ML19220C647
| ML19220C647 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/13/1979 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 7905110381 | |
| Download: ML19220C647 (4) | |
Text
0 a eks Y l
,3 - : n2
.g APR 131979 ACTIONS RELATING TO THREE MILE ISLAND Division of Reactor Safety Research OFFICE CONTACT PERSON DESCRIPTIVE TITLE EST. COMPLETION DATE RES Murley, RSR Hydrogen uptake and dissolution in Reactor Systems 1st Report, 4/12/79 Tests-Billings, Provo, Utah Ongoing RES Lanning, RSR THI Mockup and Small Break Tests - Semiscale INEL Ongoing for few weeks Olson, EG&G First test 4/18/79 RES Murley, RSR Studying possibility of accelerating LOFT small Plans, May 1979 McPherson, RSR break tests Tests Fall 1979 w
RES Tong, RSR Imputing THI-2 characteristics into TRAC at LASL Estimate in progress cc Fabic, RSR and calculate the 3/28/79 transient More than a month 6
N RES Tong, RSR Inputing THI-2 fuel parameters into COBRA and Not Available N
Fabic, RSR calculate fuel damage due to 3/28/79 accident RES Fabic, RSR Provi interpretation and understanding of 4/14/79 Zuber, RSR AP r.
aut in THI-2 Control Room during a stuck e
Anderson, RSR reliet valve incident s
RES Fabic, RSR Provide backup review of NRR and B&W natural 4/13/79 Zuber, RSR circulation cooling calculation C
Anderson, RSR O3 RES Fabic, RSR Calculate compressibity of steam /noncondensable 4/20/79 Zeber, RSL gas mixtures Anderson, RSR RES Bennett, RSR Determine the status of THI core using neutron noise M/20/79 measurements; ORNL i
f
I-ACTIONS RELATING TO TilREE MILE ISLAND (Cont'd)
Division of Reactor Safety Research 0FFICE CONTACT PERSON DESCRIPTIVE TITLE EST. COMPLETION DATE RES Stolzenberg, RSR List of Relief Valve Testing Facilities 4/16/79 RES Johnston, RSR Fuel and Control Rod Guide Analysis at INEL Ongoing Ybar:.sdo, EG&G Independant group of experts studying ability to Not Available RES Jc t
cool TMI core using R.H.R., natural circulation Probably 4/13/79 or other technique RES Marino, RSR Assessment of Core Damage 4/13/79 RES Hoatson, RSR Determination of coolant water availability by About 4/20/?9 Deckner, RSR location during the accident i
d CD r0 r0
IllEE M!E ISLMID PRESS!!E lilSTORY 2100 p
IMI ESti!Ildtea r>ressure 1900 (stineted Saturation Pressure 1700
/
.d__
-[ [/
I g
1 1500
/
=
/ T 130 19 min. operation of
{
reactor cooling pump L
Operators tower Pressiere gl.
to Allaw cosmal Oct ay elest f
fl
- *= 1 y
900 g
/
/
D M
Hatched area - perio.ls of probatele G8 te i l l ni) arid vo eding E
in nalear core g
L9 Ileactor Cooling PW t Off 500 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 Time - Hours
i-e C0t1 PARIS 0N OF PEAK CLAD TEMPERATURES FOR VARIOUS ACCIDENT SCENARIOS
[ IMI-2 Estim ted fuel i
Surface Temperature 3-28-79 3000
- ' 2500 3
E
's,-
i S 2000 i
?
e s
r 1
i Large
' )q i
as I
g E
LOCA l'soo (
,j l
N e
m i
2
/
s h:.
=
i l
N 1000 SmH t0ca J,e.
L _._ ____ ___./
(
rg>
soii. u,,e, - c.ic.i.te.
Dotted Line. - Guesstimated 500 1
2 3
4 5
5 7
8 h
10 11 12 13 14
^
Time - H6urs
.