ML19207A583
| ML19207A583 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/24/1979 |
| From: | Rickover H ENERGY, DEPT. OF |
| To: | Ferguson R ENERGY, DEPT. OF |
| Shared Package | |
| ML19207A584 | List: |
| References | |
| R#76, NUDOCS 7908210149 | |
| Download: ML19207A583 (10) | |
Text
a, 10 L Vs Department of Energy May 24, 1979 Washington, D.C. 20545 NR:D:HGR R#76 Robert L. Ferguson Program Director for Nuclear Er.ergy THREE MILE ISLAND EMERGENCY RESPONSE-INFORMATION REQUESTED BY THE PRESIDENT'S COMMISSION; FORWARDING OF The Naval Reactors program provided emergency response assistance to the Commonwealth of Pennsylvania, the Nuclear Regulatory Commission and General Public Utilities following the March 28, 1979 reactor accident at the Three Mile Island plant. Department of Energy message R151741Z May 79 requested information concerning this as'istance for transmittal to the President's Commission on Three Mile Island.
A major part of the Naval Reactors pro 1 ram support to the Commonwealt5 of Pennsylvania was provided by the Pi, sburgh Naval Reactors Office, the Schnectady Naval Reactors Office, the Bettis Atomic Power Labora-tory and the Knolls Atomic Power Laboratory through the Emergency Action Coordination Team function.
Information concerning this assis-tance has not been included in this letter in accordance with the guidelines of the above request which states that this information would be provided separately.
Additional assistance provided by the Naval Reactor program included performing radiocheel analyses as detailed in enclosure (1),
consultation on radi ysis considerations as reported in encicsure (2),
temporary loan of 6 radiological control supervisors to assist General Public Utilities in their initial radiological recovery operations, and consultation with the Interagency Dose Assessment Group composed of representatives from the Nuclear Regulatory Commission, the Environ-mental Protection Agency, and the Department of Health Education and Wel fa re.
If additional information or details are rec. f red, I would be happy to cooperate further.
G.
ICk y
Director, Division of Enclosure Naval Reactors Copy to:
R. J. Catlin, EV-10 f ~-
0 2" '
Major General, J. K. Bratton, DP-20
/
Rom TECHNICAL DIRECTOR wn one MAY 21, 1979 Sect THREE MILE ISLAND UNIT 2 ASSISTANCE to File This memorandum sumarizes the assistance provided to the Nuclear Regulatory Comission during the Three Mile Island Unit 2 accident.
This does not include assistance provided to the Emergency Action Coordination Team that is reported elsewhere.
I.
Analyses were made on several reactor coolent and containment gas samples. These included:
Sampled March 29, 1979 a.
Resetor coolant sample #1 Sampled March 31, 1979 b.
Containment gas sample #1 c.
Containment gas sample #2
- Sampled April 2,1979 Sampled April 2, 1979 d.
Waste gas tank sample #1 Sampled April 10, 1979 Reactor coolant sample #2 e.
The most extensive analyses ware performed on reactor coolant sample #1 for selected fission products as well as for core structural materials. The results of all traalyses performed are appended to this memorandum as Attachment 1.
II.
Evaluations of the initial coolant and containment gas a were made to estimate the extent of damage to the reactor c Based on the results of the radiochemical analyses as well as data presented in the Final Safety Analysis Report of Three Mile Island Unit 2, preliminary conclusions were that a large fraction of the fuel rods experienced loss of cladding integrity, 10 to 40% of the fuel experienced high temperatures (in excess of 3200*F), the fuel did not experience temperatures in excess of the 5000*F melting temperature and melting of core structurals and control rods did not occur.
Enclosure (1)
R#76 7862[3d oua cate
4 Memo to File 2
May 21, 1979 III. Consultation was provided on the adequacy of oxygen recombination in the reactor coolant environment.
Based on calculations of generation rates of oxygen from radiolysis and upon estimated hydrogen concentration in the coolant, it was concluded that oxygen formed would recombine with hydrogen.
IV.
Assistance was also provided in obtaining needed equipment for recovery operations at Three Mile Island.
Approximately 8 tons of lead bricks for shielding were delivered to Harrisburg via Pittsburgh area Air Force Reserve aircraft.
