*: $ (-I, I t.I, .j : Ji. : a ' ..g 3 ity +i h ,I* : y 4{, g e..,. -,~ . . , ni .g~9 ._ p. ,I .
- i. a. i. . . _ .,
s 2 ["6,l[ ' to ,=a= ... .. 2-es.. ! .. ..>
- g
<'il . . 41 I . I3 fh e" 8 T-e J l l , (I h ........., o I a y .pwy;.e* m .,, g "g b [ t MI ,,,,, g -- ; ; (.f.g g l p- I,pmi.e[]!j ~+ v.>., k - g s- >. q t ' t r t t s',- N }'lh \ ,... e % v ' ! h, f 4l ' *t[ '/ N l ' ;f,1') a s \(,',- \s ] " P.2 g m /,I( ; y t r... ... ... . . . . . . .. . . . . . ? ,1.,N W .. .. ....f;j: /gg, , i \, E ,/ o 7,</ ~ .. , e * < l ';;tM'f f l. i e, P I p _....4 , e i' L' a ~~~. l E (y y % I ' i g } i }I r - s p --4.5::. -- s 1 i j s W ( a
- g I r ;
'
- 2**1 r W f , ;t/ $
- r , ..g. { ).
l-e , l n v , - t { l kL ll l [f V
- g % 4 * (i'- t ge g M= g\' ,
9 i .t **~ i ! *T~ T -- ' r ~ T - p,l *7* l.. s.. ! (' ' } l v s 5......... i .....~...............................s -l g l l FIGURE 210-1 w ,- .. . - - - - - . - - _ - - _ _ - _,_. - . . _ - . - _ - - . - - ~ _ _ . - . _ - 211.1 211 - SHUTDOW COOLI!D SYSTD' A. function The function of the shutdown cooling system is to remove decay heat from the reactor core after the main coolant systen has been reduced to 350 psi, or less, and to provide spare cooling capccity for the purifiestion system. B. Description The systen is located entirely within the containment vessel and consists of a heat exchanger, two circulating pumps, piping, valves, fittings, instrumentation and control. Figure 211-1 is a flow diagram for the system. The inlet line to the shutdown cooling system is connected through the safety injection system piping to the outlet nozzle of the reactor vessel. After passing through the shutdown cooling heat exchanger, or the non-regenerative heat exchanger which serves as a spare, water is returned to the main coolant system by the shutdown cooling pumps. C. Components
- 1. Shutdown Cooling Heat Exchanger
- This heat exchanger is a flanged head horicontal U-tube and shell type unit and is a duplicate of the purification system non-regenerative heat exchanger.
- 2. Shutdown Cooling Pumps These pumps are the end suction centrifugal type with vertically split easing and back head cradle. Wetted pump surfaces are stainless steel and the pump shaft is provided with a double mechanical seal to minimize leakage to the atmosphere. Each pump is designed to circulate main coolant water through the shutdown cooling system at a rate of 50 gpm with a total dynamic head of 96 feet of water. Two duplicate pumps are provided with one used as a spare.
D. Instrumentation and Control
- 1. Temperature and Pressure A locally mounted temperature indicating controller channel (TIC-22) senses and prevents the main coolant temperature from falling below a predetermined level by regulating the flow of component cooling water through the flow control valve TIC-22V. Local temperature (TI-22) and pressure (PI-2h) indication is also provided.
- 2. Flow
( A channel of instrumentation (FI-22) is provided to monitor the ficw out of the pumps and to initiate an alarm (FA-22) in - _ _ - -_- _ _ - - _ _ ___ - - _ _ - - . - . - _ _. . _ . _ _ = _ _ - - . 211. case of lov flov. The alarm is interlocked with the main coolant pump ' breaker control circuit so that it vill not be actuated when the main
- coolant pump is operating.
l 3 Valves o Operators are provided (HIC-29, 30 and 31) to enable remote mrtnual operation of the shutdown cooling system isolation valves.
- h. Shutdovn Cooling pumpa The shutdovn cooling pumps receive power from motor starters located in the motor control centers. 04een and red indicating lights and key-operated ' Step" " Start" pushbuttons are located on the front of the Starter units _n the motor control centers. The key is removable from the pushbutton in " lockout" position only. In addition, "Stap" " Start"
'+ pushbuttons are locally located in the pump area. Each pump can also be started or stopped from the main control board by means of a "Stop" " Start" control svitch. E. Design Basis The system is designed to remove residual heat from the core during plant cooldovn operations. The heat removed vill be transferred to the camponent cooling system through the shutdown cooling heat exchanger. The above process is put into operation when the main coolant pressure and r temperature have been reduced to 100 psig and 300 F. i ,' The system piping and equipnent is designed for two pressure temperature conditions. The inlet piping up to isolation valve !!IC-31 and the discharge piping Ircra isolation valve HIC-29 onwani are desigred for 2500 pcia and 650 F. /a1 other piping in the system is designed for 150 psig and 4000 F. In addition to the standard codes for piping and unfired preocure vessels, the tube cide of the exchanger is constructed in accordance with the following special code cases and regulations governing nuclear vessels: 1270N and 1.773N . The piping and equipnent carrying primary coolant is Type 304 stainless steel. All connections between piping, fittings and valves ca rying primary coolant are of velded construction except the pump and heat exchanger head which are flanged. l /10/61 , _ w- 4. __Am-u%.-._ lee _me3..w4 Ar--m.4__A
- s. J_=A.__.- .e.--m. 4_--i md --w. _ ..ms a. m e,A_uALi.,-.aad._Aa.i. A.r ._wm.- _m-,,.,.-.ar . _,a .._
4 l Ig l, I, )..............4-; l.I 3 j t _.o _ t, ,t $rs o. e l
- ': ' ' '. ,1 i<
s L .~1, l n l
- i ,j,. h 4>.r .p
! h l r ti . ll{,-'Lef_glt b \"1,( , - y ,"d . ,. - p?, 4pvy, _,s. c.
- 1 l ., n .. a.
s.... <N , ~ Q .f .u / f . ? I :k at ; at k pi p : ni n Y 3)-fr--ll---n.h8),( g y h.a. ty3 g,l{ 4a I if !e a .s.p e .v gl . 3 ',e p 1 I . g o 6-5A l W i O' + W, x }. m I I Q ..g h
- r! ! ;i v, hyJ p, N l J, ) N
' 3, .: N r a y .....--r k k ' g M 1 / - c a e,,. . . . j O- ; e t 4 , l lhI. l ?/ i i l,y ,y ,8)jA- ~. 't I t, r G ,, .. ~!. l 3 1.:'.":2.r> --- . . ---- w m n :w~ ( FIGURE 211-1 3/27/61 .w ,, r ---w r- y -m-9 e - yi 212.3 212 ,SpTTYJfECTION SYSTDj A. Function Tne function of the safety injection system is to supply adequate a amounts of torated vater to the main coolant system toprevent colm meltdown int the event of a loss of coolant accident. B. Descrirtien The system utilizes the refueling vater storage tank and consists of tvo pumps, pipin'g, fittings, valving and instrumentation and control as shown on Figure 212-1. All of this system, except for the injection lines, is located outside the containment vessel. The two safety injection pumps are located in the yard and take auction from the 60,000 ganon refueling vater storage tank. This tank contains borated vater. The pumps inject borated vnter into the renetor vessei. through two lines which are connected to the apare 12 inch inlet and outlet nozzles. A recirculation linc is provided to enable periodic testing of the ym:rps. All piping and equignent are maintained at or~ [1 ~ above,,110 F to minimite themal shock to 'he reactor vessel nozzles. n, C. Cec:ponents The safety injection pumps are motor. driven, i.entrifugal type pumps. 'e; Each of these punpa vill supply 375 gun at 728 psig with a shut-off head of - s 915 psig. *- - % = y D. Instrumentation and Control
- 1. F1_ev A flev control channel for each of the two lines feeding the reactor vessel (FIC-22 and FIC-23) is mounted on the main control board. In case of a line rupture. the fl2X.Jn_ the line vill become abnomallyligh.
Th'TIMEll be detected by hlow controller channel, and an associated control valW'En be closed, bNerting thg.,11_ov 1 ,tpMe remainingl.ine. Another - k( coni..vi-bmd-mounted controller (FIC-21) totalizes the safety injection flow and 'st6pTthe pweps at an ndjustable, predetemined amount. l '~~ ~
- 2. Safety I_njection Pumps l The circuit breakers serving the safety injection pumps vill
; have instantaneous series trip devices only on phases A and C. A series overload l ' device on ' phase B vill sound an alam for an overload condition but vin not l . trip the circuit. Control switches for each pump are located on the main control console . Tripping cf the safety injection relay, or low pressure in the main coolant system vin also start the pumps. Starting of these pumps frcan a low pressure signal or from operation of the safety injection relay can be blocked ( by operation of a " Safety Injection Block" switch on the main control console. Closing of a contact in the flov integrating controner vill stop the pumps. //61' 7 y 212.2 /* Dreaker position indicating light are located on the control board vith the control svitches and also at the evitchgear. If,% circuit breaker opens vith the control svitch in the " Start" position (cr with the safetyinjectionrelayoperated,the"SafetyInjectionOffkannunciatorpoint on panel A of the main control board vill t,ound an alam. / P E. Design Basis The safety injection system is divided into three pressure classes. All piping and valving frm the refueling water agoraje tank to the safety
- injection pumps are designed for 150 psig and 400 F. All piping and equi;nent from the dir-charge of the high pressure safety injection pumpp to the containment
- vessel penetration valves are designed for 2500psig and 6500 t which meets the
- discharge requirements of the safety injection pumps when operated in serier.*
All piping and valving fras the containment vessel penetration valves to the. reactor vessel are designed for 2500 psig and 6500 N vhich meete + M h i requiments of flie primary plan' systems. Allpipingis49pe304or 1[ stainless steel. The system pijing is also designed to alloE dFEIEiirgT the radioactive vaste disposal system. Rif the pressure in the main coolant system or in the pressurizer I reaches 1000 psi or less d uring nomal operation, their respective pressure f detectors (PIC-5 or 3 ) oc nos a signal to a controller which automatically initiates safety injection. The isolation valves in the injection lines I (3-FIC-22Vand valve, (4V1836)3-FIC-23V) open, injection closes. Both safety if closed; pumps and the are storage started well isolation automatically k , e and continue to run until a predetermined volume of water has been injected 4 into the reactor vessel. This volume of water is detemined by the volume of the sealed control rod rocra and is sufficient to insure that the core is covered. The pumps are sized to insure adequate core coverage in the event of a 3-inch (0.0375 sq. ft.) pipe break. In addition, this gyntem is designed to intemittently pumpTva er to the reactor vessel after the safety injection 1 %, I pumps are automatically stopped in order to replenish vater that has been ; evt.porated due to decay heat of the core. ' l l
- Series alignment of the safety injection In.tcps vill be required in conjunction
~ l j .vith a post Construction R & D program. Ocznplete descriptions of the operational I changes relating to each R & D program vill be submitted as amendments to the l Final Safeguards Report. l l 3)~L ft )^*" Y" { 44 * ? .o 375 [ l ' 7/61 l a 1 p.n f f! H hll$ P Wt t' -a u, y N r'i r of [hr, *j , n
- u L
I t / IIEb"i sij .! e# g" , l b;J il?i l l t, n ,1, 9 I p' 4 -;----P??$6r5RRE ; .p.7 ._p - -. . ,i ,i 74 *i , j 4. x - 7 ........._. 4 7... ....... . l :
- . r.e - w . ., . : _g
.;_..>-- g m- ~ W -~ &C.m .- s h'd .,_- e 't ~s - ,. u. a q. . s p ,- _.-m. g ..m .u,- m l l x j .m.u i d e 5 m @H't@- l d l' m J y1 l W I..>......-............, g ( .Jt- 1 ., n .i u ~ *f ~i l M - );+_) g ,x,y ,- . g l s 1 i ^4 E ! *, .I: ;9, .I::: , , l - ! % 9 l .N \ I k e' 6 E If e/t : .i .Ia . . \ I t.* c : \ * : f ta- r, l l:1 IF d,i , 1, s % t e o e / v tE o / , .,l s a i t..._.... _...._..,... a ............... ,f ; +.u i mo , ~ (m ,ms n t..:s ms _. .g- ,.s. , r e.mA _ . _. ._ _ _ n%- .p e ;g;g,__ 9l l3 _ _ ,g m:n wrw ay,g _. -p . _ _-q'___ ._. _ _ _ 6 - l i Iit ,_ ._ _ ,,i * , gyj e =_.. . .. .. . wl ... . .:a...} t FIGURE 212-1 f u.) . A 1 i l 213 - STOPAGE WELL SYSUN l l ! A. Function The functions of the storage vell system are to transfer storage ven vater to or free the afueling water storage tank as required for , refueling operations, to purify and cool the storage ven vater, to provide a reservoir of water for safety injection, and to provide water for flushing refueling equipnent or the storage ven itself. ,. 1 j B. De'seription l The storage ven system consists of two circulating pu:nps, a heat exchanger, demineralizer,,, filters, storage tank, and the necessary piping, i valving, fittings, instneentation and control as shown on Figums 202-3 and 202-4. The pumps, heat exchanger, d wineralizer, and filters are ; located inside the containant vessel. The refueling water storage tank is located in the yard.
- Water is transferred from the-refueling water storage _ tank to '
the storage ven by gravity flow at a rate of approximate 1 0 gp jn. Check valves at the storage vell pumps prevent back flow thro Ge storage well demineralizer. Water can be transferred directly fra .the t storage ven to the refueling water storage tank, using both stora6e Weh pumps, at a rate of 2kgn. l* Cooling of the storage ven vater can be a:ccuplished using.one storage well pump and arranging the valving to circulate the storage well vater fra the ven through the storage well heat exchanger and bnck to the ven at a rate of }20 gpm. _ Purification of the storage ven water can be accomplished by using one storage ven pump and arranging valving so that ps.ranel flov exists in the heat exchanger and demineralizer. During this operation, ' flov through the demineralizer and post filter is. restricted to 15 gpn by means of a control valve in the heat exchanger outlet line. Purified storage vell water can be returned to the storage well, or to the nfueling vater storage tank. Sluicin6 vater for the demineralizer is provided by dgted water transfer .aps located in the Saxton Steam Station. Old resins are-flushed to spent resin storage tanks and new resins are introduced fra a-resin mix tank which can be connected to any of the plant's demineralizers. a During addition of new resin, an eductor is used to' remove excess water. Supply and aske-up to,the system are provided from the demera h t through the deaerated water transfer pumps. , Concentrated boric acid a ut on-from the chemical addition system is pumped' into the storage tank by the boric acid pump. . C. Components
- 1. Storage Ven Heat Exchanger The storage well hea't exchanger is a horizontal shell and
'J-tube type. It contains Type 304 stainless steel tubes which are seal 4 2/1/61 213 , velded to a stainless clad tube sheet. The design heat transfer rate is 525,000 Btu /hr. The tube side design prereure is 125 psig at 150 0 F and the shell side design pressure is 150 psig at 1500 F. A liquid relier valve is provided on the shell side.
- 2. Demine ralizer The storage veil demineralizer is a 15-inch dia:neter by 54-inch high mixed bed demineralizer constructed of Type 304 stainless steel. The unit is designed for 100 psig and sized for a flow rate of 15 ggn. It vill contain 5 cu. ft. of resin. The deminernlizer is provided with connections for sluicing recins.
3 Prefilter The demineralizer prefilter is a 120 gpn cartridge type filter of Type 304 stainless steel construction and is designed to remove particles down to 5 microns in *ize.
- 4. PontyFilter The demineralizer post filter is a 15 gyn cartridge type filter of Type 304 stainless eteel construction and is designed to
, remove particles down to 5 microns in size. 5 Storage Well Pte:ps i . The storage vell pu: cps are horizontal, centrifugal pumps with mechanical seals. The pumps are each designed fc.r a capacity of 100 gpn at a total dynamic head of 205 feet.
- 6. Refueling water storage Tank The refueling water storage tank is 27 feet zn diameter and 19 feet high, constructed of t-inch thick carbon steel. The tank has a storage capacity of 80,000 gallons and is provided with a series 300, four g coat catalized phenolic protective lining made.by the Carboline Corporation. I 0
Stee.n heating coils su' 'icient to maintain a temperature of 75 F are installed in this tank. % D. Instrumentation and Control
- 1. FA A flow control channel (FC-357T) p2ovides a signal to valve FC-356 to regulate the flov through the storage well heat exchanger to maintain 15 gpn through the demineralizer.
- 2. Level The storage well is provided with a high level switch above the j g refueling level and a lov level switch below the operating level. These- i
) t switches actuate an annunciator light and alarm in the main contro,1 room. ,
- /i/61 .
- - - . - - . - . _ . . - . . . , _ _ _ - _ - - . _ . ._-.~ - . -- - 213 3 3 Pressure A pressure switch is provided on the shell side of the storage vell heat exchanger to trip the storage vell pumps if the chcIl side pressure (River Vater) does not exceed the storage vell vnter pressure, thus preventing leakage to river.
- The shut-off valvo in the storage vell fin line vill close immediately on signal frcan either high containment vessel pressure or initiation of the safety injection system.
- 4. Btorage Well PJ:nps The storage well pumps receive their power from motor starters located in the motor control centers. Each is controlled by n " Start" -
"Stop" control svitch located on the main control board. Green and red indicating lights are provided with the control svitches. 5 Temperature A temperature indicator-controller is provided to sence the temperature of the vater in the refueling vater storage tank and to regulate the steam to the heating coil located in the bottom of this tank. E. Design Basis - The storage vell system is capable of transferring 80,000 gallons of k borie acid solution to or from the storage vell in approximately 5) hours. The storage well demineralizer, acting as a 15 gp'n bypass polishing unit, vill remove the fission products which may contaminate the storage vell vater L.e to defective fuel elements exposed to the vater during refueling prior to their storage in cans. The demineralizer vill also i remove corrosion products which come from components transferred during refueling and from other surfaces exposed to the sater. l l The heat exchanger tube side operuting pressure vill be 75 psig and l the shell side operating pressure vill be 100 pois, hence tube leakage vill i result in river vater indeakage to the storage vell vnter rather than possibly contesinated storage vell water leakage to the river. The demineralizer vill also remove nolubles that vill result frcan this leakage.' l All valves, piping, and equitanent, except the -storago tank and the storage vell, which are contacted by storage veil vater, are made of Type 304 stainless steel. The refueling vater storage tank and the storage l vell are provided with a protective lining. , 0 The water in the refueling storage tank vill be maintained at 75 F t j l or above at all times in order to minimize thermal shock to the reactor vessel noz::les and to prevent freezing. ,a f h/61 . 214.1 214 - COOLING,HFATING, AND VENTILATING SYSTDG A. Function Three systems are provided to cool and/or heat and ventilate the various potentially radioactive areas of the plant. In addition, entirely separate systems are provided to cool and/or heat and ventilate non-rad.oactive areas. These potentially radioactive systems are exhausted by a co:mnon exhaust fan and the exhaust air is monitored prior to release via a ccrmon stack. The function of the containment vessel cooling, heating, and ventilating system is to maintain the interior atmosphere of the vessel 0 between 50 and 100 F and the relative humidity at 60% or less, to protect personnel fro:n air-borne contaminants by providing continuous air filtration in each compcrtment, and 1o provide for purging of compartmencs prior to access by plant personnel. The function of the heating and ventilating system for the vaste treatment plant is to supply sufficient heat to the various building rooms to prevent space temperature frcxn falling belov 55o F and to provide sufficient fresh air during times when the vaste treatment plant is operated. The function of the control and auxtliary building
- heating and ventilating system for the areas subject to radioactive contamination is to provide a separate air supply and exhaust for these areas and to provide heating to maintain a temperature of 700 F.
