preliminary safety analysis report rm volume 3b table of ccntents section _pa 1 inr oduction and...
TRANSCRIPT
, - --
_ ,
r. y .- - -
, , ,.
- ..,
. ... .
O % c c. ,, \..
METROPOLITAN EDISON ObihPANY
TH R EE M I LE IS LAN D """"' *"F*d
NUCLEAR STATION'UNIT 1i
Preliminary Safety Analysis Reportrm
o Volume 3._.
-,-
"
G ,
/sy ff5ID'
-| .',| C 'N'
, . , , ,
'f' '''.~a I^~
'i. '';.. _ ..
;- .. . s.. .. : :: - ':: .,-,,
, C?,", {f'_~l. ; )'
''" , , '
' %. .--[. ,'(.),/
.~ ~ '.
,;
.
,
0002 053O 8o0408o 75 7 I
9 .>R . y 'c. 7 . " ,
... - .
"- -c.=.~:.
A ,
-. __ _ ____
TABLE OF CCNTENTSbSection
_Pa
1 INr ODUCTION AND SUMMARY Volume 1 . . Tab 1 . . . l-. . .
1.1 INTRODUCTION l--
. . . . . . . . . . . . . . . .
1.2 DESIGN HIGHLIGHTS . l-. . . . . . -. . . . . . . .
1.2.1 SITE CV.ARACTERISTICS 1-. . . . . . . . . . . . .
1.2.2 PCWER LEVEL l-. . . . . . . . . . . . . . .
1.2.3 FIJX SPECIFIC PCWER LEVEL l-. . . . . . . . . .
1.2.h REACTOR BUILDING SYSTEM 1--
. . . . . . . . . . . .
1.2.5 ENGINEERED SAFEGUARDS . l-. . . . . . . . . . . .
1.2.6 ELECTRICAL SYSTEMS AND EMERGENCY POWER 1-. . . . . . .
1.2.7 ONCE-THROUGH STEAM GENERATORS 1-. . . . . . . . . .
13 TAEULAR CHARACTERISTICS . 1-. . . . . . . . . . . .
1.4 PRINCIPAL DESIGN CRITERIA l-. . . . . . . . . . . .
1.h.1 CRITERION 1 l-. . . . . . . . . . . . . . .
1.k.2 CRITERION 2 l-. . . . . . . . . . . . . . .
1.h.3 CRITERION 3 1-. . . . . . . . . . . . . . .
1.k.4 CRITERION k 1-. . . . . . . . . . . . . . .
1.h.5 CRITERICN 5 1-. . . . . . . . . . . . . . .
1.h.6 CRITERION 6 1-. . . . . . . . . . . . . . .
1.h.7 CRITERICN 7 1-. . . . . . . . . . . . . . .
1.h.8 CRITERION 8 1-. . . . . . . . . . . . . . .
1.k.9 CRITERION 9 1-. . . . . . . . . . . . . . .
1.h.10 CRITERION 10 1-. . . . . . . . . . . . . . .
1.h.11 CRITERION 11 1-O t ' 12 caltzale= 12 1-. . . . . . . . . . . . . . .
- . . .. - . - . - . . - - . -
1.k.13 CRITERION 13 1- !. . . . . . . . . . . . . . .
1.k.lk CRITERION 14 1-I. . . . . . . . . . . . . . .
1.h.15 CRITERION 15 1-. . . . . . . . . . . . . . .
1.h.16 CRITERION 16 1-. . . . . . . . . . . . . . .
1.h.17 CRITERION 17 1- '. . . . . . . . . . . . . . .
l.k.18 CRITERICN 18 1-. . . . . . . . . . . . . . .
1.4.19 CRITERION 19 1- |. . . . . . . . . . . . . . .
1.h.20 CRITERION 20 1. i. . . . . . . . . . . . . . .
1.h.21 CRITERION 21 1- I. . . . . . . . . . . . . . .
1.h.22 CRITERION 22 1- |. . . . . . . . . . . . . . .
1.h.23 CRITERION 23 1- |. . . . . . . . . . . . . . .
1.h.24 CRITERICN 24 1- i. . . . . . . . . . . . . . .
1.k.25 CRITERICN 25 1-: I. . . . . . . . . . . . . . .
1.h.26 CRITERION 26 1-;. . . . . . . . . . . . . . .
1.4.27 CRITERION 27 1-:. . . . . . . . . . . . . . .
15 RESEARCH AND DEVELOPMENT REC.UIREMENTS 1-;. . . . . . . .
1.5.1 ONCE-THROUGH STEAM GENERATOR TEST . 1-;. . . . . . . .
1.5.2 CorROL ROD DRIVE LINE TEST . 1-;. . . . . . . . . .
1.5 3 SELF-PCWERED DETECTOR TESTS . 1-;. . . . . . . . . .
l.5.4 THERMAL AND HYDRAULIC PROGRAMS . 1-;'
. . . . . . . . .
1.6 IDENTIFICATION OF AGENTS AND CONTRAC"' ORS. 1-;. . . . . . .
[ 1.7 CCNCLUSIONS 1-;. . . . . . . < . . . . . . . . .i al
| 0| 0002 054 i
|
i ii
,_ __ ~-
- ._-
Secticn -
2 SITE AND ENVIRONMENT4 * Tab 2Volume 1 *. . . * .**
2.1 GENERAL DESCRIP"' ION .. . . . . . . . . . . ...
2.2 LOCATION, POPULATION,AND LAND USE . . . . . . ...
2.2.1 LOCATION . . . . . . . . . . . . . . ...
2.2.2 POPULATICN . . . . . . . . . . . . . ...
2.2 3 LAND USE . . . . . . . . . .... . . .
2.3 METEOROLOGY . . . . . . . . . . . . . ...
2.3.1 SUMMARY . . . . . . . . . . . . . ...
2.3.2 SEVERE WEATHER. . , . . . . . . . . . . ....
2 3.3 AVERAGE ATMOSPHERIC DISPERSION . . . . . . . ...
2 3.h ATMOSPHERIC DIF?USION FOR ASSESSING ACCIDENTS . . ....
2.4 HYDROLOGY AND GROUNWATER . . . . . . . . . ...
2.k.1 CHARACTERISTICS OF STREAMS IN VICINITY . . . . ...
2.h.2 OTHER POWER PROJECTS IN VICINITY . . . . . . ...
2.k.3 LOW FLOW STUDIES . . . . . . . . . . . ...
