ML20203K861

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Rev 0 to Training Lesson Plan LO-LP-36105-00-C, Post- Accident Primary Radiochemistry
ML20203K861
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 05/05/1985
From: Brigdon R, Scukanec D
GEORGIA POWER CO.
To:
Shared Package
ML20203K798 List:
References
LO-LP-36105-, LO-LP-36105-00, NUDOCS 8608210385
Download: ML20203K861 (13)
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TRAINING MATERIAL ROUTENG IN N -

NEW MATERIAL /REVIS D MATERIAL s #[ [

AUTHOR / REVISOR P.. Be m Oc4 O /

PJAss Re~ r  % 4 Q C

(.y a g REASON FOR REVISION:

MAJOR REVISION DUE TO ERRORS OR OMISSIONS.

REVISION DUE TO CHANGES IN EQUIPMENT.

x REVISION DUE TO CHANGES IN PROCEURES/0PERATING INSTRUCTIONS OR POLICT. l DESIRE ADDITIONAL GRAPHICS / HANDOUTS FOR THIS TRAINING MATERIAL l

OTHER COMMITTMENTS: TES Y NO DRAFT UG REQUEST FILLE OUT. TES NO k DATE SUBMITTE FOR SUPERVISOR'S REVIEW NW

REVIEW SAT UNSAT APPROVAL SIGNATURE I Jhh+,9 DATE M[
          • DATE NEEDE FOR EW FRCH TTF DG [7 ***** l

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LIBRARY CLERK: M l DATE TO TYFING 7b/

. DATE TO DEAFTING M/ / N I

DATE FROM TTFING DATE FROM DRAFTING NlM I CONFILED MATERYALB TO INSTEDCTOR FOR REVIEN. DATE MSTEDCTOR REVIENs TTFING SAT UNSAT DRAFTING SAT UNSAT REIRME1 1ETI. 2.cas.

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' SUPERVISOR SIGNATURE DATE LIBRARIAN RECEIFT FOR DCLUSION/0UTDATING OF FILES. DATE 1

FILE WORK DONE DATE 9609210385 960914

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Georgia Power ,

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, Powt3 GENERATION DEPARTMENT

. . VOGTLE ELECTRIC GENERATING TRAINING LESSON PLAN %# %# gp l l l

TITLE: POST ACCIDENT PRIMARY RADI0 CHEMISTRY NUMBER: c 3,q q ,cc_

PROGRAM: N ** REVISION: yo l i

AUTHOR: RICHARD D. BRIGDON DATE. . . . , .

APPROVED:

MM DATE:

S~/f/J[

REFERENCES:

l l

l. NUREG 0737, ITEM II.B.4 I J. "MCD TRAINING," VEGP FSAR CHAPTER 13, ITEM 13.2.1.1.6 '

3 MITIGATING CORE DAMAGE, " POST ACCIDENT PRIMARY RA'DIOCHEMISTRY," WESTINGHOUSE '

ELECTRIC CORPORATION q, MITIGATING CORE DAMAGE, " REACTOR CHEMISTRY," GENERAL PHYSICS CORPORATION INSTRUCT 0P. GUIDELINES: i Lo -vio -Ica e f- oo -c - oo t a

j HANDOUT: " POST ACCIDENT PRIMARY RAD 10 CHEMISTRY,".S&-He-06& '

TRANSPARENCIES: .

ooi N"f*M W M Mo c,w o* e6 m m

'O~Tg g gg,,,o c 44-TP-684-+oog,FLANT PARAMETERS GR-33-464-G 805 REACTOR COOLANT CHEMISTRY SR-D-444-4ooat NORMAL PLANT OPERATION SOURCE TERMS AND INVENTORY OF RADIONDCLIDES FOR HYPOTHETICAL ACCIDENT SS "" ^**. 5 r:SSAMPLING SCHEDULE SR-TP-664=6eod. OPERATING PLANT FISSION PRODUCT DATA

-SR-9P-684-foo? CAP mmE COMPONENT VALUES S& m et REACTOR CORE DESIGN PARAMETERS SR-TPyg4-9ee9 EQUATION - COOLANT ACTIVITY RELEASE 65-sp-484-40oseTMI-2 FISSION FRODUCT SAMPLE RESULTS 9t=TP=684-Hoss ZIRCONIUM WATER REACTION S m ir. MELTDOWN o ESCAPE FRACTIONS

?? "" ^"' !"cesACTIVITY RELEASE CALCULATION FOR MELTDOWN Y,e . W' NTMI-2 FISSION PRODUCTS ss"ACTIVITT AND DOSE RELEASE FROM SAMPLE J.