B. Containment Vessel Cooling, Heating, and Ventilating
- 1. General Description
( A senematic flow diagram of the containment vessel cooling, het. ting, and ventilating system is shown on Figure 214-1. This diagram also - shows the connection to the stack of all ventilating systems which handle s potentially contaminated air. Each of the four major containment vessel I compartments vill be conditioned by a separate air handling unit which vill constantly recirculate and filter air. Units for the operating and auxiliary compartments vill cenain a cooling coil supplied with river water and a heating coil supplied withsteam. Units for the control rod and primary compartments vill contain a cooling coil only. River vnter rupplied to the coils vill be controlled by a themostatically-operated valve. The ventilating function of the system is performed by apparatus which is independent of that vhich filters, cools, heats and recirculates air in each compartment. The ventilating apparatus consists of a supply unit, a high-efficiency filter and air exhaust fan, all located outside of the containment vessel. The heating and cooling apparatus operates continuously , during nomal operation. The ventilating apparatus vill operate to purge the vessel as a prerequisite to entering and dHPiTg its occupancy. Control of the ventilating apparatus will be manual. The supply unit contains a conventional dust filter, a heatin6 coil and a fan. Air flowing fran this unit enters the operating area of the containment vessel and flows through the auxiliary and primary compartments in series in the order of increasing radioactivity. An exhaust duct carries-the \ air from the primary compartment outside the vessel to the high-eificiency ( - filter and exhaust fan. This fan maintains a slight negative pressure in the primary compartment so that air leakage vill T,end. to flow toward areas of /1/61' (w 214.2 increasing radioactivity. Air from the exhaust fan then flows to the stack fan and thence to the stack for atmospheric dilution. Since the control rod room and the reactor compartment are not in the natural flow path of ventilation air, special provision is made to ventilate these spaces. The control rod room is provided with a small exhaust blover which vill induce a flow of air into this compartment from the auxiliary compartmer i The exhausted air flovs into the primary conpan. ment. The open ends of the intake and exhaust pipes are at an elevation hLgh enough to prevent overflow should the control rod compartment become flooded. The reactor compartment t.an be purged by opening a damper in a duct between this compartment and th9 excaust fan, closing the damper between the primary compartment and the fan, and by removimg one section of O the covered grating over the reactor compaatment blov out openings. Because of the relatively lov velocity of ventilation air moving through the operating area, a supplementary recirculating fan is provided to assure that good mixing of the ventilation and ccupartment air vill take place.
- 2. Components The pertinent characteristics of the system components are listed in Table 214-1, below.
, TABLE 214-1 \ _ CHARACTERISTICS OF CONTAIN'ENT VESSEL VENTILATING EQUIWINT Outlet Flow Rate, Velocity, Unit efm. fpm Inlet Filters
- Operating Area Air Handler 8,000 1920 High Efficiency Primary Compartment Air Handler 5,750 1680 High Efficiency Auxiliary Compartment Air Handler 940 1130 High Efficiency Control Rod Compartment Air Hanaler .2,710 1750 High Efficiency i
Operating Area Air Mix'7g Fan 20,050 - None Control Rod Ctepar A d 0 . Ventilating Fan 420 - None Containment Vessel Air Supply Fan 10,000 1465 Standed . Cleanable o Containment Vessel Exhaust Fan 10,000 2400 High Efficiency
- High Efficiency filters vill have a cartridge media having a filtering efficiency of not less than 99 95% when tested with 0 3 micron dioetyl-phthalate smoke.
3 Design Basis Heating and cooling equiT raent is provided to maintain all compartments at a temperature lover than 1000F and higher than 500 F. In ( the operating and g2xiliary compartments, humidistats vill be used to maintain the relative humidity at 60% or less. ./1/61 214 3 The containment vessel accessability criteria is based on the assumptions that main coolant is leaking into the containment vessel at a s continuous rate of 30 pounds per day. The main coolant fission product concentrations used are those resulting from 1% defective fuel rods and it is assumed that all the gaseous and volatile nuclides, namely the huons, Kryptons, and Iodines, are released to the air. C. Vaste Treatment Plant lj, eating t and Ventilating
- 1. General Description A schematic flov diagram of the vaste treatment heating and
~* ventilating system is shown on Figure 214-2. Outside air enters the building through two air handlers which filter and heat it to a temperature of 550 F. One air handler discharges air to the control room. From here it goes to the , pump and compressor room and then it flows to the exhaust fan in the evaporator and gas stripper room. The other air handler discharges air to the drum shipping room. From here it flows to evaporator concentrate room and then to the exnaust fan in the evaporator and gas stripper room. Air entering the exhuast fan is filtered through a bank of pref 11ters and high efficiency filters and is discharged through a duct in the trench to the stack fan. ' Steam unit heaters in the0 various spaces of the vaste facility vill maintain a space temperature of 70 F in the control room and 55 F in the other rooms. The unit heaters are independent of the ventilating system.
- 2. Camponents k
The pertinent characteristics of the system components are listed in Table 214-2, below. TABLE 214-2 CHARACTERISTICS OF WASTE TREATLET PLANT VENTILATING EQUIPMENT Outlet Flov Rate, Velocity, Unit efm. fTrn , Inlet Filter Air Supply Unit - control room 2000 2410 Metal, viscous i coated Air Supply Unit - drum shipping room 4000 1740 Metal, viscous coated Exhaust Fan 6600 2120 Prefilter-standard dust, Main filter - High Efficiency 3 Design Basis
- Air flov is based on an assumed air change rate of 30 changes'-
per hour in the drum shipping and evaporator concentrates room and 20 changes -{ minir.n:m in all other rooms. The exhaust fan is sized to headle 10% uore air than the supply fan so that a negative pressure is maintained in the l ventilated spaces. l /10/61 214.* D. Centrol and Auxiliary Building Heating and Ventilating
- 1. General Description A schematic flov diagram of the heating and ventilating system for the potentinlly radioactive areas of the control and auxiliary building
- is shown on Figure 214-3 This is a separate system which supplies outside air to the monitor room, instrument repair room, decontamination room, auxiliary equi}nent room, charging system room, sampling room, chemical preparation laboratory, and counting room. An exhaust fan discharges air to the stack fan. Each room is connected tc the supply and exhavst ducts in parallel to prevent spread of contamination. A separate air handler and exhaust fan is provided in order to supply 3000 cfm of outdoor air to the chemical laboratory when hood ventilation is desired,
- 2. Camponents The pertinent characteristics of the system components are listed in Table 214-3, below.
TABLE 214-3 CHARACTCRISTICS OF CONTROL AND AUXILIARY BUILDING VENTILATING EQUIPMENT (FOR RADIOACTIVE AREAS) Flow Rate, Unit efm. Inlet Filter i Air Supply Unit 8000 Impingement type dust filter Txhaust Fan - Main 8800 High Bfficiency Chemlab air supply unit 3000 Impingement type dust filter Chemlathood exhaust fan 3000 iiigh Efficiency 3 Design Basis In the potentially radioactive areas, the outside air suppb.y for ventilation is based <on an air change rate of 20 changes per hour for removing possible radioactive contaminants. Air from these rooms is filtered and exhausted to the yard duct system maintained at atmospheric pressure or below and then discharged through the stack fan. The exhaust fan is sised to handle more air than the supply fan so that a negative pressure vill be maintained in the ventilated areas. Exhaust fans used for ventilating other areas of the building dibcharge directly to the environment. E. Instrument and Control s The control and auxiliary building radioactive area ventilating system fans, the stack fan, the containment air supply and exhaust fans, and the control rod room purge fan receive power from combination motor starters - located in Motor Control Center Number 2 The vaste treatment plant supply fan, exhaust fan and evaporator concentrates room supply fan receive power from combination motor starters located in the RWDF Motor Control Center. [' The control and auxiliary building radioactive area ventilating system fans receive power from locally mounted starters that receive power from Motor Control Center Number 2 by way of the hko V Power Distribution Panel in the auxiliary equ% ment room. ./10/61 l t 214 5 The stack fan is controlled by a " Start" - "Stop" control svitch on the main control board. Green and red indicating lights are located with the control. svitch to indicate"Off" and "On" respectively. The containment vessel purge fans are electrically interlocked so that they cannot be started unless the stack fan is running, and so they vill trip off if the stack fan trips off. The contain= net air supply fan, containment air exhaust fan, and control rod roo:n purge fan are controlled by a coc:non "Eturt" "Stop" control svitch on the main control board. A pair of red and green indicating lights for each cf the three fans is located with the com:non control svitch. The vaste trec.tment plant supply fan, exhaust fan and evaporator concentrates room supply fan are controlled by " Start" "Stop" pushbuttons located on the starter units in the vaste treatment plant motor control center. In addition, the evaporator concentrates roa:n supply fan has a " Start" "Stop" pushbutton station located just inside the door of the evaporator concentrates roocr. Red and wreen indicating lights are located on the front of each starter unit. The ;xhaust fan cannot be started unless the stack fan is running.and netaer supply fan can be started unless the exhaust fan is ru ining. If the stack fan trips, the exhaust fan and air supply fans vill trip off. The control and auxiliary building radioactive area air supply fan and exhaust fan are controlled by " Start" "Stop" pushbuttons located o on the starter enclosure. The chemlab ventilating system is controlled [* by " Start" "Stop" pushbuttons located in the chemical preparation room. The exhaust fans cannot be started unless the stack fan is running and the supply fans cannot be started unless the exhaust fans are running. If the stack fan trips, the exhaust fan and air supply fan vill trip off. Red and green lights located on the main control board indicate the o operation of the contro_ and auxiliary building radioactive area air supply fan. The decay gas release valve is electrically interlocked with the stack fan so that it cannot be operated unless the stack fan is running. If any of the fans associated with the containment vessel ventilating system, the control and auxiliary building radioactive area ventilating system, or the stack fan trip off, a coc::non " Fan Off" annunciator vill be operated on the main control board. /1/61 . .--- - -- - -_-w. - - , . , - , , - - - - - - - - - - - - . - - - - - . , - - , I % _ ~ .- e . ( 4 v
- y. 4~0 % .. s4,.
- W,- .- Q. 1-
.c. n14g r q r '*
- Mid
~ l . , a . l mY.] . ( e; . , , // 1. g 7 . .. :- -*-:~ ' '.(l * -) 1: .. ,. m w ymde . t nM g- . g . .- , 3 m .. g '. . ,.E 0 LI . .'".a .,1.W, .d d. ;( , .. 1. v[ 65 l I"' k v
- v.
cu .,, __d._4 w .. ., = .l. , !) New? - s - f f, y ,sk. ~ a g h. . . . ,,, ,n nf . MH l M7f4
- 5. *
- L , ,
w -.
- .4. ; -
': . 4*i.: ;;t . as #, :2 -b a I ~.
- nn
,m. -._' we ir- g j, .,* .ar% , , c p. _,..y f9y A y , , . 3,g,@g,+.- ~ ) . N. * {. , r
- yW ,e ~- r %:s
- 4: h,&*s,- fh?4) &2 , ,
, , ~ , - . . . I ~,*7 ,' .
- p #
. 1. 1' . s n y n e* Ib W D & q, i en9m 4 8 3 S O is - 9 * . P
- D D M
> W j M M '" 9 O 4 > p gr W- -- as 9 N4 u. e= n = g np = mo e. .a e. - =g l g me \ g g _ Ml. M -- e M M M I. . _ , . _ _ I I_ my me o c s, - I **-4 M 4 . o. g *c cauglasma n = * '* ap og a . . o g, g i = . - * .l t. . u . e .s - lC. so = n e at 3 3 M O * =4 O es a n 1I IiM e g '. 2 . . - - , , 2 c ,, v ! "-* 98M9f'* 1W e $1P4 491f* f 4* 4 y h
- 5 N
- '-C3 - q ,1 p, <r,, , ,' o k g_; op , . , , .. y ,, p.: CE ' I y 9@ u ,c .., ( , j a& .gg,[ y .. geww .r m.up ..Yt N < v.: "n r jr ri:m M - - *M $t . l i. O- e 9 es .y . ,, .v g. , ; .* %
- e aH
- ' di N5*'s f f'f 5 .gi. :j. 4,im W. :c -ggggggg p ,;w, + g 4 t ,'- d-$f*I2M-* /1= %(t _. w * . Jai $',ff,4,^ ._m _ y ,<.r., gj ., z.w7%., 3 ~- g w A' $c gf f' ~
- h vg.,
e- ) Wh s - . n 'M h.k i . _ _ _ , %' .J -% -
- AE ~_ p ar 4- .A%.
s- ,, s y M.,f -- 2Gh0USE ELECT (1 - L Z__ --k . . t g - O.s ig'? e$aston Reactea Frsject y ; r eer g p:n ,e-4 ;y.g g w w
- p 3, ,p.. i - $u G> 9, h -.. -
-; y s t) 4 g k , ., 4> J.# Evilaing Service . 'r ' - j .p f_f ,7 % ,h " sa? ~ ~' ' Air tlos Ciagrsa Of - * , r 9 - '
- p. 'K M 3
S , % g .~,
- 4 4g Y, T;1 ,' C
+ g g* ; y u % ,a w g} g M 3 14 -1 I M % .ir 4 .' 2$ n'
- s 's 't i?
? [x - Als NAa9 Lit .: 5$ $# ; .1 W d ~- 4 y" 500G Cfu ' $ 9 h17 : e 1 i a k. . g v. Ii , ,; o.. 3, I,, l' T f*1 7 ca as t hn 0 )y. gvAP, garr l [ j ^J ' ( 1 '. # * -, 5000 W sa PPig - Y- ! 'd COMPT On f)j "f (-4 r ' '3 'b aOC's 3, . - " I J. i 7,400 fi 3 t' I e ', y
- l. + gQ ,3,0s0 FT (.
y 4 c. ' IY -\ d .Nr #$ y ; ~ All ESLTLE bmELTinaCelt & 31 N ' t. , ' hh [-. k' .11 r - m2 - .I W ' f .. j ; ~ . ( i y G,a
- 4000 CM
- h. e :~&,!,-*
!. n- -5 y- i , 1f cy . t- ) I p .a 2 6. i V - f ? j' g 'T .i ,' T f, Q 1 d3 Id i l } f . ._h y ",; . y > ... 4' ?* j E i,
- j j s
6-PREFILTER$3 Q"#P*$. ' } An e " Ata fitter .,A ' 6-FsLitas l A2 - nEAttsG CCIL *! I' f ' 'I ' -; i N_1 _ '['s -. _ _ . > j' M-l Is 8 i - - -]200CCFw 1 -_ 00 180L 2000 fu PUMP & e re. . EVAPO4AT08 1.40s5000CFMSUPPQa4,800, ; j ! h 6 " Coe6P. RM, p $fW . AC - -t 4t J ACOM - ITalPrta accM w e CFw To stACE JW ' I ~ ~ ' JL,_.- ! . .L._. / . ._ 5.930 F13 g S 260 FlI . l l 13.75C F1 3 I 9 . j[i; l ' / w n- +%. Asa acun
- cco uw ghr } Eg5'd'" g gy
, p.- 9 . m OV l t 4 1 N , e ,. s's ,/ , i j W , y 9 * , g> , k'4 L JJ4 .. 7 J.4 -g . m sw,J u.x, a ' _. l { t S .. ..