2.h.k FLOOD FLOW STUDIES . . . . . . . . . . . ...
2.k.5 DESIGN OF PROPOSED DAMS AND SPILLWAYS . . . . ...
2.4.6 GROUNDWATER . . . . . . . . . . . . . ....
2.5 GEOLOGY . . . . . . . . . . . . . . ....
2.6 SEISMICITY . . . . . . . . . . . . . . ....
2.6.1 SEISMICITY . . . . . . . . . . . ....
2.6.2 RESPONSE SPECTRA . . . . . . . . . . . ....
2.7 REFERENCES . . . . . . . . . . . . . . ....
3 REACTOR Volume 1 . Tab 3. . . . . . . . . ...
31 DES 1GN uSES . . . . . . . . . . . . . ...
3.1.1 PERFORMANCE OBJECTIVES . . . . . . . . . ...
3.1.2 LIMITS . . . . . . . . . . . . . . ...
32 REACTOR DESIGN . . . . . . . . . . . . . ...
3 2.1 GENER'J. SUMMARY . . . . . . . . . . . . ...
3 2.2 NUCLEAR DESIGN AND EVALUATION . . . . . . . ...
323 THERMAL AND HYDRAULIC DESIGN AND EVALUATION . . ...
3 2.4 MECHANICAL DESIGN LAYOUT . . . . . . . . . ...
33 TESTS AND INSPECTIONS . . . . . . . . . . ...
331 NUCLEAR TESTS AND INSPECTION . . . . . . . ...
332 THERMAL AND HYDRAULIC TESTS AND INSPECTION . . . ..,
3 3.3 JUEL ASSEMBLY, CONTROL ROD ASSEMBLY, AND CONTROL RCDDRIVE MECHANICAL TESTS AND INSPECTION . . . ...
3 3.h INTERNALS TESTS AND INSPECTIONS . . . . . . ...
3.k REFERENCES . . . . . . . . . . . . . ...
h REACTOP COOLANT SYSTEM Volume.1 . Tab.4 .. . . . ....
h.1 DESIGN BASES-
. . . . . . . . . . . . . ....4.1.1 PERFCRMAN6; OBJECTIVES
. . . . . . . . . ...
h.l.2 DESIGN CHARACTERISTICS . . . . . . . . . ...-k.l.3 EXPECTED OPERATING CONDITIONS . . . . . . . ....h.1.k SERVICE LIFE . . . . . . . . . . . . ...O h.l.5 CODES AND CLASS m CATIONSO . . . . . . . . ...-
0002 055.
11
- .
_ _ _ _ .- _ _ _ _ - _ _ _ _ - _ _
Sectien k P~ ^ 'O
~ REACTCR COOLANT SYSTEM (CONTINUED)Volume 1 . Tab.h .h . . .
h.2 SYSTEM DESCRIPTION AND OPERATICN . h. . . . . . . . .
h.2.1 GENERE DESCRIPTION k. . . . . . . . . . . . . ,
k.2.2 MAJOR CCMFONENTS h !. . . . . . . . . . . . . .
k.2 3 PRESSURE-RELIEVING DEVICES h. . . . . . . . . . .
k.2.h ENVIRONMENTE PROTECTION . h. . . . . . . . . . .
4.2.5 MATERIES OF CONSTRUCTION ~ h. . . . . . . . . . .
h.2.6 MAXIMUM HEATING AND COOLING RATES . k |. . . . . . . .
k.2 7 LEAK DETE ZION k. . . . . . . . . . . . . . .
h.3 SYSTEM DESIGN EVALUATION k '. . . . . . . . . . . .
lh.3 1 Sir m uCTORS u. . . . . . . . . . . . . . .
h.3 2 RELIANCE ON INTERCONNECTED SYSTEMS k j. . . . . . . .
h.3.3 SYSTEM INTEGRITY k '
. . . . . . . . . . . . . .
h.3.4 PRESSURE PETm . -. . . h. . . . . . . . . . .
h.3 5 REDUNDANCY h. . . . . . . . . . . . . . . .
4.3.6 SAFETY ANALYSIS h. . . . . . . . . . . . . .
k.3 7 OPERATIONAL LIMITS . k. . . . . . . . . . . . .ih.h TESTS AND INSPECTIONS k l. . . . . . . . . . . . .
h.k.1 CCMPONENT IN-SERVICE INSPECTION '. k. . . . . . . .
4.h.2 REACTOR COOLANT SYSTEM TESTS AND INSPECTIONS k. . . . .
4.h.3 MATERIE IRRADIATION SURVEILLANCE . h. . . . . . . .
k.5 REFERENCES 4 |. . . . . . . . . . . . . . . . .
5 CONTAINMENT SYSTEM Volume 1 . Tab 5 5. . . . . . . .
51 REACTOR BUILDING 5. . . . . . . . . . . . . . .
' 5.1.1 DESIGN BASES 5. . . . . . . . . . . . . . .
5 1.2 STRUCTURE DESIGN 5. . . . . . . . . . . . . .
5.2 ISOLATION SYSTEM 5. . . . . . . . . . . . . . .
5 2.1 DESIGN BASES '
5. . . . . . . . . . . . . . . i
5 2.2 SYSTEM DESIGN 5 !. . . . . . . . . . . . . . .
53 VENTILATION SYSTEM 5. . . . . . . . . . . . . .
531 DESIGN BASES 5. . . . . . . . . . . . . . .
532 SYSTEM DESIGN 5. . . . . . . . . . . . . . .
5.h LEAKAGE MONITORING SYSTEM 5. . . . . . . . . . . .
5.5 SYSTEM DESIGN EVALUATION 5. . . . . . . . . . . .
5.6 TESTS AND INSPECTION . 5. . . . . . . . . . . . .
5.6.1 FREOPERATIONAL TESTING AND INSPECTION 5. . . . . . .
5.6.2 POSTOPERATIONAL LEAK MONITORING 5. . . . . . . . .
6 ENGINEERED SAFEGUARDS Volume 1 . Tab 6 . 6. . . . . . .
6.1 EMERGENCY INJECTION 6. . . . . . . . . . . . . .
6.1.1 DESIGN BASES 6. . . . . . . . . . . . . . .
. s.1.2 DESCRI m 0N e. . . . . . . . . . . . . . . .'
6.1 3 DESIGN EVALUATION 6. . . . . . . . . . . . . .