  • H. DOSE FACTORS FOR SEMI-INFINITE CLOUD

$ 87 EXTERNAL DOSE FACTORS y' ~ g(/. i osSINEALATION DOSE FACTORS FOR ADULTS 4

l MXiER COPY 1

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1 -

g - P - 3( . os- co-c

.a -ee- m

1. PURPOSE STATEMENT:

THIS LESSON PROVIDES THE OPERATOR WITH AN UNDERSTANDING OF THE VARIOUS RELEASE MECHANISMS OF RADIONUCLIDES FROM THE REACTOR CORE DURING AND AFTER A MAJOR ACCIDENT AND THE RADIOLOGICAL HAZARDS ASSOCIATED WITH IT.

II. LIST OF OBJECTIVES:

,.. . ., n,., _ - e.;

a- e ...: .i swi. i...... <ne acu ent m u .... . a...... 2% f e: -u.et.-of-a

_-::- ---u- c ;e w :.. sa.. 1. .g .

.EnahlinLSh. tact.isee

1. Explain the incore release mechanisms of fuel and cladding failure and their effects on primary radiochemistry.
2. Describe the differences between a rod burst and a fuel melt including their effects on coolant activity levels. ~ -
3. Compute the increase in coolant activity level for various nuclides following an accident given appropriate background information.
4. Describe the radiological hasards of sampling following a major core release and how the hazard varies with time.

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sua. 1- ---. ;ill t. . . ' f _ ::f 5- - = != 4--

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lli. LESSON OUTLINE: NOTES I. INTRODUCTION A. Subject u t-P- h c s - ca c - cc. ,

1. Change in primary wate radiochemistry following a core damage accident. *
2. Radiological consequences of:
a. Drawing and
b. Handling of primary coolant sample following an accident.

B. Two levels of core damage to be considered *

  • Considered 10% fuel failure
1. Crack or rupture of fuel rod cladding (rod burst)
2. Partial fuel meltdown due to
a. Hi.gh core temperatures
b. Catastrophic failure following core voiding II. BASELINE PLANT AND ASSUMPTIONS A. Calculation Assumptions N
1. Core Power (MWt) 2900
2. Specific Thermal Power (MW/MIU) 40
3. No. of Coolant Loops 3
4. Primary Water Volume (ft ) 8910
5. Ncrual Operating Pressure (peia) 2250
6. Average Core Temperature 590*F
7. -Core _T MOL
8. T-- 1ed Fuel Fraction .01 B. Prima ifications 4R=TP-tM4=t

-re. o o s

1. Normal RCS activity levels for assumed plant. SR-9P-684 a. Represent failed fuel fraction of 1/10 design basis (.001)
b. Total core radionuclides inventory 6R-TP-684 'TP- cuH 3

--,,w..,.,------,-.-,,,---,,,,,,7,,._,-, , , , , - - - , . . , , . - . - , - - - , - . - - , , - - - - --.--,,,.,,--..---.,y. - _ y,,_- -, ,

LC- i [- I b s C Y - CC - C er u =

111. LESSON OUTLINE: NOTES

2. a and b above vill vary with
a. Core rated power
b. Time in core life III. NORMAL PLANT CHEMISTRY A. Normal Samples and Frequency O T7-G69-5
1. Daily samples include TP-o 05~~
a. Degassed gross beta - gamma activity
b. Radioiodines
c. Tritium
2. Will discuss effects of core damage on
a. Beta - gsama activity
b. Radioiodine
c. Noble gasses B. Principle Contributors to Beta - Gamma Activity

. 1. Iodineandpsium e

2. Approximately 1 f'/gn. May vary as much as 10 times due to: *
a. Cladding defects
b. Crud bursts
3. Noble gasses contribute approx. 1 pcV3m of activity to coolant.

IV. IN-CORE MECHANISMS

-/ gpg e, A. Fiss coolant by:

1.

, [ l to gap (release fraction)

2. Escape via clad defects (escape fraction) 4R-99-084-6 vf-co b B. Escape rate coefficients for several important nuclide en gn naa a categories Tf-co S
1. Magnitude of release varies with nuclide volatility Sa r = -
a. Noble gasses volatile at room temp.

Tt- co7 4

to-J- %icf co-(

On '." 004 lil. LESSON OUTLINE:- NOTES

b. Iodines volatile at fuel temps. but reactive with metals Iodine escape fraction dependent upon:
1) Oxide form taken after rehetion
2) Type of fuel rod failure c.