In addition, flame arrestors were procured from the Kent Manufacturing Company of Glen Burrie, Maryland and delivered to Three Mile Island.
V.
The major portion of this work, chemistry analyses, was performed by personnel of the Development Laboratories Operations and Materials Technology activities of the Bettis Laboratory. Personnel from many other proj ects and activities assisted as required for technical and administrative support.
The information developed by the Laboratory was provided to the following Nuclear Regulatory Commission personnel; V. Stello, G. Gibson, M. Barrett and S. Bland, et al.
ts
. J. Woo ruf f Technical Director
'n' ' 5 hkb
' ATTACHMENT 1 TABLE I THI-2 Reactor Coolant Sampla il Sampling Date: March 29, 1979 All radioactivities corrected for decay ta 1200 March 30, 1979 I2 Ussa
,sd:i/mi at 1200 3/30/79 I/
6750(1)
I-133 20.8 h 1-131 8.04 d 13500(1) 176(2)
Cs-136 13.1 d 63(2)
Cs-134 2.06 y 275(2)
Cs-137 30.2 y 5.4(2)
Sr-89, 90 21.2(2)
Ba-140 12.79 d 203(2)
Te-132 78 h 1530(2)
Mo-99 66.02 h 0.72(2)
Ru-103 39.4 d 0.36(2)
Ru-106 368 d 0.37(2)
Ca-141 32.5 d 0.36(2)
Ca-144 285 d Rb-86 18.65 d 4 185(2)
HDA in-114m 49.5 d 4.,,0.17( )
MDA Cd-115m 44.6 d 4 1.4(1) m Ag-110m 252 d 4 0.022(2) MDA Zr-95 64 d 4 0.54(2) MDA Hn-54 312 d 4 0.037(2) MDA Fe-59 44.6 d 4 0.034(2)
Co-60 5.27 y 4 0.30 MDA Others Gross d(
(7.2 t 2.4) x 10 pci/ml (no decay correction)
Total Uranium 2.6 pg/mi Total Boron (5) 1750 ppm 78b2bt
, ATTACRENT 1 TABLE II THI-2 Containment Cas Sample il Sampling Data: 0700 March 31, 1979 g i/m1(I) decay corrseted to 0700 March 31. 1979 Za-133 g 743
(
r Za-D3 m 8.0 8,
Za-135 3.5 I-131 0.025 w*
I-133 4 0.01
$e TABTE III THI-2 Containment Cas Sample #2 Sampling Date: 1030 April 2, 1979 jaci/m1(I) on April 3,1979 Aliquot 1 Aliquot 2 Average Za-133 g 28.6 17.7 23.2 Xe-133 m 0.33
' O.21 0.27 Ia-135 0.01 0.0023 0.0062 I-13 1 0.0074 0.012 0.0097 I-133 4 0.0061 4 0.0061 4 0.0061 HDA(6)
Cs-137 4 0.0054 4 0.0054 4 0.0054 HDA(6)
Water in gas samples, pCi/mi decay corrected to 1030 April 2,1979 Cs-136 0.028(2)
I)
Cs-134 0.014 Cs-137 0.055(2)
I-13 1 3.9( )
Crossc(
4,9.2 x 10-8 HDA(6)
OthersI ):
N 79.07., 0 21.07., g 4 0.17.
2
'/8b2E)7
e ATTACEMENT 1 '
TABLE IV TMI-2 Wasta Gas Tank Sample il sample Date:
April 2, 1979 pCL/mi on April 3,1979 Aliquot 1 Aliquot 2 Averste Ia-133 g 4200 6100 5200 Ze-133 m 43 63 53 Ze-135 1.6 2.6 2.1 I-131 0.012 0.16 0.09 MDA(6)
I-133 4 0.14 4.0.15
< 0.15 NDA( )
Cs-137 4 0.1 4.0.1
< 0.1 Others(7):
N 79.2%, 02 13.2%,
11.4%;
Hydrocarbons: CH 0 4 mole percent g
(ethane, propane IJ butane detected and all were < 0.01 mole percent each)
'i'3 0 2 b 8
. ATTACHMENT 1 TABLE V THI-2 Rasctor Coolant Sample #2 Sampling Date:
April 10, 1979 All radioactivities corrected for decay to 1200 March 30, 1979 juci/mi at 1200 March 30, 1979 Note (1)
Note (2)
I-131 24000 Ca-136 210 180 Cs-134 75 72 Cs-137 340 290 Ba-140 420 390 La-140 (decay 270 corrected with parent T1/2)
In 133 g 4.300
,MDA(6) 730 Sr-89, 90 lb-99 2300 Ru-1C3 0.030 Ru-106 4.0.083 MDA Te-132 19
~3 Gross Of.