6.1.4 TESTS AND INSPECTIONS . 6. . . . . . . . . . . .
6.2 REACTOR BUILDING ATM0 SPHERE COOLING AND WASHING 6. . . .
6.2.1 DESIGN BASES . 6. . . . . . . . . . . . . . .
6.2.2 '
DESCRIPTION 6g . . . . . . . . . . . . . . . .
U '
;
I
|.
i
0002 056m
_ _ __ __. . .
,
. _.
Ssetion
6 ENGINEERED SAFEGUARDS (CONTUUED) Volume 1 . . Tab 6. .
6.2.3 Dl: SIGN EVALUATION . . . . . . . . . .....
6.2.4 TESTS AND USPECHONS . . . . . . . . .....
6.3 ENGINEERED SAFEGUARDS LEAKAGE AND RADIATIONCONSIDERATIONS . . . . . . . . . . .....
6.3.1 INTRODUCH ON . . . . . . . . . . .....
6.3.2 SUMMARY OF POSTACCIDENT RECIRCULATION ANDLEAKAGE CCNSIDERATIONS . . . . . . . .....
6.3.3 LEAKAGE ASSUMPTIONS . . . . . . . . .....
6.3.4 DESIGN BASIS LEAKAGE . . . . . . . . .....
6.3.5 LEAKAGE ANALYSIS CONCLUSIONS . . . . . .....
7 INSTRUMENTATION AND CONTROL Volume.2 . . Tab 7. . . . .
7.1 PROTECTION SYSTEMS . .. . . . . . . . .....
7.1.1 DESIGN BASES . . . . . . . . . . .....
7.1.2 SYSTEM DESIGN . . . . . . . . . . .....
7.1 3 SYSTEMS EVALUATION . . . . . . . . . .....
7.2 REGULATING SYSTEMS . . . . . . . . . .....
7.2.1 DESIGN BASES . . . . . . . . . . . .....
7.2.2 SYSTEM DESIGN . . . . . . . . . . .....
7.2.3 SYSTEM EVALUAU CN . . . . . . . . . .....
73 INSTRUMENTATION . . . . . . . . . . .....
7 3.1 NUCLEAR INSTRUMENTAHON . . . . . . . .....
732 NONNUCLEAR PROCESS INSTRUMENTATION . . . .....
O 7 3.3 INCORE MONITORING SYSTEM . . . . . . . .....
7.h OPERATING CONTROL STATIONS . . . . . . . .....
7.h.1 Gu M LAYOUT . . . . . . . . . . .....
7.k.2 INFORMATION DISPLAY AND CONTROL WNCTION . .....
7.k.3 SUMMARY OF ALARMS . . . . . . . . . .....
7.h.h COMMUNICATION . . . . . . . . . . .....
7.4.5 OCCUPANCY . . . . . . . . . . . .....
7.h.6 AUXILIARY CONTROL STAHONS . . . . . . ..... <
7.h.7 SAFETY FEATURES . I. . . . . . . . . .....
8 ELECTRICAL SYSTEMS Volume 2 . . Tab 8. . . . . . . .
8.1 DESIGN BASES .. . . . . . . . . . . .....8.2 ELECTRICAL SYSTEM DESIGN . . . . . . . .....
8.2.1 NETWORK UTERCONNECTIONS . . . . . . . .....8.2.2 STATION DISTRIBUTION SYSTEM . . . . . . .....
8.2 3 EMERGENCY PcwER . . . . . . . . . . .....
8.3 TESTS AND INSPECTICNS . . . . . . . . .....
1.
l
; O
0002 057,
I
1
Section P-
.
9 AUXILIARY AND EMERGENCY SYSTEMS Volume 2 . . Tab 9 9. . .
91 MAKEUP AND PURIFICATICN SYSTEM 9 J. . . . . . . . . .
9 1.1 DESIGN BASES 9'
. . . . . . . . . . . . . . .
I9 1.2 SYSTEM DESCRIPTION AND EVALUATICN . 9. . . . . . . .
92 CHEMICAL ADDITION AND SAMPLING SYSTEM 9. . . . . . . .
9.2.1 DESIGN Bt.SES 9. . . . . . . . . . . . . . . ,
9 2.2 SYSTEM DESCRIPHON AND EVALUATION . 9'
. . . . . . . .
9.3 I7TERMEDIATE COOLING SYSTEM 9. . . . . . . . . . .
9.3.1 DESlGN BASES 9. . . . . . . . . . . . . . .
9.3.2 SYSTEM DESCRIPTION AND EVALUATION . 9. . . . . . . .
9.h SPENT FUEL CCOLING SYSTEM 9. . . . . . . . . . . .
9.h.1 DESIGN BASES 9. . . . . . . . . . . . . . .
9.4.2 SYSTEM DESCRIPTION AND EVALUAUCN . 9. . . . . . . .
9.$ DECAY HEAT REMOVAL SYSTEM 9. . . . . . . . . . . .
9 5.1 DESIGN BASES 9. . . . . . . . . . . . . . .
9.5.2 SYSTEM DESCRIPTION AND EVALUATION . 9. . . . . . . .;
9.6 COOLING WATER SYSTEMS 9. . . . . . . . . . . . .
9.6.1 DESIGN BASES 9. . . . . . . . . . . . . . .
9.6.2 SYSTEM DESCRIPTION AND EVALUATION . 9. . . . . . . .
9.7 FUEL HANJLING SYSTEM . 9. . . . . . . . . . . . .
9 7.1 DESIGN BASES 9. . . . . . . . . . . . . . .
9 7.2 SYSTEM DESCRIPTION AND EVALUATION . 9. . . . . . . .
9.8 STATICN VENU LATION SYSTEMS 9. . . . . . . . . . .
9.8.1 DESIGN BASES 9. . . . . . . . . . . . . . .
9.8.2 SYSTEM DESCRIPTION AND EVALUATION . 9. . . . . . . .
O 10 STEAM AND PCWER CONVEESION SYSTEM Volume 2 . . Tab 10 . 1.
. .
10.1 DESIGN BASES 1. . . . . . . . . . . . . . . .
10.1.1 OPERATING AND PERFORMANCE REQ,UIREMENTS 1. . . . . . .
10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS . 1. . . . . . . .
10.1.3 FUNCTIONAL LIMITATIONS 1. . . . . . . . . . . .
10.1.4 SECONDARY FUNCTIONS 1. . . . . . .
10.2 SYSTEM DESIGN AND OPERATION. . . . . .
1. . . . . . . . . . .
