HOME HELP O A K R.IDGE N A T I O N A L LABORATORY operated by
UNION CARBIDE CORPORATION NUCLEAR DIVISION for the
U.S. ATOMIC ENERGY COMMISSION
ORNL- TM-
3 i-
m
COPY NO.
n
DATE
W
MSRE DESIGN AND OPERATIONS REPORT
P a r t VI OPERATING SAFETY LIMITS FOR THE MOL,TEN-SALT "
-
REACTOR EXPERIMENT
R . H. G u y m o n
*
i
P. N. H a u b e n r e i c h
NOTICE This document contains information of a preliminary nature and was prepared primarily for internal use o t the Oak Ridge Natianol Laboratory. It i s wbject to revision or correction and therefore does not represent a f i n d report.
-
733 (3rd Revision)
J u l y 25,
1969
- LEGAL NOTICE
T h i s report was prepared os an account of Government sponsored work.
Neither the United h a t e s ,
nor the Commission, nor any person acting on behalf of the Commission:
A.
Makes any worronty or representation. expressed or implied, with respect t o the occtrocy, completeness, or
any
usefulness of the information contained i n t h i s report, or that the use of
information, apparatus,
method,
or
process disclosed
i n t h i s report may not inlringe
privately owned rights; or
B. A s s u m e s any l i a b i l i t i e s w i t h respect t o the
use of, or for damages resulting from the tise of
any information, apparatus, method, or process disclosed i n t h i s report.
As used i n the above, “person acting on beholf of the Commission� includes any employae or contractor of the Commission, or employee of such contractor, t o the extent that such employee
or contractor
of the
Commission,
or employee of such contractor
prepares,
disseminates,
or
provides access to, any information pursuant t o h i s employment or contract w i t h the Commii sion, or h i s employment w i t h such contractor.
*-
MSRE DESIGN A I D OPERATIONS REPORT Part V I OPERATING SAFETY LIMITS FOR THE MOLTEN-SALT REACTOR EXPERlBENT ( T h i r d Revision)
R . R. Guymon
P. N. Haubenreich
This document s e t s f o r t h l i m i t s f o r c e r t a i n parameters d e s c r i b i n g t h e o p e r a t i n g c o n d i t i o n s of t h e Molten-Salt Reactor Experiment.
The i n t e n t
i s t o i n c l u d e a l l t h o s e items d i r e c t l y r e l a t e d t o t h e h e a l t h and safelty
of t h e p u b l i c .
Some iterrs extend t o t h e s a f e t y of t h e o p e r a t o r s and
t h e p r o t e c t i o n of t h e Experiment a g a i n s t a s e v e r e and d i s a b l i n g a c c i d e n t . The s a f e t y l i m i t s s t a l l n o t b e i n t e n t i o n a l l y v i o l a t e d .
If any
s p e c i f i e d parameter goes o u t s i d e a s a f e t y l i m i t , t h e r e a c t o r o p e r a t o r s a r e o b l i g a t e d t o t a k e a c t i o n as s p e c i f i e d h e r e i n .
Any change i n t h e
s a f e t y l i m i t s r e q u i r e s a p p r o v a l of t h e OR?& management and t h e AEC-OIIO Contract Administrator,
Any v i o l a t i o n of a s a f e t y l i m i t s h a l l b e reporti-.rl
n o t l a t e r t h a n t h e i e x t work day t o t h e AEC-ORO. T h i s document supersedes MSRE Design and Operations Report, P a r t V I
-
Operating S a f e t y L i m i t s f'or t h e MSRE, ORNL-TM-733 (2nd R e v i s i o n ) .
1.
F u e l System 1.1 F i l l Rate
- The
r a t e a t which t h e r e a c t o r v e s s e l i s f i l l e d w i t k -
f u e l s a l t s h a l l . n o t exceed 1.0 ft3/min.
If t h i s r a t e i s ex-
ceeded, gas f l o w i n t o t h e d r a i n t a n k s s h a l l b e stopped.