- pd wM_y, ?'
g ' s.e,:~s n gn V .. ; n . w .s r r - - -+ - - - - r - - - - - - - - - * - -- - 'i .. - a i ,i i, s - . p< u: - i I . P n i - ' J Y. . .2 drI il --+ J j i .wm,ggw ; t sp i t ,. . . w a l g w; - - ;r ., ,. _ , 3 " + w:wd x 'b'l I i : j =. egg, . , t s ., e v . s@. . w a t p I .- >. ,. 4 ; I, y - . .-r l . ,._____._+_._______j e n ..p Lgfyg._ ; ',, f"
- gi _ g _ _. ._ ,
- + Wu - l t g ...my ..n . i - x l f4 - l 1 /g ' l j I L +-- Q 3 sr-------+-_-- -.y .wei , e I .q. u , l d;c4 y. , \
- x l -
.e 1 - I . _ ,_ .1 -l- . ,# {- I i; u ._ _ _ ; + - z l l } l l _.. ... -t , .. . p 4 , g _ 9 % e- e--m r==_=.---- S Y y$4 ygj3 y. ' ; % .' .f~p pP% .6$' gP ~ 7 ; .;.q . m+k.* , p.c- W A _. y - q f_a :P %wc,. . = . . _ . , , ~ _... - .f.. __ _ _ '" MS- . >:o.q g .jMl ' I a m ; y ,. ,_,_ _ _ HW; 4 - ;.t? qg- g.g .. e. 7 t ;; ; i !. . . .. ) m -- - p., 3 r --+----a ___-r__ 1 I . ,e g. .,,m .e l +- ! ----- ,l i u!E ' y, .=O.. .- O i h. te ,4 Y eD .I I .. q . .. . 6 i " * - _ _ _ g L _ _ ._ %v_ - -p. _ D . t~ ,i. g?: < .q - E i ,* I J 1 t._--____. _ _ _ _ _ _ _ , _ _ _ _ _ . , l I ..g' w - . m ._ . _ _, ,;._, .. g : ,,, y + aa I T 3 * '- l $ ' c- gx q y u". 3, m, i , c, . , -1 ,.i - mm.<. e >s I, . 4 . ;. 1-4 ,en,>. . n a ]7* = u 'h ..##.c7 e 2 , , . 8I C I# $ * -ec r i shy 4... $.?>4. p.. gp%,kA*g.f. ,n. a&u . gg. J ' . . .J k' 4y 4 y g t' ' 4'
- 4. 4'
.f. i . g , A ,T ,, - 1 '/. *,,,gy, , g 4. < #~': e.' . e > . .,$ 't *[ i" ) ., I, ,.j~~+ A , %.r_. . . % .w ..y , .a . a v <- m . ~ 'id W 4' W j. [f M V .' g ..y .. .<., 215., 215 - VENTS AND DRAINS SYSTD! A. Function The function of the vents and drains system is to provide piping to collecting points for vented gases c.nd for fluids VMch are vented, drained, flushed, leaked or discharged from valves and equipent located inside the containment vessel and control and auxiliary building. B. Description The system consists of two sectiods, one located within the contain-ment vessel and one located in the control and auxiliary building. Figure 215-1 is a flov diagram for this system. Carbon steel piping is generally used throughout the system.- ' Three main headers are provided in^the containment vessel._ These are a vent and drain header for radioactive gases and liquids, a drain header for non-radioactive liquids, and a flushing header. The vent and drain header for radioactive gases and liquids collects vented gases, relief valve discharges, liquids, and valve leakoffs fran radioactive systems and discharges them to the pressure relief system discharge tank,* fran which they are pumped to the-radioactive vaste disposal facility. . The drain header for non-radioactive liquide collects such liquids and discharges them to the containment vessel sump. Fluids collected in the containment vessel sump are also pumped to the radioactive vaste disposal fac131ty. The flushing header collects flushing < effluento from the purification system filter and demineralizers and discharges 4 k them to the radioactive vaste disposal facility.. Separate piping systems are provided in the control and. auxiliary building to collect non-radioactive, potentially radioactive, and radioactive effluents. The non-radioactive effluents (not shown on Figure 215-1) consist of drains from vater closets, urinals, lavoratories,, vater coolers, and toilet and shover room floor drain. These effluents are passed through a sewage treatment plant prior to release to the river. The Figure 215-1) consist potentially radioactive-of sample effluents bomb cooling -(some water of which and drains from are theshown..on chemical addition tank, boric acid tank, boric acid pump, automatic laundry, decontamin- -ation shover and lavoratory located in the monitor room, and floor drain in the monitor room. Piping for these effluents terminates in a sump in the auxiliary equipent room from which the effluents are pumped to one_of two 12 W tgr tanks. Discharges from the monitor tanks can be made to either the radioactive vaste disposal facility or to the sewage treatment plant. Radioactive liquid drains frcan valve.leakoffs, the purification - system surge tank, the charging pumps, the chemical laboratory,'the decon-tamination room, and'the sampling room are collected and discharged to the radioactive vaste disposal facility. The charging pump housing and purification-system surge tank vents are also discharged to the radioactive vaste. disposal facility. /10/61 m ,_ ....-._-..-_.m-_.._ ,~.m., ._____m,_____._. _.__.._..._...-_.~m. . _ _ _ . - ~ . _ _ _ . . . . . . . _ _ . - _ . em };.. .....W N 8 /p< t , ,, , , x -- n . ~ .= J , 7 1:j,c.::::~cc]-4.e;pm ; t g , ,% \ M/!*45? , g i N .rH #1 U ' )l -)tc/hs f 't a b = * %
- tf ) - ,4_g {
.frf.*W 4.* 6.% ' % h. .W!s% - 4t , f } .h p .l l f~9 ._ _ s _e J-t"ty [] lI l -- >s m i yI L _ .J , .l f l .~n...~=~....... 1 .
- h. i o
## 1v -- m,. . g y . D f h M k . .. . . h-- M f I ... . ... .% 'w h l M [ <. 6 p ', $ (.__. . w _. -j _ i { -l .>,.,,,,,,, u e y; '--# / p ' e' , *" 1 { extvarg JV {y !n%; .,. -gy. Q N "f f'N1=F"':*cc i / tetts iew h.ewar . .Ma.w ...r-. i* tr p ... .g .._ g .. ~~.;L:t" "- * -...-e - g 4 \\ ee < 4 [ , / \ l ---.g r- , L... awm- s so-- ... . f- _,, i i / w.x. . _ .. 4 hI , { r, -- I l . . . . o. .w. . - - - 4 ------- "I1 'W y.v.W...t : $ I / . .J5) _ s I
- -E'
. T s_ n< .s .l h. wwp w- : ; {---159 m .,. , g u . s.ygne . . 6 - . -{'j .~. .,. .c., ) ,;.rau,...mv.y --4, t w...m.wp o 4 _.q _ 1 ? 6 ,mm.3 N . i- W ,,, 4u .., - -. l \. m.,~ s - - g m 's e ""'4'v, "--*~ f , l/ w.w- - g - ,N A.g d a.' ; / N =:W-- --L.% f N . I ~' 7.2.-- "4:? ! h . gg . *~.p $ } w ; Q FIGURE 215-1' - - . . - - __ . __ _ _ _ . _ . , . . - . _ _ . . _ _ _ _ _ . _ _ - - , . . _ - , - - _ _ . _ , _ . . ~ , . _ - g g;.. .....w ~ e 3 / {l{ j t g , ,, sem,v x ~m y. 7 x Y.f 3,'(g.f .p '.7.W .I'. W* '.".}- n..~nwW t ;Rs.musrd , - y... I#' [f q "" Tff,i?w. mnes'1a-J m .5 [ % i .mm< .5 g d r 5 } r- ' _.___> _., ? ~H t.. lI 1 I -931 ' h 1 L ._ .J fI 'I Ib , , M i* , .-- -naw... ... hi i li A - m g _......u-__ g { } -~ a 11 g ....---.}'p-._ .-.. . 4. w } { l 4 .. .m _ g ; =n.w x / 1 s g _(an.,s: -~ l @;E m - 1( jl,- . s ~.m4~.wwx r.H o o, l 2 i "' '""*%(-5M ...gy'tt m ; y g . - . 2,p'***'- g n 2P- j f ,l -- , E <\ w,r.,s-- - \ 6 + +----- j e)i )l t g ,- " , , . . . . ,--- f g t " 4 ,$ r, ~ ~ ' 1 . . .. 4 . ww _._ ~ t O --- --- 41 '"- k< ~'m'k. *=w }., / t ..% d' ,f i' : r.r, [kl g y,[, 7 ; ' y g .n_% 3L,,- - t ---T --- d'h-t g m mWf,L
- I- g I j m ~m*R m ---'2 4 %g q [; { .
( v .-7 quN wt ~~~' .E l I i =~4 e> '""'T.....,I N ,_ % y ((/ ( \ :m----- ;;., j . f } T=;::,.--.i;? [ . ._ _. . . .. ~. 9 $ a m~ ~ .s-s g FIGURE 215-1 216-216 - SECONDARY STEAM CYCLE A. Description The function of the secondary steam cycle is to utilize the steam produced in the nuclear steam generator by converting it into electrical energy which vill be fed into the Pennsylvania Electric Company power system. The major equi pent in the existing plant that vill be used in the secor.dary cycle are the Unit No. 2 turbine generator, Unit No. 2 surface condenser and auxiliaries, and small amounts of interconnecting piping. Other equipent in the existing plant that vili be' used to serve both the secondary cycle as well as the nuclear facility are a portion of the i existing station service electrical equipent, the house service pumps, the air ccxnpressors, and the make-up water treatment plant. The primary features o of the existing station are given in Table 101-1. This equipent is shown on the main flow diagram, Figure 202-1 and the services flow diagram Figure 202-5 New major equipent that is being installed in the existing station - for the secondary steam cycle include a 6-inch 1800 psi steam header pressure reducing station, an 8-inch 300 psi steam header, 175,00016. aper hr. deaeracing heater and 10,000-gallon storage, tank, two turbine driven boiler feed pumps, new condensate and feedvater piping system, steam generator blovdown tank, and a 40 g p demineralizer plant. Other miscellaneous tanks, o valves, and pumps ce also being provided as required. This equipent and piping is shown on the main flow diagram Figure 202-1. [ The unit No. 2 turbine design steam conditions are 285 psig and 625 F. Steam frcan the nuclear steam generator vill .be dry and saturated and win vary in pressure frcan 500 psig to 1600 psig depending on the test program. The pressure reducing station vill throttle the steam generator outlet-pressure to 285 psig. ' j B. Design Basis While it is not known how much saturated steam the No. 2 turbine vill psss, the new secondary steam cycle piping and equipent have been sized for a flow of 175,000 lb per hr. This flow was selected so as to have ample heat removal capacity up to the limit of the No. 2 turbine so as to provide for operation of the reactor at higher ratings. -The No. 2 turbine has a nameplate rating of 10 MW and has a maximum capability of 13 MW vith boiler steam. While most of the equi. pent that is being used or has been provided for the secondary steam cycle is of a conventional steam plant design, there are several features of interest from E safety standpoint. Isolation - In order to protect the boilers and'other equipent in the existing plant frcan possible rcdioactive contamination and also to reduce the amount 'of foreign matter contamination of. the nuclear i plant, a certain~ degree of isolation'has been provided. When the nuclear plant is' shut down, steam from the boilers'will be used in the nuclear facility for building heating, tank heating coils, (. deaerating heater, tracer heating for piping, and for the.vaste treatment plant evaporator. .The only one of these steam services /17/61 216. d that might cause radioactive contamination of the secondary is the vastetreatment evaporator and this possibility is very unlikely since the steam pressure vill be higher than the effluent vapor pressure. In addition, provision is made to sample the condensate return prior to startup of the evaporator. The main steam piping and condensate piping vill be completely isolated and flanged spool pieces and elbows are being provided to convert the Unit No. 2 back j to boiler steam. In the case of the aux 131ary steem services where /e smaller pipelines are involved, isolation has been provided by / two shut-off va'ves with an open tell-tale valve in between. Condenser Leakage - The condenser has packed tubes on both ends and conductivity tests have~ indicated a high per cent of leakage. In order to minimize the possibility of chloride stress corrosion of the steam Generator Type 304 stainless steel tubes, the Unit No. 2 , condenser tube sheets vill be coated with a neoprene coating to reduce leakage of river vater into the condensate. While the steam generator blovdown system and the make-up system have been sized to control the chloride concentration in the steam generator, this coating on the condenser tube sheets vill help to reduce the load on these systems. Turbine Driven Auxiliac ,- Turbine drives have been provided for the boiler feed pumps so as to mske it possible to fill the steam generator intermittently as required to protect the reactor core fram overheating by decay' heat in case of loss of power. The nuclear ( plant has two sources of station pover supply frca the existing station busses; and in case of a bus fault in the switchyard or a transmission line disturbance that muld disrupt the power supply ( to the station busses, a 970 KW house service turbine generator, which utilizes boiler steam, is available. Therefore, no diesel- I driven or gasoline-driven generator is being provided for backup in I case of power failure. One of the existing Unit No. 2 condensate i pumps is also turbine driven. l l The exhaust steam frcm the boiler feed pump turbines vill normally be discharged to the 15 psig deaerating heater. At light load on the reactor (below 12 MWT) there vill be excess steam in the deaerator and at approximately 1*( psig a diaphragm povered valve
- opens to release this excess steam through a desuperheater to the condenser. This arrangement minimizes the release of secondary steam to the atmosphere and reduces the amount of make-up required for the a
secondary cycle. This feature may also provide a heat sink under certain conditions such as a reactor startup or reactor scram. Vents and Drlins - Drains will be collected in a tank and returned to ILhe cycle. The deaerator vent and the condenser air ejector vent vill be piped to the 125-foot stack in the vaste disposal system. The steam generator blowdown tank is being vented to the deaerating heater.
- This heat sink would minimize or eliminate the discharge of steam to the atmosphere through the steam header safety valves.
f '17/o1 216.: C. Instrument and Control l l General - Level in the steam generator is controlled by A conventional I three-element type control that benses level, feedwater flow, and steam flow. Strip chart type reconiers are provided in the main control rom of the nuclear plant to give an indication and neord of conditions * ! in the secondary cycle. Steam generster level and pnssun; feedwater i pressure, temperature, and flow; and high pressure steam flow and pressure are recorded. Abnomal conditions such as high and low i deaerator leve.1 am alamed on an annunciator panel in the main control roca. , l Pumps - The turbine-driven boiler feed hps vill normally be started , at the pumps, but can be started from the main control roca in an emergency. The two motor-driven deaerator feed pumps which take condensate from the surge tanks and discharge it to the deserating heater am started from the main control room. If either of the motor starters for these pumps trip open, a " Pump Off" annunciator ! in the control room vill operate to sound an alarm. The demerated water transfer pumps that supply make-up to the main coolant system are controlled the same as the deaerator feed pumps. i Valves - The main steam stop valve is motor-operated and is controlled frce the main control roam by a "Close" "Open" control switch. The steam generator surface blowdown valve and bottom blowdown valve are also motor-operated andLeontrolled from the main control room by a , < "Close" "Open" control switch. ! \ l Turbine - A solenoid is provided to actuate the turbine emergency \ trip lever' automatically 'in case' of a reactor' scram < i l I. s / 320/61 217.. 217 - WATER THEATVENT SYSTEMS A. Main Coolant System (See Figure 202-4) Make-up water for the main coolant system vill be supplied from the , new 10,000 gallon deaerated storage tank located in the existing plant. The hot (2500 F) deaerated vater from this storage tank vill be passed through a heat exchanger which reduces the temperature of the water before it passes through a mixed bed type demineralizer. One 30 gp mixed bed type demineralizer has been provided for the final purification of this vater before it is fed into the primary coolant system surge tank. A cartridge type filter located on the inlet side of the mixed bed demineralizer vill remove particulate iron and other suspended matter down to five microno in size. A similar filter vill be located on the outlet side of the demineralizer for the purpose of removing small resin particules. The 30 gpm flow rate for this demineralizer was selected to match the 30 g p feed rate of the charging pumps during the bleed and' feed operation. During the period when the reactor is in operation at power, this demineralizer vill only be operated intemittently as required to supply the small system losses through leakage and sampling. The capacity between regenerations is over 400,000 gallons, based on inlet vater having 1.0 ppm total solids and outlet water having 0.1 ppm total solids. This water which vill have been deaerated, should have an oxygen content of less than 0.007 ppm and the effluent fram the demineralizer vill have essentially ;ro chlorides. Provision has been made by means of the chemical addition system 4 and charging system to internally treat the mtin coolant' system with hydrazine and lithium hydroxide or potassium hydroxide as required to control oxygen content and pH. Solids control is maintained by the purification syetem which is desuribed in Subsection 207 of this report. B. Secondary Steam System (See Figure 202-4) Make-up water for the secondary steam cycle vill be taken from either the existing station filtered water supply, softened water supply, or condensate system. Provision is being made to take any'of these waters and the water used vill depend upon the chemical analysis of the various waters at.the time needed.. The water used vill be further treated in a demineralizer plant con-si ; ting of two cation units and two anion units. These units are arranged in two separate parrallelstrains with a cation unit followed by an anion unit. The effluent fram the anion units is discharged into the deaerating heater. These demineralizer trains will'be operated as required to supply the system losses caused by leakage, sampling, . blowdown and feed to the main coolant system. The units have a flow capacity of 20 gp and a capacity of 20,000 gallons between regenerations. The capacity between 2tgenerations is based on using filtered river water having approximately 125 pp total solids and l producing anion effluent having 1.0 p p total solids. The average chloride concentration in the river water is 2 ppm and the chloride concentration in the anion effluent should not'be more than.0.1 pp. Blowdown vill be used to control the chloride concentration in the steam generator to 0 5 pp , or less. 4
- g 3/17/61