10.2.1 SCHEMATIC FLCW DIAGRAM 1. . . . . . . . . . . .
10.2.2 CODES AND STANDARDS 1. . . . . . . . . . . . .
10.2 3 DESIGN FEATURES 1. . . . . . . . . . . . . .
10.2.h SHIELDING 1. . . . . . . . . . . . . . .
10.2 5 CORROSION PROTECTION 1. . . . . . . . . . . . .
10.2.6 IMPURIHES CONTROL . 1. . . . . . . . . . . . .
10.2.7 RADI0ACH VITY 1. . . . . . . . . . . . . . ..10 3 SYSTEM ANALYSIS 1. . . . . . . . . . . . . . .
10 3 1 TRIPS, AUTCMATIC CCNTROL ACTIONS, AND ALARMS 1. . . . .
10 3.2 TRANSIENT CONDITIONS 1. . . . . . . . . . . . .
10.3.3 MALIUNCTIONS 1. . . . . . . . . . . . . . .
10 3.k OVERPRESSURE PROTECU CN 1. . . . . . . . . . . .
10 3 5 INTERACTIONS 1. . . . . . . . . . . . . . .
10 3.6 OPERATIONAL LIMITS . ... 1. . . . . . . . .
10.h TESTS AND INSPECTIONS 1. . . . . . . . . . . . .
00002 058
,,
- _ _ . _ . __
.
Section_E
11 RADI0 ACTIVE WASTES AND RADIATICNPROTECTION _ - _ _ _ _ _ -
- - . _
Volme 2 . . Tab 11 . 1. . . .. . . . . .
11.1 RADIOACTIVE WASTES 1. . . . . . . . . . . . . .
11.1.1 DESIGN BASES . 1. . . . . . . . . . . . . . .
11.1.2 SYSTEM DESIGN 1. . . . . . . . . . . . . . .
11.1 3 TESTS AND INSPECTICNS . 1. . . . . . . . . . . .
11.2 RADIATION SHIELDING 1. . . . . . . . . . . . . .
11.2.1 PRIMARY, SECCNDARY, REACTOR BUILDING, ANDAUXILIARY SEIELDING 1. . . . . . . . . . . . .
11.2.2 AREA RADIATION MONITORING SYSTEM 1. . . . . . . . .
11.2 3 HEETH PHYSICS 1. . . . . . . . . . . . . . .
11 3 REFERENCES 1. . . . . . .- . . . . . . . . . .
12 CONDUCT OF OPERATIONS Volme 2 . . Tab 12 . 1. . . . . .,
12.1 ORGANIZATICN AND' RESPONSIBILITY 1. . . . . . . . . .
12.1.1 FUNCTIONE DESCRIPTION 1. . . . . . . . . . . .
12.1.2 QUALIFICATIONS 1. . . . . . . . . . . . . .
12.1 3 ORGAN 12ATION DIAGRAM 1. . . . . . . . . . . . .
12.2 TRAINING 1. . . . . . . . . . . . . . . . .
12.2.1 STATICN STAFF 1. . . . . . . . . . . . . . .
12.2.2 REPLACEMENT PERSONNEL . .1. .. . . . . . . . . . .
12.2 3 CN-THE-JOB TRAINING 1. . . . . . . . . . . . .
12.2.4 ENERGENCY DRILLS 1. . . . . . . . . . . . . .
12.3 WRITTEN PROCEDURES 1. . . . . . . . . . . . . .
12.k RECORDS 1O~. . . . . . . . . . . . . . . . . .
12 5 ADMINISTRATIVE CONTROL 1. . . . . . . . . . . . .
.
13 INITIAL TESTS AND OPERATION Volme.2 . . Tab 13 . 1. . . .
13 1 TESTS PRIOR TO REACTOR EUELING 1. . . . . . . . . .
13 2 INITIE CRITICEITY .. 1. . . . . . . . . . .-
13 3 POSTCRITICALITY TESTS 1. . . . . . . . . . . . .
lk SAFETY ANALYSIS ; Vol me 2 . . Tab 14 1. . . . .. ,
lb.1 CCRE AND COOLANT BOUNDARY PROTECTION ANEYSIS 1. . . . .
1h.1.1 ABNCRMALITIES 1. . . . . . . . . . . . . . .
14.1.2 ANALYSIS OF EFFECTS AND CON 3EQUENCES . 1. . . . . . .
lb.2 STANDBY SAFEGUARDS ANALYSIS 1. . . . . . . . . . .
lk.2.1 SITUATIONS ANEYZED AND CAUSES . 1. . . . . . . . .
lb.2.2 ACCIDENT ANEYSES 1. . . . . . . . . . . . . .
lb.3 REFERENCES 1. . . . . . . . . . . . . . . . .
15 TECHNICE SPECIFICATIONS Volme 2 . . Tab 15 1. . . . .
-
O0002 059"
. - -.
TABLE OF APPENDICES.
A;;endix
1A TECHNICAL QUALIFICATICNS . . Volu=e 3 . . . Tab 1A. . . . .
2A ENGINEERING GECLOGY AND FOUNDATIONCONSIDERATIONS . . Volume 3 . . . Tab 2A. . . . . .. ..
23 SEISMOLOGY AND METEOROLOGY , . . Volu=e 3 . . . Tab 23. . .
2C GROUND-WATER HYDROLCGY . . Volu=e 3 . . . Tab 2C. . . . . .
2D GEOLOGY . Volu=e 3 , . . Tab 2D. . . . . . . . . . . . . .
5A STRUCTURAL DESIGN 3ASES. . Volu=e 3 . . . Tab 5A. . .. . .
53 DESIGN PROGRAM FON REAC*CR BUILDING. . Volu=e 3 . . . Tab 5B3C DESIGN CRITERIA FOR REACTOR SUILDING . Volume 3 . . . Tab 5C5D QUALITY CONTROL. . . . . . Volu=e 3 . . . Tab 5D. . . . . .
SE LINER PLATE SPECIFICATION . Volu=e 3 . . . Tab SE. . . . .
5F REACTOR SUILDING INS *RUMENTATION . . Volu=e 3 . . . Tab 5F.
Supole=ent
1. . Volume h . . Supplement No. 1. . . . . . . . . . . . . .. . . .