1.2 P r e s s u r e -The
p r e s s u r e of t h e gas i n t h e pump bowl s h a l l n o t
exceed 25 p s i g whenever fuel s a l t i s i n t h e r e a c t o r v e s s e l . If t h i s l i m i t j.s reached, t h e pump bowl s h a l l be vented through
t h e c h a r c o a l beds t o t h e s t a c k .
4
1 . 3 Surge Volume - The t o t a l gas volume i n t h e fuel-pump bowl and t h e overflow t a n k s h a l l be a t l e a s t 5.0 f t 3 whenever t h e r e a c t o r is critical.
If t h i s l i m i t i s reached, t h e r e a c t o r s h a l l be
t a k e n s u b c r i t i c a l u n t i l t h e v o l u m e t r i c i n v e n t o r y of f u e l i s reduced.
1 . 4 Excess R e a c t i v i t y - T h e
r e a c t i v i t y s h a l l be such t h a t t h e con-
t r o l rods must b e withdrawn a t l e a s t 50 p e r c e n t o f t h e i r t o t a l worth t o make t h e r e a c t o r c r i t i c a l a t 1210째F.
IF t h i s l i m i t i s
reached, t h e r e a c t o r s h a l l b e h e l d s u b c r i t i c a l u ' i t i l t h e abnormality i s c o r r e c t e d .
1.5
Power - T h e
r e a c t o r s h a l l n o t b e o p e r a t e d a t a s t e a d y power i n
excess of 8 Mw.
If h e a t b a l a n c e s i n d i c a t e n u c l e a r power above
8.1 Mw for more t h a n 1 hour, t h e heat-removal r a t e s h a l l b e r e duced t o a h e a t - b a l a n c e power of 8.0 Mw o r l e s s . * 1.6 Addition of F i s s i l e M a t e r i a l - No more t h a n 120 g o f f i s s i l e m a t e r i a l s h a l l b e added t o t h e f u e l i n t h e pump bowl i n any single addition.
1.7 R e a c t i v i t y Anomaly - T h e
r e a c t i v i t y anomaly s h a l l n o t exceed
O.s$ 6k/k w h i l e t h e r e a c t o r i s c r i t i c a l .
" R e a c t i v i t y anomaly"
i s d e f i n e d as t h e d i f f e r e n c e between t h e observed r e a c t i v i t y and
t h e r e a c t i v i t y p r e d i c t e d on t h e basis of measured r e a c t o r p h y s i c s c h a r a c t e r i s t i c s and c a l c u l a t e d e f f e c t s o f changes i n o p e r a t i n g c o n d i t i o n s , burnup and f i s s i o n p r o d u c t accumulation.
If t h i s
l i m i t i s reached, t h e r e a c t o r s h a l l b e t a k e n s u b c r i t i c a l .
*
1.8 System T e s t a t E l e v a t e d P r e s s u r e - T h e
f u e l c i r c u l a t i n g system
end f u e l d r a i n - t a n k system s h a l l b e p r e s s u r e - t e s t e d a t l e a s t
once
c?
y e a r a t a minimum p r e s s u r e (measured i n g a s ) of 45 p s i g ,
a minimum temperature of l150째F, and f l u s h s a l t b e i n g c i r c u l a t e d by t h e f u e l pump.
1.9 Corrosion
- The
chromium c o n c e n t r a t i o n i n t h e f u e l s a l t s h a l l
n o t exceed 1000 ppm.
If t h i s l i m i t i s reached, s t e p s s h a l l b e
t a k e n t o minimize t h e c o r r o s i o n r a t e and t o reduce t h e chromium c o n c e n t r a t i o n i n t h e f u e l t o l e s s t h a n 500 ppm.
*T h i s
l i m i t w i l l n o t b e reached by any spontaneous change of a proc e s s v a r i a b l e , s o no o p e r a t o r response i s s p e c i f i e d .
Y
5 2,
C o n t r o l Rods and S a f e t y System 2.1
*
Scram C i r c u i t Tests -- A l l scram c i r c u i t s s h a l l b e shown t o be o p e r a t i n g p r o p e r l y by t e s t i n g b e f o r e each f i l l of t h e r e a c t o r vessel w i t h f u e l salt.