217 1 l 1 Mixing tanks and charging pu: ps are being provided for internal treatment of the steam generator salines. Separate equipnent is being provided l ( for oxygen scavenging, pH control and hardness control. While the steam generator treatment hasn't been definitely established, hydrazine, morpholine, and phosphate vill prcbably be used. ( l l { l i l f /2 0/61 , 218.1 1 /y \ 1 l 218 - STATION SERVICE ELECTRICAL SYSTDi A. Function The function of the station service electrical system is to supply the power requirements for the main coolant pump motor, the various auxiliary motor drives, pressurizer heaters, lighting, ventilating, control and comunication systems. B. General Description . The reactor plant vill have a station service elontrical system that vill be integrated with the electrical system of the existing p ant. A one-line and relay diagram is shown on Figure ClS-1. The existing plant has a 115 kv substation that ties it into the major transmission cyntem of the Pennsylvania Electric Company. The normal supply for the reactor station service electrical requirements vill be a 1000 kva,13 2 kv/4 D v tre.2former with the high side connected to the 13 2 kv generator bus in the ex$ sting plant. A standby source to the reactor station service electrical system vjll be provided through a 750 kva, 2300/4h0 y transfomer, from the 2300 y station service busses in the existing plant. The reantor plant station servM e electrical system includes two h40 four y440 switchgear bus volt motor seccions, control a pressurizer centers, a 120/208heater control v lighting bus,center, a 120 /208 v ( l vital control bus, a 125 y d-e system, an inverter-diverter to supply the 120/203 v vital control bus from the d-c system in an emergency, and a variable frequency motor generator set for the main coolant pump. j In addition, a 4h0 v load center located in the existing plant is l energized at all times by the 750 kva transformer that is the standby source for the reactor plant. Thir load center normally distributes power to auxi]! aries located in the plant; and on a standby basis, to the reactor kk0 v busses. The condenser circulating water pumps vill be supplied directly from the existing plant 2300 v busses, as originally installed. A normally open d-c tie vill be provided between the existing plant battery bus and the reactor plaat battery bus, for emergency service. l C. Generator Bus The 13 2 kv Bus flB in the turbine plant vill be the normal reactor facility generator bus. The normal mode of operation vill have tnebreakersforGeneratcrf2,Transformerf2(132/115 kv), and the Reactor Station Service Transformer (13 2 kv/440 v) closed.on this bus. D. Reactor Plant Electrical Service All switchgear, motor control centers and control boards for the reactor plant primary and auxiliary systems vill be located in the reactor * ( control and auxiliary building, with the exception of the vaste handling motor control center whien vill be in the vaste trectmen't plant and the water treating motor control center which vill be in the turbine plant. /7/o1 k S18.1 O A 2 3,800/Wo v,1000 kva transfomer located outdoors, immediately a adjacent to the switchgear room in the reactor control and auxiliary building, and supplied from the 13 2 kv generator bus flB, vill be the nomal supply to all reactor auxiliaries. An emergency feed to the reactor plant electrical service is O provided by a 40 y circuit from a 2400/40v,750kvaInerteeminsulated transfomer, located in the electrical bay of the existing plant building. This T,ransfomer bank may be energized from either 2300 v Bus fl or #2 by means oI either of two 2300 v circuit breakers. These 2300 v busses have 3 power sources; they are Station Service Transformer #1 (3000 kva), Station Service Transfomer #2 (2500 kva) and the House Generator (937 kW). , E. Main M O V Reactor Busses The MO v busses in the control and auxiliary building vill nomally .be energized by the 13 8 kv/W3 v,1000 kva transformer feeding Bus fl. The MO v. tie breaker vill be noraally c3 osed and the emergency feed breaker nomally open. Operation of the transfomer differential vill transfer supply to the emergency feed and lockout the transfomer breakers. Tripping of the nomal feed lov side transformer breaker from overload vill cause the tie breaker to open and the emergency feed breaker to close, energizing Bus #2 only. If both M O v bus sections are being supplied from the emergency feed and the emergcncy feed lov side trips from overload, tne tie breaker vill also be tripped. The nomal supp1'y breaker must be closed manually. ( Since the M O v system is ungrounded, ground fault detect".on is provided on each 40 y main bus by means of auxilisry potential transfomers, connected vye-broken delta, and overvoltage relays to operate on zero sequence voltage. Operation of the ground detector relays vill actuate an alam. A control switch and a synchronizing switch are located on the l main control board for the nomal feed station service transfomer lov side circuit breaker, the emergency feed circuit breaker, and the bus tie breaker. The preper synchronizing switch must be operated to place the .synchroscope and syntnronizing lights into operation, before either of these three breakers can be closed by its control switch. The feed breakers located on the main M O v reactor plant busses O av listed in Table 218-1, below. O TAELE 2L8-1 REACTOR PLANT FEEDER BREAKERS M O V Bus No. 1 M O V Bns No. 2 Pressurizer Heater Control Pressurizer Heater Control , Center Feeder No. 1 Center Feeder No. 2 ! Motor Control Center No.1 Motor Control Center No. 2 Lighting Bus Tmnufomer Emergency 120/208 v'Transfomer { RWDF Motor Control Center Safety Injection Pump No. 2 Safety Injection Pump No. 1 Battery Charger M-G Set M O v Inverter Bus Main Coolant Pump Variable Frequency Set Motor ,lG/01- 218.. F. Pressurizer Heater Control Center two feeders nomally serve the pressurizer heater control center; 1 Feeder No.1 from MO v Bus No.1, and Feeder No. 2 from MO v Bus No. 2. Each of the two feeders vill supply M O v power to 40 kv of heaters grouped on a singic contactor. A transfer switch vill pemit energizing a third bank of 40 kv from either one of the feeders. Control switches for the breakers of the MO v busses are mounted on the main control board. Breaker position indicating lights are located on the control board with the control svitchec, and also at the switchgear. If a breaker trips due to fault, the " Circuit Breaker Trip" anneneintor point vill sound an alarm. The contactors for heater groups 1 and 2 are controlled by "Off" - "On" " Backup" control svitches located on the main control console. The contactor for heater group three is controlled by an "Off" "On" control switch located on the control console. Heater group three, which in the nomal controlling group of heaters, is energized through a variable auto-transfomer that is controlled by the pressurizer narrov range pressure channel (PRO-2). If the control switch for heat,er groups 1 or 2 is in the " Backup" position, that heater group can be energized by control relay operation of the pressurizer narrov range pressure channel (PRC-2) or by closing of the the auto-transfomer limit is insvitch the ndl on the groupposition. voltage 3 auto-transfomar, indicating Lov pressurizer (LIC-2 and LRC-21) level vill cut off all three henter groups. The current in all three heater groups, plus the voltage on heater group 3, are indicated on the main control board. ( Each heater group contains six heaters. Both leads of each of the 18 neaters are teminated at the pressurizer heater control center in the control and auxiliary building, hence the heater grouping can be changed at the control center. G. Motor Control Centers No. 1 and Uc. 2 The MO v motor control centers comprise motor starters in com-bination with circuit breakers for short circuit protection. Each center is c normally supplied separately from its supply feeder; the tie breaker being open. These breakers are controlled from the main control board by " Trip" - "Close" control svitches. A motor control center supply breaker cannot be closed unless the main MO v bus tie breaker is closed, or motor control center tie breaker is open. The motor control center tie breaker cannot be closed from the main control board unless the main 40 v bus tie breaker is closed, or one of the I two supply breakers to the motor control centers is open. H. Lighting Bus The120/208 y lighting bus is supplied by a 112-1/2 kva, MO-120/208 v, dry type transfomer. .The supply breaker is controlled from the main control boani by a " Trip" "Close" control switch. Breaker position indicating lights [ are located on the control board with the control svitches, and also at the uvitchgear. If the breaker trips due to an electrical failure, the " Circuit Breaker Trip" annunciator point on the main board vill sound an alam. /30/61 218.h I. Emergency 120-203 V Tresfomer The emergency 440-120/208 Y transfort *r is supplied throu6ha circuit breaker on 4h0 V Buc No.1. It is cont olled by a " Trip" "Close" control switch located on the main control board and is provided with indicatin6 lights and alam similar to the Lighting Bus breaker, above. J. , WDF Motor Control Center This control center, located in the control room of the vaste treatment plant, is supplied throu6h a nomaily closed circuit breaker on 440 V Bus No.1. The power center comprises combination motor' starters with control s.vitches located on the front of the control center, and in some cases, also locally at the equiptent. K. Safety Injection Pumps Supply The circuit breakers serving the safety injection pum} u vill have instantaneous series trip devices only on phasec A and C. A series overload device on phase B vill sound an alam for an overload condition but vill not trip the circuit. Centrol switches for each pump ar'e located on the main control console. Lov pressure in the main coolant system or low p2resure in the O pressurizer vill start the pumps. A Bus tie opens and the emergency breaker closes allowing Safety Injection Pump No.1 to start from Bus No. -1 and Safety Injection Pump .lo. 2 to start from Bus No. 2. If the emergency breaker does not close, pump No. 2 vill then be started from Bus No.1
- Starting of these pumps from a lov pressure signal can be blocked by operation of a " Safety Injection Block" switch on the control console.
Closing of a contact in a flow integrating controller (FIC-21) vill stop the pumps. Breaker position indicating lights are located on the control l board with the control switches, and also at the switchgear. If a circuit breaker opens, with the control avitch in the " Start" position, or with a l low pressure condition existin8, the " Safety Injection Off" annunciator point on the main control board vill sound an alarm. ! L. Battery Charge'r l The battery charger M-G Set vill be operated whenever the inverter-diverter is out of service, or in parallel with the inverter-diverter whenever re-quired by the total 6-c load demand. An equilizer tus is provided for parallel operation. The M-G Set is supplied through a circuit breaker on 440 V Bus No. 2. This breaker is controlled by a control switch on the main control board. This control circuit is supervised by an "Open - Close" selector switch on the local control panel. Breaker position indicating lights are l located on the control board and at the switchgear. l l l The generator contactor is controlled from the main control board; but cannot be closed unless the 440 V motor circuit breaker is closed. If the (. motor breaker opens, the generator contactor vill open. Generator current, generator voltage and contactor position indication lights are located on the main control board and on the battery charger and inverter-diverter control cabinet. ' /7/61 l 218 5 : l 1 ) M. Inverter Bus and Vital Bus Supply 1 The nomal supply to this bus is through a circuit breaker en MO V Dus No.1, and a starter in the inverter-diverter control cabinet.
- The two loads on this bus are the 15 KVA, M0/120/208-V transfomer to supply the vital instrument load, and the inverter-diverter motor-generator set which supplies the d.c load and keeps the battery on charge. Whenever the MO V supply circuit is open at either the circuit breaker or starter, the power flow in the inverter-diverter is caused to' reverse, so that the d-c diverter is motored by the battery and the synchronous a-c machine becomes a generator, supplying power to the vital a-c bus. 7 N. Main Coolant Pump Supplies A variable frequency and voltage motor-generator set is provided to supply 30 to 67 cps to the main coolant pump mo' tor. The variable frequency set motor is energized through a cimuit breaker on MO V Bus No.1. This breaker is controlled by a " Start" "Stop" control svitch on the control console. Breaker position indicating lights are J ocated on the control console with the control switch, and also on the switchgear.
A circuit breaker, controlled by a control switch on the control console connects the variable frequency generator output to the main coolant 4 pu=p motor. Provision is made to synchronize with M O V Bus No. 2 before closing this breaker. Bmaker position indicating lights are located on the control console with the control switch, and also at the svitchgear. l k The main coolant pump is nomally supplied with 60 cycle, MO V power from WO V Bus No. 2, through a circuit breaker, controlled by a control
- + sviten on the centrol console. Provision is made to synchronize with the variable frequency bus before closing this breaker. Breaker position indicating l
lights are located on the control console with the control switch and also at the switchgear. A 2-element themal overload relay is provided on the feeder circuit to the main coolant pump. Operation of this relay actuates the " Main Coolant Pump Overload" alam on the main control board, i If the M-G Set motor breaker trips, it vill actuate a " Circuit l Breaker Trip" annunciator point. If the M-G Set generator breaker trips, it . vill actuate a " Variable Frequency Generator Tripped" annunciator point. If the variable frequency generator breaker opens, or the 6enerator l voltage relay indicates J ov voltage, or the variable frequency set motor breaker opens, or MO V Bus No.1 voltage relay' indicates lov voltage, concurrent with the main coolant pu=p breaker being open'or the M O V Bus No. 2 voltage relay indicating low' voltage, then scram circuit breakers "A" and "B" shall be tripped and the " Main Coolant Pump - Trip Out" alam point will be actuated on the Screm> Alam Annunciator. /7/61 I 218.i l O. Emergency Lighting i The AC-DC Dnergency Lighting Bus is supplied from the 120/208 i V Emergency Bus through an automatic transfer switch. This bus is nomally energized and supplies power to a portion of the lighting load. In the event of loss of power to the 120/2O3 V E,nergency Bus, the load on the AC-DC Emergency Lighting Bus is autcnatically transferred to the 125 V DC Bus. In addition, by action of the autccatic transfer switch, the DC Emergency Lighting Bus is energized to provide additional lighting in the control and auxiliary building. l l I D l l( l l ~ l l l l l 2/15/61 e-Se-. .2 l4 wm - %s L o , l)i pinv$lk n i . ede. -, e,; ~ -- ,q,c,', 3 . p ;j ip; .i .y li b ~ tk0 d"'* ;;; Q,.% o{ l:ilit'1 i s (. j I .et e J s. i I y .... ._._. . ,, .ti 6d @ y Og g, +-J e : q- _ # p- *:$il. .; r , i , -.,__.,. y y~~ tp ~ j i OM h5 ~lg* ! ? a I a ii. s( p % h.r; 1ll. d,lf'inlh Lf j'* _ j ,. _ lHH s% * , . _ * ; yy -'T*' l -$ j j + %2ctU i s , -t+ .y=.a ,9e
- h. 4, qn b1 '
) l-a J. (di.4 ai..,_y ' 11 4
- It +-
~ TJ Q: 8 l j ft yf <. }{-+-* . ..+_._. l ! Mm) u & I 9J l ..,{j e l ! 21..-w :a . t'- g ;! $. .[t b I' 2 -1 ,l + * ~ ~ ~ -. - i a, 99 ;%:,f. +1+.--- m ., -sl - T ,y 17
- s. . W s T .
li __+ie h 5 cg ?*M;s(2*- Q- _ - _ _ _ . ii, { ) f , ._-@ke c, ._g-c.- .-__. 4.. cy ,i ? l y a& r l l p , , ;rl.,g r e- r, . _ - _ e !i' p-+ O -< - Q- - blh- _. --7 , , plj j p l. UL tb- @ul ] 1p- @- %g . . . .fd i *. a] ) p;_w_- ,. 1, ._ , 2 O- dl l ! j L__... i ,,_ . ! j i Tlb j j i !!ao:ol3 - I i 4.t ,wljl j. i 1 - s: ;h . ii ! i #, _ pi.t -a . n! I q, E / i 1: jr e,.._ od .! r --Oi p._; _! fr' .h. . _ . 2.r .a f[y}! f .c ;-[M-@o.-ai .- __ g eG' ; * 3 i I ,,, L 4 . 7" +,~ . n- ; 4 h-d1}IJ 3' ; po'_ c, '-=-- ji l.i ! 7 t; ;n g r ,c---c3 _w- ) ps- i +, u
- c. e c 4
. _.. J yli{l. 3i M #.gg[ pt - + e ~ l l " t-- m- - , -- rr W =P 219 1 219 - RADIOACTIVE WASTE DISPOSAL FACILITY A. Introduction The radioactive vaste disposal facility is one of the four major areas of the Saxton Nuclear Reactor Facility. It is an accessory processing system available on site and is designed to accomodate all the radioactive effluents from the reactor facility. The physical layout of the facility with respect to the other plant areas is shown on Figure 201-1. In effect, the facility consists of four systems - a solid vaste disposal system, a liquid vaste disposal system, a gaseous vasto disposal system and an air-borne vaste disposal system. Air-borne vastes are handled by the cooling, heating, and ventilating systems which are described in Subsection 214. The flow diagrsa and instrumentation diagram for the fluid systems is shown on Figures 219-1 and 219-2. B. Solid Waste Disposal System
- 1. Description The function of the solid vaste disposal system is to handle solid combustible and non-combustible vattes that are produced in the course of operations. In general, relatively lov-level radioactive solid combustibles and non-combustibles vill consist of paper, rags, small tools, filters, laboratory glassvare, etc. High-level demineralizer ::esins vill be temporarily stored on site. The solid vaste disposal system is capable of packaging low-g level combustibles and non-combustibles into 55-gallon drums for off-site
, repackaging by an AEC licensed carrier, or into drums prepared at the site for ultimate sea disposal. A hydraulic baling machine is provided to perform this operation. Combustibles and non-combust 1bes collected during the course of operation vill be temporarily stored in steel drums with suitable fire protection closures. Wnen sufficient material has been accumulated, the vaste vill be compressed into steel drums by the baling machine. ' Wastes till be baled according to the amount and activity of the material collected. If a large quantity of material is to be disposed of, for instance, during refueling periods, 55-gallon drums may be used to dispose of the vaste for repacksging off-site. On the other hand, during normal' operational periods when the accumulation is expected to be relatively small, the baling machine can be used to compress the material into either 55/30 or 55/15 gallon drum l- combinations for ultimate sea disposal. Prior to the druming operation, the drums vill be prepared for sea disrosal by placing concrete in the annulus between the drums, o Resins from the purification and boric acid system, and storage well system demineralizers vill be sluiced to underground resin storage tanks where they vill be retained until disposal is effected. Three BSC-gallon spent resin storage tanks are provided.
- 2. Components
( a. Baling Machine The baling machine vill compress vastes into either 55, 5 /7/61 q 219 5 I 30 or 15-gullon steel drums or any combination thereof. It essentially consists of a vertical hydraulic piston which moves in a cylinder and ie
- mounted on an arbor.
I ' b. Spent Resin Storage Tanks l Tae spent resin storage tanks are dual tank construction. The outer and inner tanks are separated by the supporting structure between the tanks. The inner tank is a horizontal cylindrical, Type 304 stainless steel tank vith dished heads and has a capacity of 800 gallons. The outer tank is a horizontal, cylindrical, carbon steel tank with flat heads. A leak detection probe is provided in the annulus between the tanks. The inner tanks are constructed in accordance with the lethal vessel section of the ASME Code for Unfired Preasure Vessels. These tanks vill have one exception in which they do not meet the ASME Code and that is the absence of manholes. This exception has been approved by the Cocnonwealth of Pennsylvania, Department of Labor and Industry and vill be given a Pennsylvania "Special" Stamp. C. Liould Waste Disposal System
- 1. Description ,
All rad'oactive i liquid effluents from the containment vessel, control and auxiliary building, and exL *,ing plant are discharged via underground pipelines to either of two 10,000-gallou underground storage tanks, or a 5,000-gallon underground decontamination room tank. All of the piping handling these effluents is designed in accordance with the ASA B 31.1 Code ( for pressure piping. Carbon steel has been used for all of this piping, except for lines handling low pH vater or high activity in which case stainless steel has been used. All of these pipelines are run in a concrete pipe tunnel except for the pipelines between the storage tanks and the tunnel. In order to obtain a high degree of integrity, the piping between the underground. tanks and the tunnel run incide of a second pipe that is arranged so that leakage that might occur vill drain backfto the annulus between the inner and outer tanks. The tunnel is sloped in the direction of the vaste treatment plant
- so that all leakage or_ spills vill drain to a sump.
