ML19257B537
| ML19257B537 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/02/1979 |
| From: | Bender M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| Shared Package | |
| ML19257B536 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001160813 | |
| Download: ML19257B537 (3) | |
Text
&C L f.Qi:.
=
-** ? *'*.
.~.- -
~-"--.
~~5
~
UNITED STATES i'
NUCLEAR REGULATORY COMMISSION 3a 1",,)
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
"-~
,,,,:/
WASmNGTON, D.C. 20555
.Z..
. r-G May 2,1979 2h
_5..
=m -
=-d.;_~".
E&.
Yhh Dr. Joseph M. Hendrie P"
Chairman W
" ~ '
~
- ZZ U. S. Nuclear Regulatory Commission E
r-e
.~
=JJ:.
}El Washington, DC 20555 s,.,g It has become fash,ionable nowadays for every
- ...... = +,
.....--.= =
Dear Joe:
' " = " -
~ " ~ ~ ' '
+.i z-.-
==
y.3
~
self-appointed expert to express his opinion se
-r
. z;
- .m;
.=
x=
r_
about what should be done to avoid an iteration
=-
' W--
of Three Mile Isiand.
I am sure the ACRS will
?".
~
=
make its collective views known to you in due 3;
""is time.
I wanted to make some points informally 33._
~ ~ ~ ~
that might be lost in the maze of paper you K
are receiving.
Y* 'i' The first is that the development of a usable and readily accessible set of information to E=
the control room operator is something that
+=
"===
can done without significant capital in ent and could improve the safety pos-e.-.
u nuclear power plants very quickly.
4-r Z.
--r-
~he things I have in mind are:
7_ g
- -. e-Good one-line diagrams, possibly in iso-C~T metric form, that physically identify the G;T
""e relative location of important pieces of E-~
hardware.
~
" ~ ~ ~ ~ ~
/7 -- To ED0 for signature of the Chairman.
Date due Comat: :May::.16'.':. :. Distr.ibution:Mr.
79-1307.
Z-~
.. u
- ? _*-
T e -:.
~_
=
z-w
=.
O 4gS0i b
hUCLE AR REbdLATORY COM*.*lSSION
"~
. 3..r C.~ " I AOVtSORY CO*.*.uTTE E O*. REI CTOR S rEGUARDS
. N,,,* '
n'.*As W.GTON. O.C. 205SS i
J Hendrie 2
May 3, 1979
"~"
^= -
~~"
Z 2.
Simple checklists of the sort provided with
- ~ =
automobile owner's manuals to help in troubleshooting problems of an unusual
-r-e ""
nature.
u-;
ua H"4 3.
A good technical data book that has infor-F mation like the solubility of hydrogen in m;
water; the vapor-liquid-equilibrium data for the reactor coolant; radiolytic dis-sociation rates for water as a function z-of temperature, partial pressure of
~~" '
-m 7=" -
hydrogen, and radiation field intensity-
= = -
radiation stability of sealants, gaskets, valve seats comonly used within con-
~
f tainment; diagrams of important valves which include their operating capacities;
- .:.i characteristic curves for coolant circu-
-"E.
"="
lating pumps, feedwater pumps, and
=="
reactor heat removal pumps; precaution-
.7 suggestions for offnermal use of m-ary'nt equipment; sampling procedures to
~
~
=-
pla
.x.
used during accidents; and a list of
==
chnical experts who are on call to 2
1p the reactor operator.
~
i--
I think that is enough of a tabulation to suggest
.that needs to be developed, but it is not a com-
- p -
-lete list.
If that information were available f-e on some type of visual display system of
=;_ -
uitable reliability or just in an operator's library, we would not have to be so concerned gf
=.
1917 139 E
A~~
n ~ ??.~:
===-
"*~C
- T s
G-
. -.. _ __._.7,.
UNITED STATES
~
- j. g"!F,
'4 NUCLEAR REGULATORY COMMISSION
.. ", i AovaSORY COMMITTEE ON RE.*.CTOR SAFEOUARDS g,=,,,,.~
wAssincTOn o.c.20sss
..em.
9.Hendrie
+. =...
3 May 3, 1979
= - -
about the operator's diagnostic capability.
f~"
~
The second point is that operators need a
++
better understanding of thermodynamic response 1-by these systems through some other means than observing the actions on simulators.
The
"~"
't
- = -
most obvious need is to make sure that every operator understands the relationship between
..g pressure, temperature, and phase equilibria, i...
but they also should understand heat transfer 2r characteristics as a function of velocity, fluid state, and, physical configuration of heat transfer surfaces.
Again, these are
?
illustrative and they need some considered
"-~
thought by specialists in operator training.
~
. ' I:s.;..
Finally, it is difficult for me, as cn g
individual, to understand where the NRC
.. _.. =
Staff, the Licensees, the architect-engineering firms, and the nuclear steam supply vendors
~
sr oncentrating their attention.
I think i
ld be useful to everyone if there were lete set of tasks identified so that one a
cou d see what the Industry, the Regulators x-
"- e and their Advisors are trying to accomplish.
To me, it looks like the activities are
' l.
3roceeding helter-skelter without much rhyme
~
r reason by Licensees, EPRI, EEI, NRC and aybe 00E.
e
(
..1.
.=
"3/mh M. Bender
~~
1917 140 E-T u.eee se
- ..~.._
TL
-ee..e.e=
s g
"[" [
. = = -
_ _. _..