2. . Volu=e k . . Supplement No. 2. . . . . . . . . . . . . . .. . ./
3 . . . . . . . . . . . . . . . . . . . . Volu=e 5 . . S uppleme nt No . 3s
k . . . . . . . . . . . . . . . . . . . . Volume 5 . . S upplement No . h
5 . . . . . . . . . . . . . . . . . . . . Volu=e 5 . . S upple=e nt No . 5
o,
V
0002 060vii (Revised 6-23-68)
. _ __ -
- . --, - --. - __ _._ - _. _. - - _ _ -- _-- - _ - - - - -
i
:
|@.
.
i
!
i
;
i
!
!,
i
\l
i
:,
\O ;i
, ,
'
i
L
i
4
9
ii!
I@ 0002 0.
.
!1
:J,
w,- ,,---emy.- w y-.,,,-- . - . . , - . -- . , - . - - - - - - - .- - , - - . .-..e.~~.---r- .-. .- , . -, , - - . . ., . . . ._ - .. -- - - - - ., - - . - - - - - - . . - _ _ _ =e -rw---
OC
EKl'
.-
OI
e
,
O - '
0002 062.
i.
-- _ _ _ _ _ _ . - - _ _ - - --
. , . _ _ -____ _ _ _
APPENDIX 1A
TECHNICAL QUALIFICATIONS
1 METROPOLITAN EDISON COMPANY TECHNICAL QUALIFICATIONS
1.1 GENEPE
Metropolitan Edison Capany has 8h years' experience in the operation ofelectric generating stations.
Met-Ed operates four steam electric generating plants with a total of 12units and a total net capability of 8h5,300 kv. Also, one hydroelectricstation with an average capability of 1h,000 kw is operated by Met-Ed.
The ecmpany has a total plant investment of $361,990,000 and employes over2,300 people.
The ccmpany is a subsidiar/ of the General Public Utilities Corporation.
1.2 NUCLEAR PARTICIPATION
Met-Ed is a partner with other GPU subsidiaries in Saxton Nuclear Experimenta:Corporation. This Corporation, fomed in 1959, operates the Saxton Station,a 23,500 kw nuclear steam electric generating station for research, operating.and engineering experience. Many Met-Ed empicyees who will be involvedin the operation of 'Ihree Mile Island Nuclear Station vill have receivedtraining and experience at the Saxton Station.-
2 THE 3ABCCCK & WILCOX COMPANY - TECHNICAL QUALIFICATIONS
2.1 GENERAL
The Babcock & Wilcox Company was founded as a partnership in 1867 and organizeas a corporation in 1881. B&W is a videly diversified empany servingthe electric utility, transportation, steel, petroleum, chemical, pulpand paper, and nachiner/ industries , as well as one of the world's ' leadingsuppliers of specialty steels. B&W is a =ajor supplier of ecmponents forthe nuclear Navy.
The Ccmpany ranks as one of the larger American industrial enterpriseswith corporate total current assets of over $262,000,000 at the end of1966. Orders received in 1966 exceeded $8ho,000,000, and 1966 income before
1
taxes and minority interests was over $62,h00,000. The back1cg at theend of 1966 vas more than $915,500,000. Current orders for nuclear ccuponentssystems, and fuel exceed $300,000,000.
_ _ B&W employs over 30,000 persons in facilities throughout the United States ,Canada, Great Britain, and Sweden. Of this total, over 1,000 are technicaland scientific personnel working in the nuclear power activities.
O '
;
1
L '' ,,i.it lA-1 b
1
!
As the world's largest manufacturer of steam generating equip =ent, B&Wis a reccgnized leader in the American industrial family. The Cc=panyhas contributed materially to the development of fundamental materials '
data, heat transfer data, manufacturing and erection processes , andinspection techniques used in the steam generating equip =ent industry.2.2 DIVISIONS AITD SUBSIDIARIES
The major Divisions and Subsidiaries of the Ccepany located in theUnited States , and their products , include: ,
'
a. Boiler Division
The Boiler Division designs, manufactures, installs, andservices nuclear and conventional steam generating systemsand equipment and heavy pressure. vessel equipment for theutility, petrochemical, and other indnstries. 'Ihe Divisiondesigns and manufactures reactor vessels , steam generators ,and pressurizers for the nuclear Navy, for the USAEC, andfor cer::=ercial nuclear pcuer plants. The Division alsomanufactures reactor cores for cor::=ercial nuclear powerplants.
b. Tubular Preducts Division
The Tubular Products Division is one of the world's leadingsuppliers of specialty steel tubing, extrusions , and fittings.
c. Refractories Division
The Refractories Division mines raw material and manufacturesa ccuplete line of refractory =aterials and high temperatureinsulation for use in the utility, glassmaking, metals manu-facturing, and space industries,
d. Autcmated Machine Division
The Automated Machine Division furnishes the autcmotive andrelated industries with highly automated production machinery.
e. Atomic Enerey Division
The Atomic Energy Division conducts development programs onadvanced nuclear power plant concepts , systems designs , andnuclear fuel management pregrams.
f. Research and Develetment Division
The Research and Development Division conducts research , develop-ment, and testing pregrsms for the other Divisions and Subsidiariesof the Company. Development programs are also conducted undercontract in the areas of heat transfer, metallurgy, nuclear fuelsdevelopnent, critical experiments, and radiochemistry pregrams. gThe Division's test reactor (BAWTR) and hot cell facilities are W
! utill:ed for irrad:.ation testing, isotope production, and irradi-! ation encapsulatien services.
t. L 1 .0002 064-
1A-2-
- _ - _ _ _ _ _ _ - _ _ _ - _ - _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _
.
g. Bailey Meter Cmpany -
kiley Meter Ccmpany designs and =anufactures instruments ,controls , and ccuputers for power generation, industrialprocesses , and naval and =erchant vessels. Bailey alsoproduces a full line of nuclear instrumentation, incoreinstrumentation, safety systems , and process instru=enta-tion for use in nuclear power plants.
h. Diamond Power Specialty Ccrn:any
Diamond Power designs and manufactures boiler cleaningequipment, special gauges , industrial television systems ,stud tensioners, and reactor control red drive mechsuisms.
i. Babcock-Wilcox and Goldie-McCulloch Li=ited
This organization is a =ajor Canadian supplier of steamgenerators , pumps , and process equipment for a varietyof uses in the utility, pulp and paper, and chemical indus-tries. It is also a major Canadian supplier of stesmgenerators for nuclear power plants.