2.2
*
Scram Tests - T h e
scram t i m e f o r each c o n t r o l r o d s h a l l b e
measured b e f o r e each f i l l o f t h e r e a c t o r v e s s e l w i t h f u e l s a l t .
2.3
*
Scram T i m e - T h e
r e a c t o r s h a l l not be taken c r i t i c a l if the
scram time of any c o n t r o l rod i s g r e a t e r t h a n 1 . 3 s e c . 2.4
Rod Speed - T h e
r e a c t o r s h a l l n o t be taken c r i t i c a l if t h e
motor-driven speed of any c o n t r o l r o d i s l e s s t h a n 0.45 i n . / s e c
o r more t h a n 0.55 i n . / s e c .
If a r o d w i l l n o t move, t h e r e a c t o r
s h a l l be taken s u b c r i t i c a l .
2.5
C o n t r o l Rod C o o l i n g
- Any
c o n t r o l rod t h a t i s n o t f u l l y w i t h -
drawn s h a l l b e s u p p l i e d w i t h c o o l i n g a i r whenever t h e r e a c t o r i s o p e r a t i n g a t powers above l'j kw.
Temperatures i n t h e rod
d r i v e whose c o o l i n g a i r supply i s connected t o t h a t f o r t h e rod s h a l l b e a c c e p t e d as evidence of a i r f l o w through t h e r o d . 2.6
I n s t r u m e n t S h a f t Water
- The
n u c l e a r i n s t r u m e n t s h a f t s h a l l be
f i l l e d w i t h water whenever f u e l s a l t i s i n t h e r e a c t o r v e s s e l . If f o r any r e a s o n t h e water l e v e l cannot b e maintained a t
849-ft e l e v a t i o n o r above, t h e f u e l s h a l l b e d r a i n e d . 2.7
Nuclear S t a r t u p I n s t r u m e n t a t i o n
- One
n e u t r o n c o u n t - r a t e channel
s h a l l b e i n s e r v i c e throughout t h e f i l l i n g of t h e f u e l loop w i t h
f u e l s a l t and whenever t h e r e a c t o r i s b e i n g t a k e n c r i t i c a l .
If
a n i n s t r u m e n t f a i l u r e o c c u r s d u r i n g f i l l i n g , t h e f u e l s h a l l be returned t o t h e d r a i n tank. 2.8
**- A
Flux I n s t r u m e n t a t i o n
minimum of two f l u x s a f e t y channels
s h a l l be i n s e r v i c e during nuclear operation.
*T h i s
l i m i t w i l l n o t be reached by any spontaneous change of a proc e s s v a r i a b l e , s o no o p e r a t o r response i s s p e c i f i e d . 3c)c
A f u e l f i l l s h a l l n o t b e s t a r t e d i f "chis l i m i t i s n o t m e t . If t h e l i m i t i s v i o l a t e d a f t e r f u e l i s i n t h e core, t h e r e a c t o r s h a l l b e t a k e n
s u b c r i t i c a l immediately by f u l l i n s e r t i o n of a l l c o n t r o l r o d s and s h a l l n o t b e t a k e n c r i t i c a l u n t i l t h e requirements a r e met.
2.9
Period Instrumentation
t
.3c.x
- A
r
minimum of two p e r i o d s a f e t y
channels s h a l l b e i n s e r v i c e d u r i n g n u c l e a r o p e r a t i o n .
2.10 F u e l Temperature I n s t r u m e n t a t i o n
*- A
minimum of two r e a c t o r -
f u e l - o u t l e t temperature s a f e t y channels s h a l l b e i n s e r v i c e during nuclear operation.
2.11 Flux T r i p P o i n t
*- The
r e a c t o r power which w i l l cause a s a f e t y -
r o d scram t r i p s h a l l b e 1 2 Mwt o r less d u r i n g n u c l e a r o p e r a t i o n .
2.12 Flux T r i p P o i n t , F u e l Pump Off*-
The i n d i c a t e d r e a c t o r power
which w i l l cause a s a f e t y r o d scram t r i p s h a l l be 12 kwt or l e s s d u r i n g n u c l e a r o p e r a t i o n when t h e f u e l pump i s n o t o p e r a t i n g . .