Cesium will vaporize at fuel temps but has a lower escape fraction than iodides.

d. Strontium
a. Exists in metallic or oxide form
b. Not readily released from fuel unless meltdown takes place.
c. Increase in coolant activity can be SR-38-084 estimated by: Sp,oog.
1) CA = (NI)(EF)(FF) ,,

V where: CA = activity (pci/al) oo 4 NI = core nuclide inventory SS "" 00! 4-EF = Escape fraction for SS "" " i

nuclide class Y'007 Y = coolant volume (ft ) S" "'" ^ ^ ; i FF = failed fuel fraction Tf-c o ?

2) Best guess estimate of EF V. ROD BURST EFFECTS ON RADI0 CHEMISTRY A. Accident description
1. High inte ressure causes cladding rupture
2. maintained

- .y jeg q.;

3. Stumes ivalent to failure of 10 percent

.q : k',

B. Exsaple calculations

1. Noble gasses (Kr Ie)
a. Factors
1) EF = .03 _-u-vo -,

TP-oc7 7

2) NI = 30.85 x 10 Ci e"

l

t o-cP-  % os .cc -c_

C D _T D _ A O f.

lli. LESSON OUTLINE: NOTES 3 8

3) V RCS

= 8.91 x 10 ft3 (1.82 x 10 g) Conversiog factgr 2.04 x 10 g/ft

b. Calculation results .  ?"-T"MS'; 9 7 6
1) CA = (30.85x10 C1) ( .03) (*.10) 10 uc h 8 A(; al 1.82 x 10 g
2) 5 x 10 pc'/m (noble gasses)
c. Short lived isotopes will decay quickly
1) Atsamplinglevegvillhavedecreasedto l approx. 2.5 x 10 pc/ml l
2) Normal noble gas concentration approx.

.3 pd/ml

d. Cogclusion: Noble gasses increase approx.  !

10 times l

2. Beta - gamma grosa activity
a. Iodinen ~
1) EF = .017
2) NI = 6.5 x 10 Ci 0".""J 000 0
3) CA = 6 x 103 ue/al
b. Cesium *
1) EF = .05  ?" *" 00? P re- co i 0
2) NI = 13.8 x 10 Ci SR-GF-484 CA = 4 x 102 ,,f,1 *M 3) l c. contributions negligible due to:

l 1)f low escape fraction and low i ~ sq ~ ory (i.e. SR = .1 uc/ml) beta - gasma activity .1 ue/al -

d.

Conclusion:

beta - gasma ingresses approx. 700( f p o, f, w t

times (CA7 + CACs = 6.4 x 10 uc/ol) ,

g gy C. Conclusions and Observations ,

1. Effect of varying sample times

[/ - 9/04 + AM'M**

a. Calculations based on immediate sample 7aa d/

6

. w o J- w oS-uc -c 02 R-U64 lli. LESSON OUTLINE: NOTES

b. One day later
1) Noble gas decrease by factor of 2
2) Iodine decrease by factor of 3
3) Cs relatively constant
c. .i.e.: time of sampling has a significant effect on activity (Sample must be corrected for time)
2. Comparison with TMI .SR ZB-084-44
a. Even though more extensive core damage than T-oeo rupture results compare well VI. MECHANISMS FOR EXTENSIVE CORE DAMAGE: RADI0 CHEMISTRY EFFECTS A. Cladding Characteristics o4 TEN t.

t 1. Zirconium alloy - high strength and heat transfer characteristics

2. At high temperatures reacts with H O

. 2

a.  :: ; 00' ;;

Zr + 2H20 4 Zr02 + 2H2 + w a ar-

b. Produces heat (exothermic) and embrittlement of Zr.
3. Prevented by limiting: '
a. Peak clad temp. to less than 2200*F
b. Clad oxidation less than 17 percent of thick-
ness during DBA.

I

- At operating conditions, does not

.p o-if  ; .

1 percent of limit over core life

4. Assions (core uncovered) w . ., 3 -

l a.9 Cladi more than or equal to 2000*F.

s b. ',,^,%^%.* " embrittlement and failure within r

b. Cisd temps greater than or equal to 3450*P.

/

w

1) Oxidised sitconium melts .
2) Evidence shows UO 2 can dissolve in Zr ./

melt 4

7 l

l

....A ,_ _.-_.m . . _ - . - . - . _

L.e_c?-3uof-co- c 02 LT 000 Ill. LESSON OUTLINE: NOTES

3) 1.e.: fuel becomes liquid below melting

temp of 5200*F -

+1 - ' s '

c. Conclusion
1) Fuel melt characteristics' release may occur well below 5200*F B. Calculations
1. Conditions considered
a. Same equation used for rod burst rN oos
b. Escape fractions S" '" 09' ? (compare with S" '" 004 7)-
c. 10 percent partial meltdown 79-ocry
2. Noble Gasses (Xe, Kr) SA-9P-684-4='

rf- oo 9

a. Higher escape fraction (.9) sa m

~t1-olt

b. C1=1.53x10 ve/a1 ,: sa.3s=084 43 Tf--o t2
3. Beta - gasma activity
a. Iodine ** -" 0"i ? -