Equipent is provided to add alkali to the acid vaste liquids l prior to their storage and disposal. Primarily this treatment is performed in order to minimize the corrosion of pipe and storage vessels by the 1% H3 B03 removed from the reactor during a cold startup. The neutralization vill also enhance borate solubility and reduce the vaporization of the H 3303 into the steam during the subsequent concentration of the vaste liquid by l evaporation. The system consists of a proportioning pump and an alkali
- solution tank with a dilution water float valve, screen mixer and other l necessary tank appurtenances. The proportioning pump and motor vill be l
used to inject a prepared solution of alkali into the pipeline which carries the borated water from the reactor to the storage tanks. _ The equipent is located on the first floor of the control and auxiliary building. The decontamination room tank vill collect drains from the decontamination room, the chemical laboratory, and m$scellaneous other drains [ in the solid vaste baling area of the control and auxiliary building. These drains vill vary in acidity and alkalinity and therefore vill be discharged to the decontamination room tank which is made of stainless steel. The' drains that are nomally discharged to the storage tanks can also be diverted into the decontamination room tank if additional tank capacity is required. 219 Two 1,200-gallon monitor tanks are located above ground at the east end of the control and auxiliary building. These effluents are not expected to be radioactive and therefore after samples are taken and analyzed, it may be possible to discharge this vaste vater directly to the sevage system. If not, provision has been made to drain these vastes into either the storage tanks or decontamination room tank. Drains from the secondary blevdown tank vhich is located in the existing plant are not expected to be radioactive and vill normany bt discharged to the existing plant circulating vater outlet tunnel. If a lesk ry teaks should develop in the steam generator tubing, the radioactive ra.n ci olant water would contaminate the secondary cycle water which is at a lom r pressure. Boiling in the steam generator provides an inherent deconth.oitation process o which vill concentrate the nonvolatile and solid radioactive c..rrosion products and fission products'in the liquid phase. Through the contint aus blovdown system, this concentration of radioactivity would then be t:ansferred to the blevdown tank. The blevdown water is monitored and if high activity is detected the valves in the system win be automaticany closed and the flow manually diverted to the underground storage tarAs.' Since the vaste disposal facility is not sized to accomncdate this f1M on .a continous basis, the plant vill be shut down to investigate thit. so m e of radiolctivity. Liquids. stored in the two 10,000-grinen storage tanks and one 5,000-ganon decontemination room tank vin eventually be put through a degassing cad radioactivity decontamination process. The equipent used in this process consists of one gas-stripper-p.eheater, one gas-stripper, one , y evaporator, and one evaporator condenser. This equipent along with a drumming' ; j i facility for handling the evaporator concentrates is located in a concrete shielded and compartmented building, known as the vaste treatment plant. This - building is shown on Figure 201-8. The vaste liquids vill be moved from the underground storage tanks to the vaste treatment plant by means of a steam-operated ejector. The liquids first pass through the gas-stripper-preheater before going to the gas l stripper. Both cf these units can be by-passed if volatile fission products , are not present. The radioactive decontamination factor for gases between the vaste stream inlet and gas-stripper outlet is expected to be at least 105, l After leaving the gas-stripper, the liquids flow by gravity to an evaporator which concentrates the radioactive and nonradioactive solids. The steam generated in the evaporator then passes through e "tsinless steel wire demister where further decontamination is effected by rea, val of entrained moisture particles. The decontaminated stess then passes to a vent condenser where the steam is condensed and any residual gases are vented to the gas disposal system. The condensate is next pumped into'one of two 5,000-gallon discharge tanks where it is held for sanpling and analysis. The condensate can then be reused, recycled through the vaste treatment plant, or discharged l to the river, depending upon its activity._ The radioactive decontamination l factorbetweentheevaporagorstill-potandthecondensateproducedis expected to be at least 10 . y It is presently contemplated that the evaporator c[ncentrates f can be concentrated to a 40 veight per cent solution' of solids before the vaste treatment plant must be shut down to remove these concentrates unless - radioactivitylevelsinexcessof100ue/ccprecludiconcentratingtothis 3/10/61 - 219 d ' limit. The evaporator concentrates, which may be highly radioactive, vill be drained into various size steel containers which contain a measured amount of dry cement. These containers are precast in concrete inside of standani 55-gallon steel drums. After these drums are filled, they vill.be moved to the shielded storage area shown on Figure 201-1, and stored until such time as there is a sufficient number of drums on nand to make up a shiInent to an 3 AEC licensee qualified to handle radioactive materials. An evaporator concent, rates dru=.ing system, consisting of conveyors, elevators, a filling station, a stirring station, a gasoline - driven fork lift truck, scales, and a velding machine is provided to facilitate the handling of evaporator concentrates.
- 2. Components 4
- a. Tanks The two 10,000. gallon anderground storage tanks and the one 5,000-gallon deccntamination room _ tank are dual construction, or tanks within a tank. The inner tan'. for the stora6e tanks is made ' of carbon steel designed in accordance with the ASE Code for Unfired Pressure Vessels and the-W-2 lethal vessel section. The outside of the tank has a protective coating,
+ however, no protective coa +ing is provided .for the inside of, the tank. .The inner tank for the.decontaination room tank is made of stainless steel designed in accordance with.the same code as the inner tanks of the storage tanks. These three inner tanks, like the inner spent resin storage tanks, , have one-Commonwealth of Pennsylvania approved exception in which they do not meet the ASE Code. This exception is the absence.of manholes. These manholes are cuitted in order to obtain a high degree of-integrity for the inner tanks. Also, in order to obtain a high degree of _ integrity, the piping between.the . underground tanks and the tunnel runs inside of a second yipe that is arranged so that leakage that might occur vill drain back to the annulus between the inner and outer tanks. The outer tanks for these three tanks are made of carbon' , steel and are designed in accordance with the Underwriters' Laboratory Code. The two 1,200-gallon monitor tanks and the two 5,000-gallon discharge tanks - i are single, carbon steel tanks. -The inside of the discharge tanks has a i protective coating. b.- Gas-Stripper and Preheater The' gas-stripper is a_ vertical" column. direct contact type, consisting of a 10-inch diameter, Type 304: stainless steel,. packed _ column: _ __ _ containing one-inch Type 304 stainless steel Pall rings to a depth of 10 feet. It has a nominal capacity of 1,000 lb/hr. The gas-stripper preheater is at steam-to-vater horizontal type heat exchanger of Type 304 stainless steel construction having a minimum heat transfer rate of 126,000 Btu /hr. Both?of these items are designed in _accordance with the ASE Code for Unfired Pressure Vessels, W-2 Lethal- Vessel Section. -
- c. Evaporator Unit' l.
The evaporator unit,; including the evaporator still-pot,_ demister, and vent condenser is constructed'of Type 304 stainless steel and in. f accordance with~',he lethal vessel- section of the ASE Code for Unfired . Pressure Vessels. -It has a minimum feed liquor capacity of_1,000 lb/hr. ~ 4 _ /6/61 l _ _ , - . , . _ _ _ ~ - - ,.- .---. ~. -4 ._-.__.---,_-.--.,-.-o . . . . . _ _ . . , _ . - E ~ l 219
- d. Evaporator Condensate hp and Discharge
! Tank Discharge Pump These pu=ps are hor $zontal, single st8ge, centrifugal pumps which are constructed of stainless steel and have a capacity of -5 gpm. D. Caseous Waste Disposal System
- 1. Description When the radioactive primary coolar.t effluent is depressurized, hydrogen gas and volatile fission products, if present, vill be evolved. These gases vill be present in the resin storage tanks to a limited extent. These gases vill also be present in the discharge tank which is located in the bottam of the containment vessel. All of these tanks are vented to a common system that is maintained under a slight negative pressure (2-8 inches H 2O gauge) by a gas ,ompressor. This collection system and the gas compressors are shown on Figure 219-1. The negative pressure prevents any leaknBe of radioactive gas into the surrounding environment.
One of the two compressors vill be in continuous operaRon and , . Vill compress the gaces removed from the ta'nks along with t F gsses removed fram the gas-stripper and evaporator condenser vent into one of three 133 cu. ft. tanks. Vent gases vill be stored in these tanks at. pressures up to 80_p. gig. Gases vill be held for an optimum reduction in radioactivity due to decay to a point where they can gradually be released to the stack for atmospheric dispersion. ( The hydrogen gas presents an explosive hazard and therefore special provisions have been made to control the concentration of this gas in the air-gas mixture handled by the gas compressors. Nitrogen vill be used tio purge the vessels end lines and maintain the hydrogen concentration below its h lover explosive limit. A gas analyzing system vill continuously and automaticallyj check the gas mixture for hydrogen and origen concentrations and an alarm vill f be sounded whenever these concentrations approach dangerous limits. '
- 2. s Ccce onent_s,
- a. Ons Compressors The gas co= pressors are rotary water sealed type and have a capacity of 22 scfm. Suction pressure is automatically controlled by means of a bypass system which contains a heat exchanger for removing the heat of compression. The river water used to remove heat from this heat exchanger vill have a higher pressure than the gas, so that any leakage vill be in the direction of the radioactive gas rather than the water which is discharged to the river.
- b. Gas Decay Tanks Each of the three carbon steel gas decay tanks has'a capacity of 133 cu. ft. at STP. They are constructed in accordance with the lethal vessel section of the ASME Code for Unfired Pressure Vessels.
( 2/13/61 . 1 219.( , E. Instrumentation and Control
- l. Storece Tanks
- The spent resin storage tanks are provided with instrumentation for level, temperatore, and vacuum; the decontamination room tank and the tvc 10,000-callon o.orage tanks are provided with instrumentation for level and vacuum; the gas decay tanke are provided with instrumentation for pressure; and the moni+.or tanks and discharge tanks are provided with in-strumentation for level. Each tank is provided with a capacitance type probe for continuos level Mdication. These instruments provide 3/4 and full tank a3 nrm points. Separate short proben with completely independent circuitry provide back-up high level alams. Temperature monitoring is acecruplished by a unit which continuously monitors all points against adjustable alarc points between 250 F and 250 0 F. Pressure and vacuum are direct reading gages with alam contacts either on the gage or through separate pressure switches in the source line.
Annuli of the duni storage tanks have two means of detecting the presence of liquid. A short capacitance probe mounted near the bottcru vill actuate an alam, and in addition a pneumatic bubbler-type instrument is provided which vill indiente level in any one annulus as selected by the ope Stor. L. Evaporator The evaporator process is under control of a pneumatic i level controller which senses level of the evaporator bottcras. On rising level, the steam admission valve V1626 is opened and concentrat hn by evaporation begina. The vapor passes through the demister, the outlet pressure of which is controlled at a small positive pressure by V1450. l This is in essence a back-pressure valve with remote set point adjustment. l Thus the vapor is used in the preLenter and gas-stripper on demand and released to the evaporator condenser or.ly when the demister outlet pressure tends to rise. A lov level contact operates a solenoid valve in the steam line to the ejector in the liquid transfer line, causing more liquid to be l drawn frca the storage tank into the evaporator. A high icvel contact stops thL actier.. A pressure svitch sensing the evaporatt.r shell pressure, actuates a solenoid valve that dumps the control air to V1626 causing it to close on high evaporator pressure. Another presture switch sensing a diff-crential above atmospheric vill prevent operation of the bottcans removal valves should a positive pressure exist within the evaporator. River water flov to the evaporator condenser is controlled manually. The evaporator condenser hotwell level is controlled by a pneumatic indicating level c A-troller that starts end stops the evapomtor condensate pump. This instru-ment has panel-mounted set point and proportional band adjustment which allovs full operator control of the process frcra the panel. The temperatum of the evaporator bottoms is continuously indicated. The liquid stnam into l the evaporator or gas-stripper is heated in the preheater. Steam frcan the demister outlet is used for this purpose under control of V1436 which senses the preheater effluent temperature. Thepancl-mountedindicating . controller p ovides manual set point adjuatment throughout a 1000 - 300 F range. /6/61 - . - . _ . _ - _ -- __ _-- - _ _ . - _ - _ - . _ - _ - - . _ . -_. - - - - ~. a.: . t 3 Dan-Stripter Sten:n flow is controlled by set point of Vlk50 controller and/or V1443 The set point of the gas catnprestor suction manifold pressure vii..L also have same small effect upon the flov since it affects the pressure d*op acrosc the vessel. The vent condenser pressum is continuously indicetol o:. the panel and an adjacent manual controller is provided for, the river vate" flow to the vent condenser.
- 4. Hydrogen-Oxygen Analyrer
+ This analyzer is equipped with tvelve sample points, and monitors ec:tinuout.ly whenever the RWDF is in operation. Details of the system are shown on Figure 219-2. 5 Das Compressors and Gas Compressor Seal Water Pumps The gas compressors receive power fram motor starters located in the IMDF motor control center. Each is controlled by its respective relector switch, with 'An" "Off" "Standoy" positions, located on the starter units in the motor control center. With the selector switch in the " Standby" position, the compressor vill start when a contact of a pressure svitch on the auction manifold closes, indicating lov vacuun, provided the associated seal water pump is running. Each gas ca mounted "Run" "Stop" pushbutton control statica. jnpressor 'However, also a gas has a locally ccropressor cannot be stopped from this control point, if it has been started either at the motor control center or by the pressure switch on the suction manifold. g When the pressun svitch indicates low vacuum, in addition to starting the " Standby" compressor, it vill start its gas ccznpressor seal vnter pump. In addition to being started autcznatically by the pressure switch, if its ccanpressor selector evitch is in the " Standby" position, each seal vater pu=p can also be started at any time by " Start" "Stop" pushbuttons located on the starter, units in the RWDF motor control center. .The seal vnter pump cannot be stopped at the motor control center if it is being controlled by the pressure switch. F. Design Criteria The design criteria that have been used for the radioactive vaste disposal facility are as follove:
- 1. All Saxton Nuclear Reactor Facility effluents discharged frcrn the Pennsylvania Electric Campany Saxton Plant property into the natural envirvwmd vill meet radiation tolerance guides established by both Federal and Commonwealth of Pennsylvania Regulations.
- 2. After treatment, the release of liquid eft;uents vill be acccruplished by controlled dilution with condenser circulating vnter.
After hold-up, gaseouc effluents vill be released to the stack for atmospheric dispersion. ( 3 Radioactive demineraliter resins vill be temporarily stored U. site in underground storage tanks. 3/6/61 g s.. 14 . Radioactively contaminated solids of either a combustible or ' i noncombustible composition that cannot be economically decontaminated vill be baled into steel drums for shipment off site. 5 Fission product contamination in the main t solant is assumed to be equivalent to leakage that vottid result from defects (pin-hole leaks) in 1% or the fuel rods. ( 1
- 6. Corrosion prodget contamination in the main coolant is based on acorrosionrateof10mg/dm/ month.
7 Main coolant discharged fram the reactor plant during cold startups vill contain low concentrations of borio acid.
- 8. During a cold startup, boric acid dilution and expansion vill result in approximately 8,000 gallons of main coolant being discharged to the storage tanks.
9 The radioactive vaste disposal facility vill receive all vents-and drains from the containment vessel, radioactive or potentially contaminated i vents and drains from the control and auxiliary building, and drain fram steam generator blevdovn tank if excessive radioactive contamination is present. \ U s /6/61 -. _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . __ ._ i
- p. ,.
4 'I'. -.M I the1/13 ~ 4~~ l' "*~~T E , 5;l k [fM!! I )l. l d - 't l i t 9 ~:d'. . ," Id Mi ha. y' N. di .) l , ' p.,,1d <(" - i - .J, ..u.]: ; 3 ; 'il' L I i .yjid !! I d,' 2 j ,i , y'
- .11 I I pU
. tl [p.I .!rd ' Ig[r,i i[ # . gl ( -y.Pj 'e). ; tii)u, v i'h r{m
- q. i*1_t .
J p; p t a r L i t ;i 1, . ! h_ilis'I a . i. lnl . l Id, i *i i lhi Il--*- i ! II I f1 . ~~1 9! '!I If t ! : (dr~ ~~~~'"t i i ==:i -[lo e d.-qir - i - eq Q $. l- ' ...ij m )gw i mg: I f 1- [ ~ I i l ;' {i j j i I lil > a., ljC ....r-~~' * !W
- i! .I
,Q l j '.l l T +; +1 i d I ,;iltdgg' [ l t j i l l { .* L. .__d l dbilI
- g F d. "" i
~ . . _ di!A r t- , ,,4 r.1 ids, 1 "== ;___ J.G,.y, M' g)i< jq. _ 7.c _ , { it 8 i ! ! ! ff p : { I .. .. m_~,m , ~- n -tr -m a ' , if .8, a, 4- ,e pilliipdl",ll! id i M 'l' ' ..!gd. ; '5 : - ii p'du!;g y** e _m 7*l} *-).i.l -~ "TN.! ,7- ]$ t .l n i i i - 'l
- 1
,s , m . , J.L i l i l l i b_ a, , 1 d q'.I 7 <w d OI IEsir _-.-u_ -. - b.--m "- - # m+ w - 1 [, y ! [,-' ~ k __Ud ~~ j {t!!!!! [!!!((!![! m -'t - L.l ,' Wge.:-!li r- Il End i4Iy , =-- if 8 1 u . _ , i p+-- si 1 ,: ll p';{,w/@"' G_G giLc. t: I - l - _ l 'l j 'ItE4 . ..... i t-- e.* tl!;olli l j.,a,,g jlg, p l ,: , . , e ;I l+14I na l 1, I i l l u l lh. li L ... 4 i i ;= j mr s , lll 1 # i,, fi ll 1 ~ '.[if I - 'a $.h; tidek t i % {~t = 1, ,_, i pli rns 1 i ','" q'i t i i I ,i , 'J . n - -r" ' 6 I> 7< i !i i ' '" i i li a Sg;h.! ,, 's,LLiStg 1 .-*^ a _j.l.L-b ' . . - ; .jt u I, < ~w e,ti,t %!.1 .:._.. 4.i .! Di J' l l l .__ - -- _ _ _ _ 1 E e- ~w ,-,->-,~--,t,*-g- -r, ,- t. -e-+j- - - - - , , , . ,_.,..-,--.,--,.-.c . c~ m-.:-y , , . - , y-.. gw-,m,.yv-r -ye--.e -,.e-..m~ . -,-,4-,,4-- er i < j iJ3 .ll,r M ....,....., , n.'i J1 Hi IIlli 1 1 y i n g i g l,y-j T ol je,! - y . u ,: i L- Nof ;q N a y @y,; i ,i ,.4 g-- ,,, f ;g. (r b i q i ,- i- . s ii , l ' g lj --- l i .i . . b .r w 4 . _ _.gjifll I p, : d'a E .c Ifj r ,p1
- t. +g"_y,j,t_Q, 1 n v m F Ag R.
4 5 i Jn $ i< w ..Ib pirr! 1m.-l4 ,.i;). 1 li gbi
- q. _
.. n s -- Wt r. . i . , , .. s p.#s .Jz, m , 1 pvrc.it 1, 3 l i,.iL. ,..;6,, , i t i .1_ i i.s , J_ l Dp - w 37.n i l j -n! "bl: .i, x r 4 ._ a ~ -- tS@1. -. . . T 4 p l j .. . plc . Q.,c!i j 4 It 'i! 4.n.gl< go, ,,_ n _ _ h -=-- kJt s p a .1 g/j r, { ; ; 4 3 L, Jh = e - ,Vi;oW, i :t l .,.I i . s . J. , .. dl1.1 j. l1 - u . .. ..... Ll_lJ i; . j ;,, 461. - _m % fp4 6 Fy-dj@ g M "D, dg-"r't r [i ',! l' i. Y'M.- 'i 'Ed 9,. # o~ m .u .. , _ _ _ 1F ,1 3, I LW CK "*,,4 p -7*ll ; s r- 1 =' ;Mf~ = cf- - wau-~mam + ,. i. . itil l l o l 1. s -. . .. . . . ..{j 4..~.U m; - i w-o -)" i. 3 u , 8, 6 a:~ ', _g;o = .c --~ i o H t j' " ? . : . 2 ' I -, ~~ _p q 1 a p _ w:.Cf.i, p .g .. , iig i + t. m- + i ! l,lll ,: 3 lhl"l ! j 1 ;ni F ~ , u j p%=g- - ]9 ' h l T . 7 F 1 y Q,,1.lJ, i ll J io ii a_. me ; a.3 J l ,..p ii I "*--*fi..Ih'~ I }, CJ~~ ~ ~ O. .j -eyry a i . t e ' l( il nAsvvn. s jy-A g Ij i d + (3 -#wedes ' --.r-1 gl ws w ss A { i-l, '- +-' -A A g l pgl ge.11
- t. ;, -m=. d i ,
W i'+- ! I wty i -- k !.ger ' iQ l p j, i I [, I M. . , g.p.e _.J . i !