2.13 P e r i o d T r i p P o i n t
*- T h e
shortest positive reactor period t h a t
w i l l b e t o l e r a t e d w i t h o u t c a u s i n g a s a f e t y rod scram t r i p s h a l l
b e no s h o r t e r t h a n one second d u r i n g n u c l e a r o p e r a t i o n .
2.14
F u e l Temperature T r i p P o i n t
*- The
r e a c t o r o u t l e t temperature
which w i l l cause a s a f e t y r o d scram t r i p s h a l l be 1300째F o r l e s s during nuclear operation.
3.
Coolant System
3.1
System T e s t a t E l e v a t e d P r e s s u r e
*- The
coolant circulating
system and c o o l a n t d r a i n - t a n k system s h a l l be p r e s s u r e - t e s t e d a t l e a s t once a y e a r a t a minimum p r e s s u r e (measured i n g a s ) of
45 p s i g , a minimum temperature of l150째F and c o o l a n t s a l t b e i n g c i r c u l a t e d by t h e c o o l a n t pump.
4.
Containment
4.1
*
C e l l S h i e l d Blocks - A l l
r e a c t o r c e l l and d r a i n - t a n k c e l l
s h i e l d b l o c k s shall b e i n p l a c e and s e c u r e d by hold-down d e v i c e s whenever f u e l s a l t i s i n t h e r e a c t o r v e s s e l .
4.2
C e l l Oxygen C o n c e n t r a t i o n - T h e
r e a c t o r c e l l and d r a i n - t a n k
c e l l s h a l l c o n t a i n a n i t r o g e n - a i r mixture having a n oxygen conc e n t r a t i o n below 5 p e r c e n t whenever f u e l s a l t i s i n t h e r e a c t o r
*A
f u e l f i l l s h a l l n o t be s t a r t e d i f t h i s l i m i t i s n o t m e t . If t h e l i m i t is v i o l a t e d a f t e r f u e l is i n t h e core, t h e r e a c t o r shall be taken s u b c r i t i c a l immediately by f u l l i n s e r t i o n of a l l c o n t r o l r o d s and s h a l l n o t b e t a k e n c r i t i c a l u n t i l t h e requirements are met.
*T h i s
l i m i t w i l l n o t b e reached by any spontaneous change of a p r o c e s s v a r i a b l e , s o no o p e r a t o r response i s s p e c i f i e d .
W
7 4.2
(continued) vessel.
If t h i s l i m i t i s reached, t h e n i t r o g e n purge i n t o t h e
c e l l s h a l l b e i n c r e a s e d t o b r i n g the oxygen c o n c e n t r a t i o n below
5 p e r c e n t as q u i c k l y as i s p r a c t i c a l . 4.3
C e l l Pressure
--
The p r e s s u r e i n t h e r e a c t o r c e l l and d r a i n - t a n k
c e l l s h a l l b e maintained between -1 p s i g and
-4 p s i g whenever
If e i t h e r l i m i t i s reached
f u e l s a l t i s i n the r e a c t o r v e s s e l .
and t h e p r e s s u r e cannot b e brought back i n t o l i m i t s w i t h i n one hour, t h e f u e l s h a l l b e d r a i n e d ,
4.4
C e l l Temperature -
- The
average t e m p e r a t u r e of t h e atmosphere
i n t h e r e a c t o r c e l l and d r a i n - t a n k c e l l s h a l l n o t exceed 350째F. If t h i s l i m i t i s reached t h e f u e l s h a l l be d r a i n e d .
4.5
C e l l Leak Rate During Operation
- The l e a k r a t e of
air into
t h e r e a c t o r ane d r a i n - t a n k c e l l s s h a l l be determined once p e r week d u r i n g r e a , c t o r o p e r a t i o n .
It s h a l l n o t exceed 70 s c f d a t
t h e normal o p e r a t i n g p r e s s u r e o f -2 p s i g and t e m p e r a t u r e of 130째F.