2.3 NUCLEAR EXPERIENCE
B&W's participation in the development of nuclear power dates from theManhattan project. B&W's nuclear activities are broad and includeapplied research to develop fundamental data, design and manufacture
Os of nuclear systems ccmponents , and design and manufacture of ccupletenuclear steam generating systems.
The major activities and accomplishments in the water-cooled and moder-ated reactor field are sunmarized below,
Indian Point No.1 (Censolidated Edison Ccmpany of New York, Inc.)a.
In 1955, B&W contracted for the development, design, and supplyof the nuclear steam supply system, reactor core, and relatedcontrol system for Consolidated Edison's Indian Point No.1Unit. Indian Point No.1 ia a light-water-cooled and moderatedpressurized vater reactor system rated at 585,000 thermalkilowatts. The unit includes a separately fired superheaterwhich heats steam from the reactor system before introductioninto a 275,000 kilowatt electric generator. Indian Point No.1 vent into ectmercial operation in January 1963.
b. NS Savannah (USAEC)
B&W was awarded a contract in 1957 to develop, design, andsupply the entire propulsion plant for the NS Savannah. B&W'sinitial contract scope included, in addition to the design andsupply of equipment and reector core, the responsibility for
O..safety analysis work, supervision of propulsion plant equipmenterection, crew training, and advice in fuel lorsding, testing,
. . . . .
0002 065. , ,
IA-3,8
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
and operation. Through later ancillary contracts , B&W personneldeveloped and directed the propulsion testing, start-up, andinitial operational programs.
B&W has continued to supply services in the areas of crewtraining, upgrading, and operation.
The NS Savannah vent into ecz:mercial operation in May of1962 and has been in continuous service since except for
-
a one-year enforced outage resulting frcm a labor dispute.
The Savannah nuclear steam supply system is a light-water-cooled and moderated pressurized water plant rated at 80,000thermal kilowatts.
c. Advanced Test Reactor (Ebasco/USAEC)
B&W vas retained in 1960 as the nuclear subcontractor toEbasco Services, Inc., for the design of the Advanced TestReactor. B&W's final scope of work included the design of,
the nuclear portion of the reactor ccmplex including thereactor core, critical experiments, control rod drives,reactor vessel internals , and fuel handling tools. Inaddition, B&W was responsible for supervising the researchand developnent pregrs=s including corrosion testing, fuelassembly development and heat transfer testing, and thesupply of the reactor control rod drive system, as well asthe design of inpile test loops. The advunced Test Reactoris a light-vater-cooled and moderated high flux test reactorrated at 250,000 themal kilevatts ,
d. Otto Hahn Power Plant
B&W received in 1960, through its Geman licensee , DeutscheBabcock & Wilcox, a contract to provide technical and designconsultation and assistance on the nuclear steam supply systemand reactor core for the Geman Nu.: lear Ship, " Otto Hahn."Tne reactor is an advanced light-water-cooled and moderatedpressurized water reactor in which the core, stes= generator,primary pumps , and piping are integrated into a singlepressure vessel similar to B&W's Consolidated Nuclear StermGenerator (CNSG). The reactor is rated at 38,000 themalkilevatts.
Oconee Nuclear Station Units 1 and 2 (Duke Power Comagny)| e.
| B&W has a contract to supply two pressurized water nuclearI steam supply systems. Each system is rated at 2,h52 MWt for
a net electrical output of 839 MW. The first unit is scheduledfor service in May 1971 and the second in May 1972. Eachreactor uses chemical shim and control rods for reactivity,
| control and generates steam with a small amount of superheat gin once-through steam generators .
'l . .
I. ' i g [t;ie
".
4. ,
I
f. Jersey Central Power and Light Ccutany ~
B&W will supply one pressurized water nuclear steam supplysystem for instnllation at an undisclosed site. Initialoperation is scheduled for 1973. The unit is rated atapprcximately 600 MWe net and vill be a near-duplicate of-the units being supplied to the Duke Power Ccmpany and theMetropolitan Edison Ccepany.
g. Florida Power Cortoration
B&W vill supply one pressurized water nuclear steam supplysystem for installation at the Crystal River Station (nearTampa, Florida). Initial operation is scheduled for 1972.The unit is rated at approximately 820 MWe (net) and villbe a near-duplicate of the units to be supplied for DukePower Capany, Metropolitan Edison Company, and JerseyCentral Power and Light Ccmpany.
h. Research Reactors
B&W has designed and supplied seven research and test reagtorsranging in size frem 1,000 to 6,000 themal kilowatts.
1. Research and Develotment
B&W's research and developent and study efforts are significant
O and range from developent of basic physics and materials datathrough the developent of ccuplete reactor systems including a~,
substantial effort in advanced converter and breeder reactorsystems. I
12.4 ORGANIZATION
B&W's Boiler Division vill execute the Metropolitan Edison Ccmpany contractwith active participation by the other Divisions and Subsidiaries. )
3 GILBERT ASSOCIATES - TECHNICAL QUALIFICATIONS
!3.1 GENERAL
Gilbert Associates , Inc. , engineers and consultants , was organized in 1906and has its main office at Reading, Pennsylvania. Principal offices are l
,
also located at Philadelphia, Pittsburgh, and New York City. Originallyknown as W. S. Barstov and Ccmpany, the corporate name was changed to E. M.Gilbert Engineering Corporation in 1933; in 19h2, the corporate structure
|vas revised to provide for ccmplete employee ownership and the name becameGilbert Associates, Inc.
O,
pa ; .x 0002-067lA-5. -..
- _ _ _ _ _ _ _ _ . . ._. - - -.
_ . _ _ _
Throughout the past 60 years Gilbert Associates has pregressively grownin size and in scope of activity. The collective experience and capa-bilities of the firm offer ecmplete consulting cnd engineering servicesin both investor-owned utilities and to general industry in such diversefields as : nuclear and conventional power generation; transmission,substation, and distribution systems ; economic engineering and managementconsulting service; steel making and processing; cement and mineralsprocessing; chemical and general industrial facilities ; vater desalinationplants ; institutional and commercial installations ; environ = ental andsolid vaste treat =ent; and water production projects. Projects undertakenhave ranged frca large electric power generating plants and productionfacilities to small industrial boiler plants and allied service facilities.