- v. w
. *ii - i ,i j i f ,.lm_- j i _- .l w v s s ft = *, 9
- Qwt.
'gi ii. li ~ w- : h, t==p l- e u p'p4 l,ulll!! ! l4 dlfit i lll 1 y q. p ..% $c vll. 4 i i . d,tk fT Iw y - 1 I ,l j I - - i .- A;;'t ,s , ] l sa li d'~!! ~~' ~ d f* I l i a{ ,! g; _y ql\ -m! 4J_:g, !n >; .3 .=- : / e .' i i ._.L,-<>J---- = le i rtI j y. - g%. * '--.r e ' LS { , j j . jg;gt I ,!.il _ mi 7< o- _a. +. . _ _---_~_-- 41 i,L3,Jo% b .ged *- '**** M t h . { d(N -.M'.".*.' 9.l 6,$ * * * * * * * * * * * - *
- l l
l 1 ,.,--n--,.,---., --, ,. , . , . . , _ _ . . . , . . , , , - , , , , - - - - - . - ,-, , - - - , - , - . - - - 220. 220 - RADIATION M01UTORING SYSTai A. Pune g The function of the radiation monitoring system is to detect, compute and indicate the radiation level at selected locations in t.nd around the plant. If predetemined radiation levels are exceeded at any of the monitoring stations, an alam vill be actuated. The system therefore serves the dual purpose of providing health hnzard warning, plus an early varning of plant malfunction which might result in a health hazard or plant damage. B. Description
- 1. General The radiation monitoring system consists of six shelf-mounted count-rate meters located in selected areas and, in addition, ten radiation monitoring channels which are connected to a common alann, indicating, and recording panel located in the nactor plant control rocrn. The radiation -
monitoring system can be divided 'into four general categories. These are (1) plant process monitoring, (2) plant effluents monitoring, (3) site monitoring, and (4) plant area monitoring. A block diagram of this system is shown on Figure 220-1. j 2. Plant Process Monitoring The plant process radiation monitoring channels include detection of both radioactive particulates and gases in the containment vescel, detection of radioactivity in the ccnponent cooling and steam generator blevdown water, and detection of fission products in the main coolant. 3 Plant Effluents Monitoring l The plant effluents radiation monitoring channels include the detection of radioactivity in both liquid and gaseous plant effluents. The plant liquid effluent to the Raystown Branch of the Juniata River is monitored prior to dilution by condencer cooling vater (river vnter). The l plant air-bome effluents are released to the atmosphere by way of the .! nuclear plant stack. The air-borne effluents a n monitored undiluted and C ' ,g prior to entering the stack. f
- 4. Site Monitoring Two air-bome particle detectors are located in the immediate flC' E vicinity of the plant site. These detectors continuously monitor the air to urn of any health hazard and are in addition to five other continuously g ,q operated air sampling stations located within a 20 mile radius of the site -
which function as a part of the radiological survey program described in #^~) g Subsection 109 ./27/61 220, 5 Plant Area Monitoring Potentially hazardous plant areno are monitored by cix identical shelf-mounted area monitors. Five of these monitors are located in the control and auxiliary building and one is located in the control room in the vaste treatment pit.nt. The monitors in the control and auxiliary building are located , in the reactor plant control roam, the charging room, the sampling room, the chemical preparation laboratory, and in the health physics office. C. Design Basis The design of the radiation monitoring system is based on the expected radioactivity at the various locations and the intended use of each channel. Tne primary purpose of the plant process monitoring channels is to provide early varning of plant malfunction; therefore, the ="4m= sensitivity available was chosen. The pr$ nary purpose of the site monitoring channels is also to provide early varning of potentini health hazards; therefore, the maximum sentitivity available was also chosen for these channels. The sensitivity of the plant area monitoring detectors was chosen to be campatible with the expected activity. D. Camponents
- 1. Plant Process Monitoring
- a. RIC-1 This channel continuously samples containment vessel air for the presence of radioactive particulate matter. The air is drawn through a section of moving filter paper by a constant displacement vacum pep.
Pressure evitches operate indicating lights on the c m puter-indicator panel to indicate variationsin filter paper pressure drop beyond-an adjustable preset value. The motion of the filter paper can be set from the control room. A lead chielded, end-on phosphor photamultiplier detector is mounted directly behind thg filter paper for beta detection. With sodium-24 as a reference, 10~7 microcuries per cubic centime.ter of air-bon.e radioactive particulate matter can be detected in sixty minutes with the filter paper moving at 1-inch per hour. A calibration source of radium DTS foil with a 22-year half-life is built into the detector. This source can be moved in front of the detector head, by remote control from the control room, and a calibrated count per second reading vill be indicated. Alann signals go to a common annunciator, and an alam leap in the associated computer-indicator. The annunciator can be manually re-set; however. the lamp indication vill remain on until nonnal conditions are restored. A background flasher is provided to give visual indication of proper channel functioning even though the radiation level is below the minimun meter indication.
- b. _BIC-2 This channel continuously samples the exhaust air frcan RIC-1 for radioactive gas. The detector is a 1-foot diameter sphere which I
i ./aT/61 l.._- _ _ _ _ _ . _ _ __ _ 220. t ! containo a photcznultiplier and scintillation crystal to view the inside volume. The cencitivity is approximately 3 x 10-6 microcuries per cubic centimeter in a background of 0.6 mr/hr. A preamplifier, tm inpedance matching network and a long-lived remote operated radioactive test source are integral parts of the detector. 110th itIC-1 and RIC-2 detectors are nounted outside the vapor container for acceccibility and are housed in a venther proof encloture.
- c. R10.h This channel continuously monitors the component cooling vater downstream of all the serviced equiyrnent to detect any leakage frcra the main coolant to the ccruponent cooling voter. One medium gamma senci-tivity Ceiger-Mueller cetector is housed in a cylindrical tank which currounds the detector with approximately one cubic foot of liquid. A bypass valve is provided to regulate the flov through the tank. The detector sencitivity is 0.01 to 10 mr/hr, using Cobalt 60 ac a reference.
- d. RIC-5 This channel is identiet.1 to RIC4 and continuously monitors the steam generator chell side blovdown vater to detect any leakage frcrn the main coolant cyctem to the steam side through the stetun generator tubes.
- e. RIC-7 This channel is a spare channel for future use if deemed necessary. It consists of a single medium gamma sensitivity, Geiger-( Hueller detector with integral impedance matching network.
- f. RIC-10 This channel is located in the bleed line downstream of the heat exchangers in the feci and bleed circuit of the main coolant loop.
The detector consisto of a cetion bed in series with an anion bed with a photomultiplier tube and ceintillation crystal gamma detector mounted on the anion bed. Integral preamplifier, impedance netvork, and a long-lived, remote-operated test source are provided.
- 2. Plant Effluents Monitoring
- a. RIC-3 This channel continuously monito*c the main plant stack effluents and consists of four thin-valled, Geiger-Mueller tubes operated in
. parallel. The detectors are mounted in a velded steel pipe framo suitable for mounting in the duct to the 6 tack. The detector mininum detectable activity is 2.0 x 10*' ue/ce. l b. RIC-6 l This channel monitors liquid effluent to the river prior to dilution by condenser cooling water. The detector is a sphere which k contains a photomultiplier nr.d scintiMation crystal to view che inside volume. A preamplifier, an impedance matching network and a long-lived, !/27/61 - 220.* remote operated radioactive test cource are integral parto of the detector. The minimum detectable activity in 10-5 microcuries per cubic centimeter for an aqueous solution of CO 60 in a background of 0 5 mr/hr. In adJition, a remote indicator-alam is provided for the vante disposal control panel . 3 Site Monitoring
- u. RIC-8 and RIC-9 These channels conciot of radioactive air-borne particle detectoro identical to RIC-1. Each in housed in a venther proof enclosare.
- 4. plant Area Monitoring
- a. RIA-1, 2, 3, 4, 5, 6,,
Each of these detectors are single element Geiger-Mueller tubes v1th approximately 40 inches of cable connecting each detector tube to its count rate meter. A continuous meter indication and an audibic signal are provided. RIA-2 is provided with a remote indicator and p. lam in the control rocn. . 5 .Reneter Control Room Cabincto The control roam cabinets are provided te hcroce the ten ecnputer-indicatoro, power supply, audible alam, calibration and aQur'anetnt f panels.
- 6. Recorder A multipoint strip chart recorder is mounted in one cabinest to record all RIC channelo. Points are reconled at approximately thirty seconds per point.
7 Summary The various components of the radiation monitoring system, their function and sensitivity are tabulated in Table 220-1, below. TAELE 220-1 CHARACTERISTICS OF RADIATION MONI'IORING SYSTD4 COMP 0NENT_S Channel Func tio,_n_ Sensitivity RIC-1 . Detect radioactive particulate 10-9 to 10-6 ue/cc in the vapor container RIC-2 Detect radioactive gas in the 3 x 10-6 to vapor container 3 x 10~3 ue/cc ( RIC-3 Detect activity in the stack 2.0 x 10*7 ue/cc feed duct 4 RIC-4 Detect activity in ccruponcnt 0.01 to 10.0 mr/hr cooling vater 1/27/61 l _ _ ___ , . __.. _..__.m_ _. _ _ _ - - _ _ _ _ _ - . . _ _ _ . _ _ . . .- . _ _ _ _ _ _ . -. _ _ _ . _ . _ _ _ _ _ _ _ . _ . c.s v . s Punetion Senoitivtt y g_ang1 R1 C-5 Detect activity in steam generator 0.01 to 10.0 mr/hr blevdovn vnter T00-6 Detect activity in liquid vaste 10'0 to 10-2 ue/cc effluent TUC-7 Spare 0.4to400mr/hr T00-8 Detcet radioactive particulate 10*9 to '10 0 uc/cc l in site ambient air TGC-9 Detect radioactive particulate 10*9 to 10' ue/cc in cite c.mbient air k to 100-10 Petect fission products in the 2 x 10'1 primary coolant 2 x 10~ ue/cc (sensitive above 0.8 mev. ) IGA-1 Detect activity in reactor plant 0.2mr/hrto200 control room. mr/hr
- RIA-2 Detect activity in charging 0.01mr/hrto room in control and auxiliary 10 mr/hr
( building . RIA-3 Detect activity in sampling 0.01mr/hrto room 10mr/hr - RIA-4 Detect activity in chemical 0.01mr/hrto j preparation laboratory 10 mr/hr l RIA-5 Detect activity in vaste 0.01mr/hrto ! treatment plant control roam 10 mr/hr TGA-6 Detect activity in health 0.01 mr/hr to physics office 10mr/hr o I i3/7/61 (s . _ _ _ _ - . _ . = . - - _ . - _ . . . _ . , _ _ . ._ . - _ _ a4h& Ce - --ma_- 2 1.6A- AA &-4as h-.4h-.-,.d,. , 'ah--,+ ---W_.-.24-.3..ee--h- ,. +i-=Am h..-Se.4+m&*4 Aman.m-mWJ,- 4M_-*.af._e A4-saar_- h ad W -aam A aa n-_m- a +--,s m- p ge m.4ydd pe asme m 4 - t r . I E 4 1 if.-- r l 5 a, u - t ~ ~ ~ ~ ' f , i -(--- b i !.gsn !id. li"HguQ SL 'I(i!< 3 .e oni [f!!!{. qp
- f. I'igry 3 t?H
$iIiiE D'" d , nr 1 v h a b $ $ ?r I I. IT i -- if ' - -i -{l'[ L l i O e n ET I TT, T i ! ?(6MP ;; a p , r i r is pa '!p_l i -n ., E D l 5 ,, t--q 7 l- g ;n I ar. a n . . , l T , . - 'a, p r r e i W r a ;3 g {$ l - S' g l' i v3 I a A i . > a l 3 I r -- l {di - l I
- y a
*
- e
, s- T i- - ] . I W j ' 8 W l I (t o l l -l i i i, I g _ -_ i - , 55 I f fl l{ t .. a r t s ,' 1 ? , div 3 .
- e. .,
t , I hL I l > 'b l 1 I y t- l* , 1 - i .: .t tg g 1 g-o- I t y i, g t $} je _ _ J ,---,.l - l -{} c p + _, y I i i _ 1 bg j- -( ,c.a 1 ! ,,e,~e, 2~imo,me. I ..o niano 4! I a * /,L-FIQURE 220-1 . - . .-.. . . . . - .-._,;.--. . . _ - . . -.. . . - .,. . -.. - -- ---.a.-- 221 221 - SHIELDING 1 A. General ! The radiation shielding is designed to provide biological protection wherever a potential health hazard from radiation exists. The shielding is divided arbitrarily into five categories according to function. These are (1) neutron chield, (2) primary shield, (3) secondary shield, (h) fuel handling shield, and (5) auxiliary shield. The shielding described can be seen on 1 Figures 201
- 201 h, 201-5, 201-6, 201-7, and 201-8. !
l B. Neutron Shield l i The compartment in which the reactor vessel is located is filled with sufficient vnter (minimum of 4 f t. radial thickness) to tr+ vent neutron activation of the plant camponents within the containment vessel and to prevent overheating or dehydrating of the prbnary and secondary concrete shield immediately surrounding it. The primary concrete over the reactor vessel l together vith the reactor vessel and internals vill provide the necessary ' neutron protection in the axial direction. . . C. Primary Shield This v111. consist of a reinforced ordinary concrete (p = 2 3) structure, bnmedittely adjacent to the exterior of the neutron shield which serves to attenuate radiation from the reactor to the same level as the 4 radiation emanating fras the main coolant system. The bottom portion of the shield is an integral part of the main structural concrete support for the reactor vessel. The radial shield consists of a 5-foot thick conrete vall separa+1ng the reactor area from the primary equipent area, and a 15-foot thick concrete annular vall' extending from the main structural concrete to the operating deck above the reactor. This portion of the shield serves as a canal which, together with the contained water, acts as a shield during refueling operations. Removable block shielding (5 feet of ordinary concrete) is provided above the reactor vessel to reduce the sky shine radiation to below 2.0 mr/hr during full power operation. Penetrations in the primary shield have been arranged to minimize streaming effectc and, where necessary, shielding plugs have been provided to maintain the effectiveness of the shield. D. Secondary Shield The secondary shield consists of reinforced ordinary concrete (p = 2 3) and' utilizes the earth surrounding the containment vessel belov grade elevation to limit the dose rate outside the container to less than 2.0mr/hr. The vertical portion of the shield, inside the containment vessel, consists of an ordinary conemte vall, separating the primary frcan the auxiliary ccuupartment. This vall is 3 5 feetthick fra the operating deck to l Elevation 800' - 0", belov which it tapers to 2 5 feet. In addition, a 1 5-i foot thick annular concrete vall surrounds the entire plant within the containment vessel. 3/10/61 L __ - - - - - - . . . - - - - - . - . - . . . . . _ . ~ - . . . . - . . - . - - _ . - - 221 Supplementary secondary shielding is provided external to the enntainment vessel. The reactor cetupartment as surrounded by a 3-foot thick concrete vall extending frca 5 fc 6 Teelev grade to a point 3 feet abc e grade. The pipe tunnels outside the reactor and primaty ecopartments are shielded by 3 feet and 2 rect concrete slabs rupectively. The operating floor over the primary ocupartment consists of a 3 5-fcot thick conrete shield which serves to reduce the sky shine radintton frcn t.he primary equirnent to below 2.0 mr/hr. In addition to providing safe radiation levels of less than D sr/hr outside the containment vessel during full power operation, the secondary ahielii serves to reduce ,the shutdown radiation levels to permit extended cwess times vithin selected areas of the container. 'the control rod roca, in which are 10cated the centrol rod drive mechanisms. is shicided by an ironeshot filled tank vnich vill reduce the radiatien levels in that area to less than 15 mr/hr eight hours after the plant is shut down. Penetrations in the secondary chield have been arranged to minituis.e streaming effects and vhere necessary supplemental shielding has been used. E. Nel Mano tag Shield The fuel handling shielding is designed to insure protection to personnel durang the unloading of spent fuel elements and control rods. The reactor shield compartment vill be flooded to a level of 17 feet above g the vessel seal line during the refueling operation to provide shielding t and cooling for the spent fuel as a blies. F. Auxiliary Shield Auxiliary shielding is provided to protect personnel in the control and auxiliary building frcn the radiation emanating frcn the equiInent located in the charging pump area. The chielding consists of l'8" of ordinary concrete and vill m sult in a dose rate of 0 75 mr/hr at the outer surfaces of the shield. G. Design Basia Tne design criteria for access to this plant require that no one enter the containment vessel when the reactor is hot critical or operating at pover, and that the plant site be evacuated in case of a major reactor accident. The fo'.lvving radiation levels were used as design criteria for specifying :Me3dirg: Continuously occupied area 0.25mr/hr Intennittently occupied working areas 0 75 mr/hr Intent.ittently occupied ground avel area during operation . 2.0 mr hr . Fus . handling area durin6 refueling operations 2.3 hr , h& allovable dose rate (based on 40 hr. Week) 2 5 mr hr ( . ./10/61 . . . . - - - . - .- --J . . . .. - -. _ - . - _ _ _ . - ~ . . _ _ - - _ _ . - - - . - - -. - - _ - . - . . - - . - . -. 22203 222 - FVEL HANDLI1D 't A. General The fuel handling tools, equipment, and facilities described in this subsection are designed to provide for the lifting, handling, and
- storage required to perform a cor.plete refueling operation starting with the unica;ing of new core components and terninating with the loading of the spent fuel cask en the off-site carrier.