If a measurement i n d i c a t e s a leak r a t e i n e x c e s s of t h i s
l i m i t , t h e leak.-rate data s h a l l be analyzed w i t h o u t d e l a y and i f t h e a n a l y s i s does n o t i n d i c a t e t h a t t h e r a t e i s a c t u a l l y
w i t h i n l i m i t s , t h e f u e l s h a l l be d r a i n e d .
4.6
*
C e l l Leak T e s t a t E l e v a t e d P r e s s u r e - T h e
r e a c t o r and d r a i n - t a n k
c e l l s s h a l l b e l e a k - t e s t e d a t l e a s t once p e r y e a r a t a minimum p r e s s u r e of 20 p s i g .
The l e a k r a t e a t t h i s p r e s s u r e s h a l l n o t
exceed 280 s c f d .
4.7
Reactor C e l l Annulus Water
- The
water l e v e l i n t h e r e a c t o r
c e l l annulus s h a l l b e maintained above e l e v a t i o n 844 f t
- 9
in.
If t h i s l i m i t i s reached, s t e p s s h a l l be t a k e n w i t h o u t d e l a y
t o r a i s e t h e water l e v e l . attained within
*T h i s
If t h e s p e c i f i e d l e v e l cannot be
4 hours, t h e r e a c t o r s h a l l be t a k e n s u b c r i t i c a l .
l i m i t w i l l n o t be reached by any spontaneous change of a p r o c e s s v a r i a b l e , s o no o p e r a t o r r e s p o n s e i s s p e c i f i e d . V
a 4.8
Vapor-Condensing System P r e s s u r e
- The
maximum vapor-condensing
system p r e s s u r e s h a l l n o t exceed 3 p s i g whenever f u e l s a l t i s i n the reactor vessel.
If t h i s l i m i t i s reached and t h e p r e s s u r e
cannot b e brought below 3 p s i g i n one hour, t h e f u e l s h a l l be drained. Vapor-Condensing System Water Volume - T h e
4.9
volume of water i n
t h e vapor-condensing t a n k s h a l l be between 8000 g a l l o n s and 9300 g a l l o n s whenever f u e l s a l t i s i n t h e r e a c t o r v e s s e l .
If
t h e volume of water cannot be h e l d i n t h a t range, t h e f u e l s h a l l be drained.
4.10
Vapor-Condensing System T e s t a t E l e v a t e d P r e s s u r e
*- The
vapor-
condensing system s h a l l b e p r e s s u r e - t e s t e d a t l e a s t once p e r y e a r a t a minimum p r e s s u r e of 20 p s i g .
4.11
V e n t i l a t i o n F i l t e r s Test
*- The
high-efficiency p a r t i c u l a t e
f i l t e r s ("absolute" f i l t e r s ) a t t h e s t a c k s h a l l be t e s t e d i n p l a c e a t l e a s t once a y e a r and a f t e r each change of f i l t e r e l e F i l t e r s i n s e r v i c e s h a l l have a n e f f i c i e n c y of 99.9% o r
ments.
g r e a t e r f o r 0.3-micron d i o c t y l p h t h a l a t e p a r t i c l e s . 4.12
V e n t i l a t i o n Through Open C e l l -When
openings a r e made i n t o t h e
r e a c t o r c e l l o r d r a i n - t a n k c e l l , a flow o f a i r s h a l l b e maint a i n e d through each opening from t h e o p e r a t i n g area i n t o t h e cell.
If a n e t inward f l o w cannot be maintained, t h e opening
s h a l l b e c l o s e d o r b e reduced i n s i z e t o meet t h e requirement.
4.13
F u e l System Gas Supply P r e s s u r e
- The
p r e s s u r e i n t h e header
s u p p l y i n g cover gas t o t h e f u e l system s h a l l n o t b e l e s s t h a n 28 p s i g .
If t h i s l i m i t i s reached, a p p r o p r i a t e b l o c k v a l v e s
s h a l l b e c l o s e d immediately t o g u a r a n t e e containment.