1.3 x 10 pCi/mi (no decay correction)
(3)
~3 Gross 4.0 x 10 pCi/ml (no decay correction)
Total Uranium (4) 1.4pg/mi Total Boron (5) 2400 100 ppm (duplicate analyses) pH 7.65 "c'902[53
ATTACHMENT 1 BOTES (Applies to Tables I thru V)
(1) Direct GeLi spectrum analysis of aliquot (2) Radiochemical separation
(
Direct alpha or beta counting (4) Mass spectrometry (S) q,g,,yg,,,g,,,go,g,,,,g,,,,1,g, 7
(6) MDA is min 4== detectable activity where To t
e MDC = Min 4-- Detectable Counts = 1.645 2
MDC x decay factor x yield factor gg g.
Counting efficiency x dilution factor x aliquot volume
(
Gas chromatography
'[#d'o53OO
TABLE VI Typical Particle Analyses of Filter Paper Residue From Three-Mile Island Samples
- Veight Percent
_Si
_Fe
_N3 S
_C1
_K
_Ca
_P
_Na
_Al
_Ti
_Hn
_Cu
_Zn
_Sn
_Cr
_Ni
_P.b_
(A)
WG-1 *
- 7 27 11 1
(1) Long, Black 54
.5
.4 4
41 20 8
Fibers 26
.1
.3 7
7 33 3
19 (2) Long 25 5
6 3
19 10 42 Yellowish-19 1
5 8
5 50 White Fibers 30 as Separated 6
6 11 4
20 1
(3) Yellow-white 27 30 Fiber Still on Collection Filter e
2 7
1 3
51 6
19 (4) Y-W Fiber on 9
8 e
Tan Spot 1
3 6
1 2
6 8
4 18 1
(5) Particles on 25 27 Y-V FU>er
.3 36 2
'5
.3
.1 17 (6) Flat Flake 39 6
1 2
3 1
4 1
3 4
2 (7) Small Round 50 28
.4 1
1 9
6 1
6
.5 Particles 45 22 1
3
.4 1
14 1
1
.2 58 2
10 14 1
4 5
2 (8) Small 3
7 Part!cle Clump (B) CG-2 * *
- 4 9
4 (1) Fiber 82 1
.2 1
1 2
1
.2 s'
(2) Angular 95
.1 F'
6
.1 1
1 1
CO Particles 96
.5 4
.2 2
.2 4
2
.7 2
15 2
C' pg (3) Particle 36 38 C;
Clump as
TABLE VI (con't)
Weight Percent Si Fe
}{j$
S C1 K
Ca P
Na Al Ti Hn Cu Zn Sn Cr E.
Pb (C) Asbeefas Standarda (1) Chrysotile -
.1
.5
<.1 ~. 3 NBS 39 1-3 32 6
.2 3
Bettis 46-
. 5-37-1-2
.3 59 3
46 (2) Amosite -
- 1. 5
.1
~.3 NBS 50 15-28 11
.2 1
2 Bettis 44-6-
6-1-3 65 44 20 (3) Anthophy111te
.1 1
1
.1
~.7 1
NBS 58 2-4 24 u
Bettis 68 5
23 3
1 (4) Crocidolite
.1 5
~.5 NBS 49 15-27 4
Bettis 60 18 16 4
2 Energy Dispersive X-ray Microanalyses hy Show Large Ranges for Mixtures of Haterials of Distinct, but of Various, Compositions.
n' 1
- WG-1 means Waste Gas Tank Sample #1.
g,j.'
s.
CG-2 means Containment Gas Sample #2.
g DC CO CQ