The items of fuel handling equipment are designed to safely perform a manual, underwater refueling procedure; including the handling of new and spent control rod conponents, and all associated components of the reactor vessel and its internals. The lengths of the fuel handling toole plus thei-associated slings and coupling devices are such that lift is limited to an elevation which assures an adequate depth of shielding water over fuel at all times. B. Reactor Compartnent and Storage Well-A rectangular opening appr6ximately 27 feet 6 inches by 13 feet can be provided in the operating floor above the reactor compartment and associated storage well by the renoval of precast 20-ton concrete slabs. The reactor is located in the west end of this compartment. The east end of the compartment forms a spent fuel storage area. A mininum depth of 12 feet of shielding water is provided over ( the active portion of a fuel assembly during refueling operations when the storage well is at a high water level, and also, when the spent fuel stora(;e rack is in the storage position and the storage well water is at norms.1 water level. A maximum depth of 17 feet of water nbove the contact surface of the reactor vessel closure is provided with a splash depth of approximately B inches renaining below the operating deck. The concrete surfaces of the reactor compartment and storage well are lined with a Serica 300, four-coat catalized phenolic protective lininc made by the Carboline Corporation. Underwater lighting is provided by means l of 5 - 1,000 watt removable lighting fixtures located around the periphery of the storage well in any one of six positions, and 2 - 500 watt lights on the traveling personnel bridge which can be lowered beneatn the surface and positioned anywhere along the central area of the opening. Underwater type lights with aluminum materials are used where metal parts must be in contact , w% h borated water. Other materials in contact with the storage well water are mtde of either aluminum or atainless steel. C, Fbel Handling Equipment, Tools and Structures
- 1. Rotary Bridge Crane A 20-ton rotary bridge crane with a single two-speed hoist having a 60-foot lift is mounted on the containment vessel shell. The t
hoisting speeds a-e 5 and 15 fpm, and in addition special inching control ) ( is provided. The low speed will permit safe handling of the reactor vessel head and core components.- The higher speed is for raising or lowering tools-and equipment into shielded compartments. The traverse speed of the trolley /28/63 222e is 25 fpm. The bridge will rotate 3700 at a traverse speed at the rail ( of 25 rpm. The fuel elements will be handled by a reparate hoist attached O to the trolley. This hoist has speeds of h end 12 fpm. ,
- 2. Tools for Handling Puel Bearing and liighly irradiated Core Components These tools are attached to the hook of the lifting mechanism by slings which have sufficient length to prevent the elevation of radio-active components above a safe level in the shielding water. They consist of riCid shafts with positive mechanical gripr .ng devices at the lower ends and actuation devices at a level convenient for operators on the personnel bridge. A spring scale is used in conjunction with the tools as a sensitive guide to the lifting force being exerted. These tools consist of a fuel assembly and control rod handling tool, a special fuel rod handling tool, a utility actuating and locking tool, an instrumented test element handling tool, a control coupling tool, a noninstrumented test element and "L" shaped subassembly handling tool, a fixed core instrumentation lifting adapter, and a utility handling tool.
- 3. Spent Fuel Storage Rac'k The spent fuel storage rack is a rectangular, stainless steel, crate type structure which is located in the storage well. The rack can be moved vertically in guides by the rotary c 'ane between the refueling and storage positions. It is held in the upper position by mechanical latches,
( and when in this position fuel in the rack is at the same elevation as the fuel in the reactor vessel, thus facilitating handling of components. When the rack is in the storage position, the workir.g area around the reactor vessel flange is adequately shitided from stored components by storage well water at the normal operating level. The fuel bearing compobent storage compartments in the rack are arranged i'i slabe separated by a minimua of / 12 inches, fuel to fuel. [ t h. Spent Fuel Transperting Cask and kily A spent fuel transporting cask, designed to meet 100 Bureau of Explosives, and AEC Regulations, will be provided by Westinghouse as required. The cask, which will carry a maximum cf four Saxton fuel assemblies, I will be transported to and from the site and loaded vertically. It will be l moved through the containment vessel equipuent access port horhontally on a dolly which runs on tracks through tho equipment accese port. The cask is I supported on the dolly by four saddles which are located ur. der four of the
- cix cask trunions. The wheels of the dolly can be braked to control or stop i
its movement along its track. The cask will be transported to and from the site on a special truck trailer.
- 5. Miscellaneous Teols. Eouipment, and Structures Additional tools, equipnent and structures which are provided to facilitate fuel handling includes a traveling personnel bridge, a concrete slab lif ting frame, a storage bracket for the reactor vessel head insulation
( can, racks for handling and storing the reactor vessel head studs, guide studs and indicator rods for the reactor vessel head, a reactor vessel head lifting device, a reactor vessel head stcrage structure which consists of a concrete ring on the operating floor designed to shield the irradiated central underside of the head sufficiently to prevent a significant increase in activity in the general /28/61 area and t permit manual installation of new head gackets, a barrel lifting device, a new fuel element carrier and an underwater shear. _ _ . _ _ _ _ _ _ _ _ _ _ _ - - ~ _ 223 223 - CONTAIUMDIT r A. General The containment vessel is a vertical cylindrical steel vessel with a hemispherical head at the top and an elliptical head at the bottm. It is 50 feet in diameter and has an over-all height of 109 ft. 6 in. The bottom of the vessel is located 50 ft. 4 in, below grade with the bottom head embedded in concrete. Tne portion of the containment vessel vall that is be> grade is provided with an inner vall of reinforced concrete that is 1 ft. 6 in, thick. The primary purpose of this vall is to reinforce the below grade cylindrical portion of the containment vessel shell against external pressure due to ground vnter and backfill and to contribute to the support of the concrete operating floor. This concrete also provides shielding and serves as a missile barrier to protect the containment vessel frm penetration by small primary system camponents (valves or instrument vells, etc.) that might act as - jet propelled missiles in the unlikely event of their release frm the piping. One-half inch thick, pregolded, expansion material is provided between the steel shell and the inn,er concrete vall to a depth 6 feet below grade to provide for differential expansion between the steel shell and the inner concrete vall. When the reactor is operating at power, the containment vessel is closed and pressure tight. All access openings, connections, ard pipelines j vhhh are not required for operation are kept closed with tight shutoff valves or gasketed doors. Pipelines not required for nomal operation, which enter the containment vessel, are provided with valves that are located outside the vessel. These valves are kept in a closed position to maintain the integrity of the containment vessel. Pipelines required for nomal operation are adequately , valved vbere necessary tc maintain the integrity of the vessel. Quick closing valves, which evi be closed frm the control room, are provided in the inlet and outlet air purge lines. No personnel may enter the containment vessel when the reactor is hot critical or operating at power. Personnel locks have been prcy .ded, so that personnel can enter the vessel to perform inspections or minor maintenance when the reactor is shut down vith all the control rods in and the main coolant system is still at operating temperature and pressure. The general arrangement of the containment vessel is shovn on Figures 201-3, D01-4, 201-5, and 201-6. B. Design pressure The vessel is sized so that the main coolant can, in the event of a rupture, flash to an equilibrium mixture of water and steam, without ev.cedi.w, the design pressure of the vessel. The design pressure of the containme vessel is 3Q gig (refer to Subsection 506). Tnere an openirge between une various campartmente to allow pressure equalization. The op oe. n used to establish the containment vessel design pressure emphasizes e uservatist. with I respect to both method of calculation and the selection of .', ant data for use in these calculations and vill be des'oribed in Section 500, Accident Analysis. /20/61 y . .. .__ _ ____ _ a 823 C. Design Features A
- 1. Design Conditions Vessel Diameter 50 feet Tangent Length 72 feet Internal Design Pressure 30 poig Internal Decign Temperature 2500 F Maximum Vneel Load Frcra Rotary Crane 50,000 lb.
Number of Crane Wheels 4 Unifom External Pressure Due To Vacuum Within The Vessel 0 5 psig Gross VolLume 1p0,200 cu. f t. Het Volume ( Approximate) 141,500 cu. f t. Wind and snow loads vere investigated in order to detemine their relative importcace in the over-all design. The vessel vill withstand an 80 mph vind load (20 psf) applied to the vertical projection of the above grade portion of the vessel and a snow load of 25 psf applied to all portions of the hemispherical head with a slope within the range of 0 to 50%.
- 2. Materini and Fabrication The design and fabrication of the vessel is in accordance with the ASME Code and the latest applicable . code cases. Steel plate and all other pressure parts of the vessel confom to AS7M Specifications A-201 Orade B
( Firebox CNality and in addition are heat treated to ASTM A-300 Specifications for plates and A-350 Specificatsons for forgings as covered in Code Case 1272N. All velding, stress relief, radiographing, and other inspection and test procedures used to conform to the requirements of Section VIII of the ASME Boiler and Pressure Vessel Code as modified by Code Case 1272N. Shell velds are fully radiographed, double velded butt-joints. All velds, such as those , around nozzles and opening frames that cannot be mdlographed so as to successfully detemdne a flav, vere examined for cracks by magnetic particle or fluid penetrant methods of inspection. All doors, nozzles, and opening ;1 Ames are preassembled into shell plates and stress relieved as ccruplete assemblies before they are butt-velded into the shell. Openings are designed and reinforced so that all parts are at least as strong as the shell itself. The portion of the containment ve:.sel which is above grade is not insulated. A refined cual tar enamel (Bitumastic) is applied to the outside surface of the below grade portion of the vessel that is not embedded in concrete. 3 personnel Access Locks Two personnel double door assemblies are mounted in the vessel shell, slightly above grade level, at locations shown on Figure 201-4. One assembly is for nomal personnel access to and frren the vessel and the second provides an emergency exit frcin the vessel. Each door assembly consists of two pressure-tight, latched doors, mounted in a cylindrical section. Each door is designed to withstand the design pressure or vacuun within the vessel without leakage, and opens toward the inside of the vessel so the.t the vessel ( design pressure vill help to fom a seal. The doors for nomal access are 2 ft. 6 in, by 6 ft. 8 in, and the doors for emergency escape are 2 ft. 6 in. in diameter. /20/61 . _ . _ . . . . . . . . __ o 223 3
- k. Equi 1rnent Accecs Openings
% One finnged and bolted access opening for the removal of fuel casks and reactor plant eceponents is mounted in the vessel shell slightly above grade level at the location shown en Figure 301-4. The opening is designed to withstand the design pressure or vacuum within the vessel and vill utilize any internal vessel pressure to help effect a leak ~ proof seal. The opening is 6 feet in diameter. . 5 piping and Ventilating penetratfens All piping ata ventilating penetrations are below grade except for those penetrations for vacuum breakers and ventilating air. The penetrations for lines vhich operate at a temperature below 2500 F consist of a section of the carbon steel or stainless steel pipe system velded to the vessel pinte and stress relieved in the fabrication shop. The penetrations for J W h safety injection lines and lines which operate at a temperature greater than 2500 F utilize themal sleeves that are sealed to the pipe system by means of an expansion joint or a solid metal end connection.
- 6. Electrical penetrations Each cable entering the containment vessel entera through a seyarate cable penetration. The cables entering the containment vessel are of five basic constructions; these are (1) mineral insulated viLh a metallic sheath, (2) silicone rubber insulated with a lead sheath, (3) coaxial and (1 triaxial instrumentation cables with polynthelene insulation and a vinyl or similar jacket, (4) plastic insulated strain gage leads, and (5) var-glass insulated themocouple leads. The basic penetration design for each of the three types of cables is shown on Figures 223-1, 223-2, and 223-3 The containment vessel fabricator supplied and placed all couplings for all penetrations. All couplings vere in place, velded and plugged on both sides at the time of the containment vessel pressure test, thereby testing all velds.
As shown on Figure 223-1, Detail #1, each MI type cable is pressure sealed by a pressure gland seal thmaded directly into the coupling on the outside of the containment vessel. A pipe tee and second gland seal on the inside of the containment vessel is provided to allow testing of each indi-vidual penetration. The only rubber insulated lead covered cable is that provided for the main coolant pump, consisting of 3-1/cg350 M0H nbleweiliE compounds vill be pumped into the cable to prevent'p Esage of gas through the conductor interstices. Figure 223-2, Detail fl, shows the basic penetration design. One end of the chamber is filled with ccupound to assure a pressure seal. The other end of the chamber and its pipe plus provide a means for testing the assembly. All coaxial and triaxial cables are teminated in a pressure , sealed receptacle on the outside of the containment vessel, as,shown on Figure 223-1,Detailf2. A pipe tee and sealing bushing on the inside of the contain-ment vessel is provided to allow testing of each individual penetration. Where plastic insulated strain gage and var-glass insulated thermo-(. couple leads are required to Ienetrate the containment vessel, the leads shall be cut, the 1naula tion vill be removed frca a section of the solid conductors which vill then pass through a "Conax" bare vire themocouple Bl and with sealant plug as shown in Figure 223-3 The "Conax" gland forms part of the penetration i/20/61 1 l 223 1 assembly. The pipe tee is previded to facilitate the adding of additionni sealant material and testing. 7 Testing Upon ecx pletion of erection of the containment vessel, but prior to backfilling, the pneumatic testing consisted of th2ie phases. First, an initini lov pressure (5 psiB) soap bubble test of all vessel velds, seals, and penetrations subject to internal pressure vas performed. Second, a hi6h pressure test at a pressure equal to 125 % of the internal design pressure was perfomed after.the successful ecznpletion of the initial soap bubble test. Third, a second soap bubble test, a leak rate test and a third soap bubble test vere perfomed after the internal pressure was reduced to the design value. As a result of the leak rate test, it van determined that the containment vessel 6 leakage rate was 0.04% 10.093% 'of the contained volume in 24 hours when the vessel was at design pressure, and ccxnpensations were made for changes in temperature . , A final low pressure soap bubble or vacuum box test vill be; perfomed after the internal structures have been erected, the equi;xnent installed and the temporary construction opening in the shell revelded and radiographed. The inspection vill be limited to new velds performed since the '[ previous test. I ( 3/28/61 ) 1 1 ; .l j Q'b <. *ji-- t I g rl llf -l g 3 - 2 }1 ! { *4 1 . a 9 t_..nl1 jj 'j~$ ,! ,il1- ~ ,l .a.. !,! I, hI M j' i i . {' [I !3ffh ikit ; 1 = . lJ
- i y$ e
< - ' %- 1.f ' g- _ m e, i n; W 1 i + jg ! M N dj ,;t I !! j l 81 n n, . ,Jj L~ . h - * 'N t '),
- \
. . o ' ;N ' 2 j / I ' '~ Y ,g. - k-4 g-- , {- 7 3 \ 'A [ ) ) ) l !f $[j . ll V I , I i a J \ '
- 1. . M -{
y-m . . d,.:::A ,pl} ji )llk 5 t Y l, l l t' I d ll - ., .v-l v ! / Q/ , . FIGURE 223- ! _ _ _ ___ ___ A ,_-.-- 2 _ .__- m _ _ . _ _ . . _ _ . _ . . - _ _ _ _ . ._m - . _ . _. _ _ = 1 1
- l a, f f N f
- .m 's Y{ ? t-] 'n jl k li pl Q ! i al 2 l .4%af,g [,,-3 ] []3 c m '" J, J ,f ' lT T (8 ! : InMBI uG :i Ql), i y 'I i i t 'l fjft 0 i 4 v. immmmmnemunw gmunnp a u ~J r. ema. a el .-' : . L t. < O>J {' , 7 ./ s,J N A ',u ' {
- ! 9 i !
g !! ' _ ~ N)o ([ ~ 1 ; cL I ? ! /, , - m.--g 'N l: -,1,\ i ' e } j,'y - d J J t_ J -l#d N; __ g
- g jj
-~1 ( - + h> .m,1 ;' ) , hjn 1 ;) ILt- a , ' L)Md_ &p y ! I i :. t i i ; - f, n ;: a \! i, ( '(F ) arms. .- m m m m m , 1 ( t FIGunE 223-2 [ l jf . i fl( j hl[h s a ;,, k, h ,l k y 3. - A 3' a I mh! l j' ;a RW - - t , ' B; g f,7 , } y!! E i a,k < jll& llh,'f'k ,- yt V ' ,r flbf j l/ - ~ , i & ff . i , m., . a
- la
!c 1;, i bl w.S, g oft .lle-cx ({ fl i NJe ' ' L, 0 t# j %d ;l N '!y$ ~ / M', . . 'c g y ,; 3 6 I , } Au f-l g [] , N y ih (; I b xl oS 3 ,$"9 f* th>, ! K; 51 , x y Y ,e '^ 0 }/ ll ,y f QJ4 ll h. % .c i b ^t e= sg f6 1 !) l } la va b' h) . ! 4 4 l na i? h bk ~ l bi & kfu h k l AY u v y si 8 [, .< ;i 1 l };.hs&& . <? . h dI ~ ' ~ ^ - }} :!,i. N ' g , # " fi: 8 h ffH TN ;% ha$:' / " 5 ]#hJ/ n,s , >i Pd d Q )L}J ' ij ( M} 4 FIGURE 223-3 - - - _ #"'T- ,, SECTION 300 k DESCRIPTION OF OPERATIONS 301 ORGANIZATION 302 AIMDlISTRATIVE POLICIES AND PROCEDUES 303 RALIATION PROTECTION 30h PLANT ERECTION3 INSPECTION, AND PREOPERATIONAL CECKOUT r 305 NOR!%L OPERATING INSTRUCTION 306 EERGENCY OPERATING INSTRUCTIONS 307 1:AINTENANCE 308 INITIAL CORE LOADIN3 AND LOW POWER COE TESTS 309 INITIAL P0h*ER OPERATIONAL TESTS
- 310 CHEMICAL SHD1 TESTS
- 311 SPDID ELEMENT TESTS
- 312 BULK DOILING TESTS AND IHORPJ SED SPECIFIC POWER TESTS
- 313 BOILDIG WATER OPERATION TESTS
- 31h NUCLFJJt SUPERHEAT LOOP TES7S l
l l l I (
- Subsections not included with initial report. May be submitted in future as amendments.