Since 1942 Gilbert Associates has been made responsible for the design ofover 110 themal generating units both fossil and nuclear power representingmore than 16,000,000 kilowatts of new generating capacity. Gilbert'sexperience includes one of the first reheat units , one of the first oncethrough boiler units , and one of the first supercritical steam pressureunits. Designs range in ratings up to 900,000 kw in stations of variedcomplexities - =ine-mouth, closed cycle cooling tower, base-load, peaking,and others. At present Gilbert has over 8,000,000 kw of generation underdesign.
3.2 NUCLEAR EXPERIENCE
| Since 1950 Gilbert has played an active and i=portant role in the) development of nuclear energy for private utilities , industry, and ggovernmental agencies. Gilbert projects include ccmplete programs
of nuclear power developnent involving analysis of sites , ccepleteevaluations of proposals , contract and fuel program assistance, prep-aration of license applications, ccmplete plant design and procurement.
The following is a chronological su= mary of scme of the significantnuclear projects undertaken by Gilbert:
1955 - Design proposal for South Carolina Electric 3: Gas Companyin negotiation of possible demonstration pressurized waterreactor (later Shippingport) sponsored by U. S. Atomic EnergyCannission.
i 1956 - Study and evaluation of 60 MWe pressurized water reactorI plant for Manila Electric Ccmpany.
1957 - Detailed Design study for a 20 MWe pressurized water reactorplant for overseas application for Amy Reactors Branch ofU. S. Atcmic Energy Ccamission.
1958 - Preliminary specifications , designs and cost estimates , andproposal evaluation for 5 to 10 MWe boiling and pressurisedwater reactors for General Public Utilities Corporation.
Ov . . .. 0002 060
.
lA-6
__ _ _ - - _
1958 - Detailed study of application of water reactors (5 to 70 MWe).O in remote locations for Department of The Air Force.
1959 - Design, and construction management of 20 MWt Saxton ExperimentsPower Reactor plant as subcontractor to Westinghouse for Genera'Public Utilities Corporation.
1960 - Detailed study of nuclear power reliability involving fiveoperating reactors for Department of the Air Force includingthe SM-1 at Fort Belvoir, SL-1 in Idaho, Shippingport, EBWRat Argonne , and the Vallecitos BWR have been reviewed andthe reliability of the ccuponents and systems in each plantevaluated.
1961 - Fallout shelter surveys in eastern Pennsylvania for Departmentof Defense.
1962 - Preliminary design and cost estimate for SPX reactor as partof Supercrities1, Once-through Tube Reactor (SCOTT-R) programfor Westinghouse Electric Corporation.
1963 - For Atcmics International, development of original concept,prelim nary design, and cost estimates for 160 MWt organicreactor to provide power and steam to Packaging Corporationof America mill.
1963 - Engineering and econcmic evaluations for 600 MWe OysterCreek turnkey proposed designs for Jersey Central Powerand Light Ccupany.s
1963 - Develo; ment of a nuclear power reactor containment designconcept for plants in close proximity to large populationcenters.
1963 - DeveloInent of system planning procedures which indicatecapacity addition patterns for most economical powergeneration, broadening applicability of nuclear power.
1963 - Preliminary plant designs and cost estimates for 170 MWeand 260 MWe gas-cooled nuclear pcwer plants for RochesterGas and Electric Corporation.
196h - Preliminary plant designs and cost estimates for a 200 MWesodium cooled nuclear power plant for Rochester Gas andElectric Corporation.
196h - Over-all plant design and engineering for 470 MWe Ginnanuclear power plant, as subcontractor to Vestinghouse,for Rochester Gas and Electric Corporation.
196h - Design for electrical espects of Saxton Superheat Loopexperimental installation for Westinghouse Electric
. Corporation.
m c ..,~
u-T 0002 069
.
1965 - Evaluation of a syste=-vide series of ten sites for a =ajoreastern U. S. utility for =ultiple unit application of large(600 MWe and over) nuclear power plants. The scope includesthemal pollution studies and nuclear siting criteria.
1965 - Develop =ent of a fuel cycle ec=puter program which willestimate fuel cycle ecsts over long term periods andcalculate isotope buildup in the core.
i
1
1965 - Design study and cost evaluation for converting Saxton into| a fast-breeder prototype for Westinghouse Corporation.
1965 - Pioneering the design of containment vessels by empicying[ new concepts of design and construction. The use of pcst-
tensicned concrete combined with hinged joints and pre-stressed rock-anchors leads to an accurate predicticn ofthe lead-carrying capacity of the vessels and consequentlyto minimum construction costs. The aseismic design ofthe containment vessel and of equipment and piping vill bebased upon a dyna =ic analysis of the structure-soils system.
1966 - Plant design and engineering as subcontractor to Westinghousefor the 3ko MWe Mihama plant, Kansai Electric Pcver Company,Japan. Scheduled for completien in July 1970, the plant islocated on Tsuruga Peninsula on the main Japanese Island ofEcnshu. Gilbert vill provide design engineering for all ofthe nuclear steam supply systems and structures.
1966 - Site evaluation specification and evaluation of proposalsleading to the design of large nuclear power plants (500 MWeto 1,000 MWe) for four major eastern utilities: MetropolitanEdisen Co. , Florida Power & Light Co. , Baltimore Gas andElectric Co., and Pa. Power & Light Co.
1966 - Architect-engineer for an 8h0 MWo nuclear unit for theMetropolitan Edison Ceepany. Preliminary studies, overa period of nere than two years, indicated an ecencmicadvantage for a nuclear unit over a fossil fuel unit.During the studies numerous sites were investigated through-cut the area served by the utility. The results of compet-itive bidding produced a unit utilizing a pressurized waterreactor and non-reheat turbine generator. The site finallyselected includes a c1csed cycle cooling tcver arrangement forcendenser circulating water. This arrangement eliminatesthemal stream pollution, and provides a captive veter sourcefor cooling purposes.
1967 - Architect-engineer and censultant to Florida Power Corporationfor an 8ho MWe nuclear unit. Ccmplete evaluatica of threepossible sites was necessary, and a ecmplete program of sub-surface investigatien and procedures was instituted at the
O'
0002 070.m .w1A-8 (7-2f-67)
_ _ _ _ . .___ - -_
i
O selected site. Evaluation of total plant equipment bids re-sulted in a pressurized water reactor with a reheat turbine.
The site involves installation at a plant which will have, two existing ccal fired units en a coastal location.
3.3 ORGANIZATION
The Gilbert Associates organization includes nearly 700 employees witha ecmplete staff of engineers , draftsmen,' and many technical specialists.Included in the total staff are over 300 engineers and technical specialistsand 160 draftsmen. This includes members of management, professionalpersonnel, and incividuals in other specialized fields.