4.14
Leak D e t e c t o r Header P r e s s u r e - T h e
pressure i n leak detector
headers connected t o f l a n g e s i n t h e f u e l and f u e l o f f g a s systems s h a l l b e a t l e a s t 10 p s i above t h e p r e s s u r e i n s i d e any of t h e connected f l a n g e s whenever fuel, s a l t i s i n t h e r e a c t o r v e s s e l . If t h i s l i m i t i s reached, a p p r o p r i a t e b l o c k v a l v e s s h a l l be
c l o s e d immediately t o g u a r a n t e e containment.
*T h i s
l i m i t w i l l n o t b e reached by any spontaneous change of a p r o c e s s v a r i a b l e , so no o p e r a t o r response i s s p e c i f i e d .
9 U
4.15
Block Valve and Check Valve Test
*- All
b l o c k v a l v e s and check
v a l v e s t h a t a r e p a r t of t h e primary containment of the f u e l cover gas and f u e l o f f g a s s h a l l b e l e a k - t e s t e d a t l e a s t once a year.
4.16
Thermal S h i e l d Water Flow - A
c o o l i n g water flow of a t l e a s t
1 5 gpm s h a l l b e maintained through t h e thermal s h i e l d whenever the reactor is crikical.
If t h e flow drops below t h i s l i m i t
w h i l e t h e r e a c t o r i s c r i t i c a l and cannot be r e s t o r e d w i t h i n one hour, t h e r e a c t o r s h a l l b e t a k e n s u b c r i t i c a l .
5.
Radiation
5.1
B u i l d i n g Radia-bion Monitors - A
minimum of two r a d i a t i o n
monitors s h a l l b e i n o p e r a t i o n a t a l l times, one i n t h e high-bay a r e a and one i n t h e o f f i c e
- control-room
area.
If a f a i l u r e
should occur, s t e p s s h a l l b e t a k e n w i t h o u t d e l a y t o r e s t o r e t h e system.
U n t i l t h e normal system i s a g a i n operable, e q u i v a l e n t
p r o t e c t i o n s h a l l b e provided by u s e of p o r t a b l e i n s t r u m e n t s and s p e c i a l procedures.
5.2
B u i l d i n g A i r Monitors - A
minimum of two a i r a c t i v i t y monitors
s h a l l be i n o p e r a t i o n a t a l l times, one i n t h e high-bay area
and one i n t h e o f f i c e
- control-room
area.
If equipment f a i l u r e
should occur, s t e p s s h a l l b e t a k e n w i t h o u t d e l a y t o r e s t o r e t h e sys tem.
5.3
S t a c k Release of R a d i o a c t i v i t y - T h e
r a t e of r e l e a s e of r a d i o -
a c t i v e m a t e r i a l s from t h e v e n t i l a t i o n s t a c k , averaged o v e r any 12-month p e r i o d , s h a l l n o t exceed 0.62 p / s e c of i o d i n e ,
79 mc/sec of noble gases, and 36 pc/sec of o t h e r mixed f i s s i o n products.
If t ' n i s l i m i t i s reached, o p e r a t i o n s s h a l l b e r e -
s t r i c t e d t o minimize f u r t h e r r e l e a s e s ,
5.4
S t a c k Monitors --A
system c a p a b l e of m o n i t o r i n g release of
i o d i n e , particu:Late p
-y
emitters, and p a r t i c u l a t e
a emitters
s h a l l b e i n s e r v i c e on t h e v e n t i l a t i o n s t a c k s a t a l l times.
If
equipment f a i l u r e should occur, s t e p s s h a l l b e t a k e n t o minimize t h e p o s s i b i l i t i e s f o r u n d e t e c t e d release and t o restore t h e s y s -
t e m as soon as p o s s i b l e .
*This
l i m i t w i l l n o t b e reached by any spontaneous change of a p r o c e s s v a r i a b l e , so no o p e r a t o r response i s s p e c i f i e d .
10
6.
S t a f f and Procedures
*
6.1 Minimum S t a f f -Whenever
f u e l s a l t is i n the reactor vessel,
t h e minimum staff s h a l l c o n s i s t of one S u p e r v i s o r o r Chief o p e r a t o r and two t e c h n i c i a n s .