3/??/61 301 l 301 - OInANIZATION t A. neneral The Saxton Nuclear Experimental Henctor Project involves a partner- I ship arrangement with the Vestinghouse Electric Corporation in which the nuclear power reactor facility owned by Saxton Nucleur 2xperimental Corporation (SNEC) vill be utilized to conduct a five year research and development program. Westinghouse has the responsibility of initiating, planning and carrying out the research and development program. Saxton has the responsibility for operating and maintaining the nuclear facility and assisting Westinghouse in carrying out the program. The organisation chart for the project is shown on Figure 301-1. The project is guided by a Steering Committee made up of engineering-management and consultant personnel representing both Westinghouse and SNEC. The prime function of this committee is to review the progress of the research and develo pent program and to approve changes or additions to the program. The Henctor Safeguards Ccmittee is made up of engineering, scientific and ' consulting personnel representing both Westinghouse and SNEC. This cacxmittee ' and its function are covered in Subsection 401 under Technical Safeguards Control. Both the Saxton General Manager and the Westinghouse project Manager are ex officio members of both the Steering Ccmittee and the Henctor Safeguards Cormittee. In addition to the job 11assifications that are assigned to the Saxton nuclear facility on a full time basis, additional job classifications k from the existing station vill be used on a part-time basis for maintenance, general services, and operation of the existing equipent and non-nuclear equipent that is located in the existing station. Security measures vill be taken by means of fences and restricted areas and by using the operating force that vill be on duty at all times. Therefore, no guard force is being provided for the nuclear facility. Westin6 house vill assign personnel to the Saxton nuclear faci 3ity as required to supervise the startup and preliminary operation of the reactor plant and to carry out the research and developent program. B. Nuclear plant Organization
- 1. Nuclear plant Superintendent The nuclear plant facility vill be under the direction or a Nuclear Plant Superintendent who vill be rerpon,sible to the General Manager for the safe operation and maintenance of the nuclear plant facility as well as for coordinating and expediting the research and clevelopent program. In carrying out his responsibilities, the Nuclear Plant Superintendent vill coordinate the planning of operation and maintenance schedules with the General Station Foreman of the existing Saxton Steam Generating Station.
- 2. Operations and Tests
( Supervision of the nuclear facility operation and collaboration with Westinghouse representatives in connection with the research and develop-ment program vill come utder the direction of a Supervisor-Operations and Tests who vill be responsible to the Nuclear Plant Superintendent. To assict him in 3/21/61 { 301 i. i carrying out his responsibilities, the Supervisor-Operation]s and Testa vill have ) under his direction Recetor Plant Supervisers, Reactor Plant Technicians and 1 ( Test Engineers. A Reactor Plant Supervisor vill be in direct charge of the operation of the nuclear facility. There vill be five Reactor Plant Su;ervisors to take care of four shift crews and serve as a relief man for both the Reactor Plant Supervisor and the Reactor Plant Technicianc. The Reactor Plant Suyervisors vill be AEC licensed reactor operators. In addition to the routing o;eration of the nuclear facility, the Reactor Plant Supervisor vill have the responsibility of, operating the facility ao required to carry out the research and development program. In this connection, he vill be guided by detailed operating procedures which vill be jointly prepared and approved by Saxton and Westinghouse. ; Four Reactor Plant Technicians, one on each shift, vill nesist the Reactor Plant Supervisors in operating the nuclear facility. It is pinnned that these technicians vill also become AEC licensed reactor operators. These techndcians vill se aupervised by the Reactor Plant Supervisors, and will assist , them by making inspections of the facility, logging o;erating data, and operating valves and controls. % I Two Test Engineers vill accist the Supervisor-Operations and Testa 1 in carrying out his responsibilities in connection with the research and develo pent program. These engineers vill work with Westinghouse personnel in making plans for tests and vill help prepare and review schedules and detailed operating procedures in connecticn with the various tests that vill be performed. g They vill also instruct the Reactor Plant Supervisors and Technicians regarding test equi;raent. test procedures and data requirements. l Operators presently working in the existing station such as switchboard operators, turbine room operators and condenter and pump roam operators vill remain under the control of the shift foreman in the existing steam station; however, their work schedule and daily operating procedure vill be coordinated by the Nuc1 car Plant Superintendent and the Saxton Steam Station General Foreman so as to satisfy the requirements of the nuclear plant. 3 Reactor plant Services _ Reactor Plant services vill be under the direction of a Supervisor-Reactor Plant Services who vill be responsible to the Reactor Plant Superintendent for such matters as radiation protection and control; chemical control; main-tenance of reactor pinnt equiIraent, instruments, and controls; and general housekeeping. To assist him in carrying out his responsibilities, the Supervisor-Reactor Plant Services vill have under his direction, a Radiation Protection Engineer, a- Radiochemist, and two Instrument and Control Technicians. Tne Test Engineers may also be used to assist or substitute for the Radiation Protection Engineer and'Esdiochemirit. The Radiat' ion Protection Engineer vill be responsible for the control of radiation contamination, radiation exposure and good safety practices. His duties shall include the following: coordinate the release of pisnt f effluents with the Radiochemist; define and tag hazard areas; complete radiation . t work pemits; ccmpute vorhing time ltmits; perform radiation and contamination surveys; direct deemtainisation procedures; maintain complete records of j radioactivity releases and of area and personnel mcnitoring; instruct employees 3/21/61 . ; 301. in personal safety and establish that safety rules are obeyddj and arrange for, . and cause to be used, all safety devices and clothing as required for radiation exposure control. The Radiockemist shall be responsible for all nuclear plant chemistry, including primary and secoadary cycle vater treatment and the chemical and radiochemical control cf liquid and gaseous vaste processing. His duties shall include the following take and perf om chemieni analyses on plant vnter camples, keep records thereof and take steps to maittain required water conditions; take and perfom chemical and radiochemical analyses on samplec from campling points in the Radioactive Waste Disposal Facility as required to maintain the chemical and radiochemical control of the facility; coordinate the release of plant effluents with the Radiation Protection Engineer, and make or tequest arrangements for radioisotopic identifientions required for control and safety. , The Senior Instrument and Control Technician shall be responsible for the calibration, routine maintenance, and repair of the nuclear facility operatit 9 instrumento and control equiinent and also pertable and laboratory inst ractts . He shall be assisted in carrying out his work assignments by a Junior Instrument and Control Technician. Maintenance men from the existing station vill be assigned to the nuclear facility as requested by the Supervisor-Reactor Plant Services. Personnel who are so assigned to the reactor plant vill be under the control and supervision of the Supervisor-Reactor Plant Services, or his representative. ( C. Training All persons who have been assigned to the full time operating staff of the nuclear facility were recruited from the four SNEC shareholder operating utilities shown on the front cover of this report. The top supervisors (the Henctor Plant Superintendent.- the Supervisor-Operations and Tests, and the Supervisor-Reactor Plant Services) were selected on the basis . of their academic training, and the experience received on other nuclear ' l projects. These men have been participating in the design and construction l phases of the Saxton Project and vill obtain further on-the-job training during the startup phase at which time the various auxiliary systems, the main coolant cyctem and the reactor vill be started up systematically under the supervision of experienced Westinghouse personnel. Prior to assignment to the Saxton Project, the nuclear training of all other full-time employees was l limited to a General Orientation Course given by SHEC. These employees were selected on the basis of their interetit in the project, their perfomance in , the General Orientaticn Cource, and their work experience with their hczne company. The training that is being provided for these men falls into four cate6eries. Tnese categories are (1) general orientation, (2) speciality schools, (3) resident training and (4) on-the-job training at the site. I Each person (excluding the top supervisors] y ,1gned to the Saxton Projcet on a full-time basis, as well as the supervisors and many of the key operating and maintenance personnel of the existing steam station, vere given the General Orientation Course. Tne course was of a comprehensive introductory i nature nimed at thoroughly acquainting each trainee with the fundamentals of nuclear technology and more detailed aspects of the Saxton reactor facility so that the maximum benefit is obtained frcn later and more spec.ialized training. Th18 course consisted of approximately G hours of leW ires, training films and examinations and van taught by Saxt on to)~ cupervii fy p sonnel. l_3/21/61- . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _. _ _ __ _ ___ __m_ _ _ _ _ _ _ __ 301.- Those persons selected for the job classifications of Reactor Plant Supervisor and Reactor Plant Technician are given further academic training in nuclear physics, reactor theory, radiation control, instruments and controls and reactor operation. Two courses are presently being utilized for this training. The firnt is a course of two veeks' duration given at the Nuclear Reactor Facility of the Pennsylvania State University, and ic taught by the supervisory staff at the Reactor Facility. It consists of )cetures on the above subjects, reactor experin,ents, reactor operation, ani examinations. Each trainee is given the opportunity to start up and shut down the swimming pool type reactor at least ten times during the two weekt' period. The second cource is given after the completion cf training at Pennrylvania State University. This course, which is of ten vecks' duration, is given by the Westinghouse Electric Corporation at its reactor facilities near Waltz Mill, Pennsylvania. The course includes eight veeks of on-the-job training at both WTR and WREC, and two veeks of classroom work devoted to acquainting the trainees with the nuclear aspects of typical pover reactor startup and operation. Upon completion of their training at Westinghouse, the trainees return to the Saxton site and obtain additionni training by following construction and studying the facility system descriptions. Part of these men's on-the-job training vill consist of developing more detailed operating procedures from the operating guides that .. ave been furnished by Westinghouse. These men vill also receive additional cincoroom instruction given by the Gaxton top supervisors and Westinghouse personnel. Those persons assigned to the specialist classifications nuch as Radiation Protection Engineer, Radiochemist, Test Engineer and Instrument and f Centrol Technician are being trained by attending speciality schools and through t resident training at Westinghouse nuclear facilities. The radiation Protection Engineer attended two consecutive two-veek coursesin " Basic Radiological Hen 1th", and ' Reactor Environmental Henith Problems", given at the Robert A. Taft Sanitary Engineering Center in Cincinnati, Ohio. He was then assigned to the health Physics Sections of the Westinghouse Atamic Power Department and the Westinghouse Test Reactor for on-the-job training. The radiochemist is receiving on-the-job training with the Chemistry Section of the Westinghouse Atomic Power Department. One Test Engineer attended the Robert A. Taft Sanitary Engineering Center courses with the Radiation Protection Engineer and was then assigned to the Test Section of Westinghouse Atomic Power bepartment for on-the-job training. He completed seven months' training in the test section and vas then enrolled in the training course being given to the Reactor Plant Supervisors at the Westinghouse renetor facilities at Waltz Mill, l Pennsylvania. The Senior Instrument and Control Technician spent one month l vorking with the instruments and controls group at the Westinghouse reactor facilities. He was then enrolled in a three-week course entitled " Fundamentals l of Instrumentation" given by the Foxboro Company, af ter which he vill return to l Westinghouse facilities for further training. The men assigned to the specialist l classifications vill return to the Saxton site several mo iths prior to startup to receive additional on-the, job training, relative 'to their respective P.reas l of responsibility. l The supervisors and several of the key operating snd maintenance personnel of the existing Saxton Steam Station vere given the General Orientation Course described earlier. Additional courses vill be given periodically during ( ( the conntruction phase for existing station rersonnel. These coursesvill be aimed at acquainting the trainees with detaia.ed aspects of the Saxton nuclear facility, and the maintenance and operating problemq associated with it. Emphasis vill be placed on that portion of the facility locatt:d in the existing station and with which the trainees vill be directly associated. = ___ __._.._ _ _ __.__~_._____ _._ _ . . _ _ _ _ _ .____ 301. The training and experience already received, that which it in progress, f and that which is pretently planned for full-time reactor plant job claccificationc is su:=arind in Tabic 301-1 belovt TAILE 301-1 PETC0!iliEL TRAI!iI!!", AliD EXPERIEllCE Job Classification Training Reactor Plant Superintendent Graduated from the Carnegie Institute of Technology, IG (12). Registered Profes ' al Engineer in Pennsylvania. Worked with the Atcnie Power ueveloluent Associatec Inc.,in the Test Operationo Section during the period January 1953 to April 1960. Attended the third Shippingport Nuclent Power Station Training Program April 1960 to August 1960. Started work at the Saxton cite Aucunt 1960. Supervisor-Operatione and Tecto , Graduatt ^ fram the Penncylvania State University, IG (EE),10 (EE), Regictered Professional Engineer in Pennsylvania. Attended one-month cource " Atomic Power for Industry" at North Carolina State Univercity in July 19%. Worked with the General Electric Company in the Atomic Power Equilnent Department from November 19% ( to December 1956. During this time, he worked in the areas of control and instrumentation, stability analysis, hydraulic analysis and completed a Nuclear Engineering Course given by General Electric personnel. Worked at the Westinghouse Electric Corporation in connectior with the PAR Project on control and instrumentation, chielding, radiation heating studies and test loop operation, from July 1957 to January 1959 During this same period, he attended Huclear Engineering and Heat Trancier courses 4t the University of Pittoburgh and a Reactor Physico course at the Carnegie Institute of Technology. Has worked on the Saxton Project at the Westinghouce Atomic Power Department since January 1959 I Supervisor-Henetor Plant Services Graduated from the Drexel Institute of Technology, IG (EE). Registered Profeccional Engineer in Pennsylvania. Attended the second secsion of the International School of Nuclear Science and Engineering at the Argonne National Laboratoriec given during - the period November 19% to June 1956. Worked on General Public Utilities Corporation studies for a nuclear plant for the Manila Electric Campany from June 1956 to August 1957 Assigned to
- j. Saxton Project February 1959 Worked on the Saxton Project at Gilbert Ansociates Inc. during the period August 1959 to January 1961. Started vork at the Saxton site Janusry 1961.
I Radiation Engineer Graduated from the Wyanissing Polytechnic Institute in Reading, Pennsylvania. Attended first Saxton General Orientation Course. 3/21/61 } 301.t Attended cources in Basic Radiological Health and Reactor Environmental Henith Problems at Robe-t A. Taft Sanitary Engineering A Center in May 1960. Was assigned to the Health Phycies Sections of Westinghouse Atomic Pover Department and Westinghouse Test Reactor for on-the-jot training in June 1960. Will report to the Saxton utte in May 1961 for further on-the-job training. Radiocham.st Graduate; from Pennsylvania State University, tis (Chemistry). Attended the first Saxton General Orientation Course. Was 7 assigned to the Westinghouse Atomic P9ver Department Chemistry . Section for on-the-job training in September 1960. Will report to the Saxton site in July 1960. - Test Engineer Graduated from Rutgers University, BS (EE). Attended first Saxton General Orientation Course. Attended a course in Basic Radiological Realth and Reactor Environmental Health Problems at the Robert A. Taft Sanitary Engineering Center in May 1960. Was , assigned to the Westinghouse Atomic Pove- Department for on-the-job training during the period May 19601 > January 1961. Attended a Reactor Operator Training Course at the Westinghouse nuclear facilities from January 1961 to the middle of March 196. Reported to the Saxton site for further on-the-joh training in March 1961. ( Senior Instrument and Control Technician Attended the Pennsylvania State University for two years. Attended the second Saxton General Orientation Course. Was assigned to the Westinghouse Test Reactor for one month for on-the-job training with the Instruments and Control Section. Attcnded the course, " Fundamentals of Instrumentation", given by the Foxboro Company, durfng March 1961. Will receive ft.rther on-the-job training at Westinghouse facilities and at the Saxton site. Junior Instrument and Control Technician Attended the DeVry Technical Institute for two years. Will be-given on-the-l ' training-at Westinghouse facilities and at the Saxton site. ReactorPlantSupervisors(4) All are high schcol graduates. One is a graduate of Carnegie Institute of Technology, BS (ME) and one has completed two years of college. The four have a combined total of approximately , i fifty years of conventional power plant experience. Attended ! the second Saxton General Orientation Course. Attended a two-I week course for reactor operators at Pennsylvania State University given in December 1960. Attended a ten-veek course for reactor l operators at the Westinghouse nuclear facilities at Waltz Mill, ! Pennsylvania. Reported to the Saxton site for futher on-the-job l g training in March 1961. 301. Reactor Plant Supervisor (1) s Ilich School graduate. 11ac had twelve years' conventional power plant ope-ating experience. Attended the third Saxton General Orientation Cource. Will attend a two-wek reactor operators course at Penncylvania State University in April 1961. Will attend a ten-veek reactor operators course at the Westinghouse nuclear facilities at Waltz Mill, Pennsylvr.nia, .to be Elven in May, June, and July, 1961. Will report ta the Saxton site during the latter part of July, 1961 for on-the-job training. Reactor Plant Technician (4) All_ are high school graduatec. Three have had a co:nbined total of 42 years of conventional power plant operating experience. The training planned for this group it the same as for the Reactor P] ant Supervisor imediately above. 1 l l 1 l l l i 3/21/61 .g -- JOINT STEERING -- ------------q s i I f @ ' PROJECT _ _ _ _ _ _ _ _ _ , REACTOR SAFEGUARDS SAXTON GENERAL MANAGER COMMITTEE MANAGER _____ @ ATOMIC NUCLEAR PLANT 3 _ g POWER DEPT. SUPERINTENDENTg) ggy i I i i @ R ESID ENT ________________ SUPV-OPERATIONS .___________k _ _ _ _ _ _ _ _ _ _ _ an.~.- REACTOR ENGINEER AND TEST ggy { PLANT SERVICESg,} ELECTRIC STATION FOREMAN SPECIAL PERSONNEL r----- " "----> I I f f REACTOR PLANT SHIFT MAINTENANCE SUPERVISORS g FOREMEN FOREMAN RADIATION ENGR ggy. () INDICATES FULL TIME NUCLEAR STATION PERSONNEL REACTOR PLANT SWITCHBOARD ELECTRICAL ^ TECHNsCIAN (4) OPERATORS TRAINEES MAINTENANCE TURBfNE MECNANICAL RADIO TRAINEES OPERATORS MAINTENANCE CHEMIST m TEST CONDENSER INSTR. REPA!R , ENGINEDiS gg 6 PUMP OPRS. $ WATER TREAT. 1 m H O TRAINEES UTILITY INSTRUrJENT $ g WORKERS CONTROL TECH g u S : SAXTON NUCLEAR PROJECT " TRAINEES ORGANIZATION CHART - 3w . _ 302 - AD!MSTRATIVE POLICY AND PROCEDURES A. Rec o_rdn l Ledger type log books vill be maintained in the main control room and the radioactive vaste treatment plant control room. Date stamps and l ! shift stamps vill be used for these log books and the time of each entry vill be noted. These 108 books vill be used to record such items as emergency shutdowns, norral startups and shutdowns, putting equipent in service or taking equipent out of service, equipent malfunction, abnomal conditions, special perfomance data, and routine system or equipent tests or checko. The shift supervisor vill sign the 106 book at the bottom of entries made during his shift and vill record the names of his assistant or assistants. A separate los sheet vill be maintained for some of the more important routine perfomance data that is not recorded. These readings vill probably be made hourly; however, some of the data may only be recor ad once or twice a shift. Special logo of plant performance data vill be kept when necessary for tests or experiments made as part of the pinnned research}}