Responsibility for engineering and design of nuclear power plants iscentered in the Utilities Division of the Ccmpany. Every nuclear projectis assigned to a project manager, selected frca a staff of engineershaving an average of about 15 years with Gilbert Associates. Throughthis divisional control, the production function of the project iscarried through to ccepletion.
The engineering disciplines such as nuclear, =echanical, electrical,civil, structural, architectrual, environmental engineering, etc. aregrouped into departments and provide the technical resource to theproject. Each department is managed b,y a chief engineer, who providestechnical and administrative responsibility to the personnel assignedto the various projects.
Additional necessary support to the project is provided from other'
N service departments, including: drafting , estimating , apecifications ,legal, accounting, purchasing, expediting , etc.
3.k SUMMARY
In summary, and in view of the above, it is believed that Gilbert Associates ,Inc. is que.lified and capable of discharging its responsibilities to theproject for which this license application is made.
k TECHNICAL QUALIFICATIONS OF UNITED ENGINEEPS ANDCONSTRUCT 0R'S CONSTRUCTION STAFF,
k.1 GENERAL
United Engineers & Ccnstructors Inc. , with headquarters in Philadelphia,Pa. , was founded and incorporated in 1928 under the laws of the State ofDelaware as a consolidation of four successful engineering sud constructionorganizations. In January 196k Jackson & Moreland, Inc. , a vell knownconsulting engineering fim established in Ecsten, Massachusetts in 1697,was merged and became the Jackson & Moreland Division. There are twowholly evned subsidiary ccmpanies , U. E. & C. (Canada) Ltd., which wasincorporated in 1955, and Jackson & Moreland International, Inc., whichwas incorporated in 1958.
O0002 071 |
v ..gi ; ,nom u_9
.. .-. .. -- .
The present scope of activities includes the design and/or constructionof fcN.11 and nuclear pcver plants , power transmission lines and substations ,researec snd development facilities, laboratories, cc==ercial and industrialbuildings, chemical process plants, hot =etal, rolling, finishing and
.
auxiliary plant facilities for steel and the other metal industries , andheavy industrial plants of other types. Consulting engineering is alsoprovided for facility and site planning, ecencmic studies of steam andpower systems , evaluations and appraisals , depreciation and rate studies ,ccst analyses , continuing property records , studies of tax matters , andthe furnishing of independent engineer's certificates.
General and engineering offices are located in Philadelphia and Boston.A branch engineering office is =aintained in Chicago. There is also acen=ercial office in Chicago and others in New York and Washington.
h.2 CONSTRUCTION
All construction activities are managed frem the Philadelphia office.Mr. R. H. reters is Vice President - Construction, and a = ember of theBoard of Directors. Mr.' Peters is a C.E. graduate of Newark Collegeof Engineering. He joined United Engineers in 19h5
As Vice President - Construction, Mr. Peters is responsible for allconstruction verk and maintains control over perfomance with respectto schedules , costs , purchasing, labor relations , and safety. Reportingto him are ten constructica managers , the chief safety engineer, thedirector of labor relations, and all field management and supervisorypersonnel.
The prestent United Engineers ' Construction Department includes morethan h50 pemanent empicyees , including construction =anagers , super-intendents , resident job engineers , field engineers , craft supervisors ,quality control engineers , accountants , and other required field servicepersonnel. In addition, United Engineers currently employs = ore than3,000 craft labor personnel. A substantial amount of modern constructionequipment is maintained and kept in constant use and the latest con-struction techniques are employed. CPM scheduling is applied to every=ajor project.
United Engineers is currently responsible for approximately $1,500,000,000of construction verk in progress , including more than $1,000,000,000 innuclear and fossil povered generating plants.
4.3 NUCLEAR EXPERIENCE
A listing of specific nuclear construction assignments for which UnitedEngineers & Constructors is new or has been responsible follows:
a. ATCMIC ENERGY CCMMISSION'4ashington , D. C.
Ccnstruction =anagement services for Fast Reactor Test Facilities(FARET) in two phases. Phase 1 included over-all detailed pre-construction planning, CPM scheduling, estimating, coordinating ,
, .g : and construction specification preparation. Phase 2, actual> i''' construction, was cancelled. Phase 1 ce=pleted 1965 g: .-
7
| ON02,
lA-10
. - - _ _ - _ _ _ _ - - - - _ - _ - - _ - _ _ _
_ _
/~ Design and supervision of construction of secondary shieldingsystems for PM-3A reactor at McMurdo Sound. Cmpleted 1962.
b. COMMONWEALTH EDISON COMPANYChicago, Ill.,
Morris , Ill. - Construction manegement services , in associationwith the General Electric Cmpany, for Units 2 and 3 at DresdenNuclear Pcver Plant, each rated 600 MWe. Cmpletion - 1969/1970.
c. CCMMONWEALTH EDISON COMPANYICWA-ILLINOIS GAS & ELECTRIC CCMPAIR
Cordova, Ill. - Construction management services , in associationwith the General Electric Cmpany, for Units 1 and 2 at Quad-
iCities Nuclear Station, each rated 800 MWe. Cmpletion - 1970/1971. )1d. CONSOLIDATED EDISCN CCMPANY OF NEW YOFX |
New York, N..Y. |
{Peekskill, N. Y. - Design and construction services , in association Iwith Westinghouse Electric Corporation, of Indian Point Nuclear i
Unit No. 2, rated 986 MWe. Cmpletion - 1969 l
e. THE DETROIT EDISON COMPANY il
Detroit, Mich. I
p Monroe, Mich. - Construction of the Enrico Fermi sodium cooledi
L/ fast breeder nuclear power plant, rated 100 MWe. (As member ofAtmic Power Developent Associates , Inc. , contributed to thedesign and develop ent of the fast breeder reactor concept.)
lC a pleted - 1961.i
f. PUBLIC SERVICE ELECTRIC AND GAS CCMPANYNewark, N. J.
Burlington, N. J. - Construction of a pressuri::ed water reactornuclear generating unit rated 1,03h MWe. Completion - 1971.
g. (CONFIDENTIAL PROJECT)
Design and construction of a nuclear power unit rated approxi-mate 17 1000 MW. Cmpletion - 1971.
|
O |'
0002 073
| u-u:
| I_ _ __ _ _- _
_ . ,. -- -