6.2
*
C o n t r o l Room -Whenever
f u e l salt is i n the reactor vessel,
t h e main c o n t r o l room s h a l l b e a t t e n d e d by a c e r t i f i e d Superv i s o r , a c e r t i f i e d Chief Operator o r a c e r t i f i e d O p e r a t o r ,
6.3
*
R e a c t i v i t y C o n t r o l s -Whenever
f u e l salt is i n the reactor
v e s s e l , m a n i p u l a t i o n of t h e c o n t r o l r o d s o r r e a c t o r power cont r o l s s h a l l be done o r d i r e c t l y s u p e r v i s e d by q u a l i f i e d p e r s o n n e l c e r t i f i e d by t h e D i r e c t o r of t h e Reactor D i v i s i o n , ORNL .
6.4
Procedures
*- The
r e a c t o r s h a l l be o p e r a t e d i n conformance
w i t h c u r r e n t MSRE Operating Procedures and t e s t procedures and
i n s t r u c t i o n s approved as s p e c i f i e d i n t h e O p e r a t i n g Procedures. I n no c a s e s h a l l t h e s e a u t h o r i z e exceeding t h e s a f e t y l i m i t s applicable a t the existing reactor conditions.
*T h i s
l i m i t w i l l n o t b e reached by any spontaneous change of a p r o c e s s v a r i a b l e , s o no o p e r a t o r response i s s p e c i f i e d .
11
ORNL-TM-733 Revision 3 Internal Distribution
35. 36. 37. 38. 39. 40. 41. 42. 43. 44. 45. 46. 47. 48. 49-50. 51.
1. R. G . Affel
2. J. L. Anderson
3. 4. 5. 6. 7. 8. 9. 10. 11.
12. 13.
14. 15. 16. 1.7. 18. 1.9. 20. 21.
22. 23.
24. 25. 26. 27. 28-32. 33.
A. H o u t z e e l
T. L. Hudson
64-65. 66-67. 68-70. 71.
72-86. 87-96. 97-98. 99.
M. R. H. R. H.
C e n t r a l Research L i b r a r y (CRL) Y - 1 2 Document Reference S e c t i o n (DRS) Laboratory Records Department (LRD) Laboratory Records Department Record Copy (LRD-RC)
-
E:t e r n a l
V
A . I. Krakoviak Lundin N. w o n G. MacPherson E. MacPherson E. McCoy H. C . McCurdy L. E. McNeese A. J. M i l l e r R. L. Moore E . L. Nicholson A. M. P e r r y M. Richardson M. W. Rosenthal A. W. S a v o l a i n e n 52. D. S c o t t 53. M. J . S k i n n e r 54. I. Spiewak 55. R. C . S t e f f y 56. D. A. Sundberg 57. R . E. Thoma 58. D. B. Trauger 59. A. M. Weinberg 60. J. R. Weir 61. M. E . Whatley 62. J . C . White 63. Gale Young
C . F. Baes E . S. B e t t i s S. E. Beall 'E. S. B e t t i s R . Blumberg E. G. Bohlmann C . J . Borkowski R . B. Briggs F. R. Bruce W. B. C o t t r e l l J . A. Cox J. L. Crowley F. L. C u l l e r S . J. D i t t o W. P. E a t h e r l y 5. R. Engel D. E . Ferguson L. M. F e r r i s J . K. Franzreb A. P. F r a a s C . H. Gabbard W. R. G r i m e s A. G. G r i n d e l l R. H. Guymon P. H. Harley P. N. Haubenreich
34.
P . R . Kasten
Distribution
D i v i s i o n of T e c h n i c a l Information E x t e n s i o n (DTIE) H. M. Roth, D i v i s i o n of Research and Development, AEC, OR0 T. W. McIntosh, Div. of Reactor Development & Technology, U. S . Atomic Energy Commission, Washington, D. C. 20242 Milton Shaw, Dii-ector, D i v i s i o n of R e a c t o r Development and Technology, U. S . Atomic Energy Commission, Washington, D. C ,
20545