TP - 0 0 4

1) EF = .9 48 4P-684-1-2 Tr-oa7
2) CA = 3.2 x 105 ,,j,1 ,,_,,gg,_33_

rt'- o s3

b. Cesium
1) IF = .8 3
2) CA = 6 x 10 uc/ml
c. Str 7/. - cape fraction = .1 x

[ h 4c._ W .7[ uc/ml

.. - gamma activity increases by more than 300,000 times.

C. Conclusions (Comparison to Rod Burst) gms c. 3

1. Amount of activity increases significantly due to larger escape fractions.
a. Primarily due to the melting and homogeneous mixing with reactor coolant.

8 1

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=== '

III.

LESSON OUTLINE: NOTES

b. Fission products released to coolant due to fuel pellet breakdown - diffusion through pellet unnecessary.
2. Type of nuclides released
a. Sr-90 is major contributor along with Cs-137
b. Serious melting accident will also release U-235 and Pu-239.
3. Keep in mind that analysis does not include i

nuclide ts's.

a. Activity at onset of damage may be significantly different than at time of sampling.
  • 1) Kr/Xe decrease by factor of 2
  • Assuming one day delay in sampling
  • 2) I (short lived) decrease by factor of 4
  • 3') Sr decreases by 25% i

' 2: l D. Comparison with TMI-2 .

4R-fr=004=tt-11-o84

1. Fairly significant beta - gamma activity
a. Indicates fuel amit
b. Due to presence of Sr-90 (approx. 5% released)
c. Iodine, Cs, Rb 65% core inventory released
d. H2 - 60% release
2. Noble gasses '
a. Appros. 50 percent released VII. HAZARDS OF m q ds.. .

A. Eigh 'ereste problems associated with i

      • F h:,

~

1. sample

. 2. Inhalation of activity B. l 4

Estimation of consequences of accident sampling 1 i

1. Assumptions
a. 100 mi sample collected 9

i.e- J- N cs-co -c.

4R-he-e*

ll1. LESSON OUTLINE: NOTES

b. 10% of fuel rods ruptured
c. Total noble gas concentration - 5 0x 10 W ' ,

(previously determined) ,

ts .

.gg 2.

Q' f' ' ,

Asampleonedayafteraccgdentwillcontain primarily Xe-133 (2.5 x 10 uc/ml) -

(, "

a. 3 Total Activity - (2.5 x Ig uc/ml)(100 ml) = ,

= 2.5 x 10 uc or .25 C1 ,,

b.

y, ,

If this ses escapgs the coolant and fills the >

sample room (36 m ) e

,ja Room noble gas concentration =

.25 Ci =

.007 Ci/m 36 a

c. DR calculated using conversion to ares /hr. GR=TP=004-M-DR' = 7x10 -3 C1 10 uuc 2.94x10 aree-10 3

,3 1 Ci uuci-yr ,.

= 21 x 10 aram/yr Assuming 15 minutes in sample area.

DR = 21x10 mram yr day hr 15 min yr 365 days ~24 hrs 60 min 1

= 60 aren '

d. Direct radiation dose from sample may be estimated using the curie-enter-rem thumbrule.
1) I curie at 1 meter = 1 Ram /hr
2) Cesium activity one day after accident

-3p

] . ,

ins has only low energy beta's f hrisBetaemitter At'one meter = .6 Rem /hr //

r

4) If operator only 1 foot from bottle

')(b a) Dg = D, = .6 = 5.4 Ram /hr bU i

or 1.4 Ren for 15 minute exposure 10

, _,..----,..-y-m,, . _ , - . - - , , , _ . , ~ . _ , - , - - - - - - . - _ , _ _ . . . _ - - . , , - , - - - - . - - - - +

2 s

e s-O-La~ keCC-CC~c S". '.7-034

+

lil. LESSON OUTLINE: NOTES l

3. Conclusions w s

/  ;

a. Very high dose therefore extreme care must be taken during sampling . ).  !

i: l

b. Requires special shielding to reduce operator exposure. '

C. Contamination Levels for Spill of Sample

1. Assumptions
a. Bottle dgopped and spills half of contents over 4 m i
b. 10% sap release I
c. Sample one day after accident
2. Primary nuclides are I-131 and 133, Cs-134, 136, 137
a. I-131 activity TA = V ,x CA

" ~

7

= 7.7x10 Ci .017 .1 (100g) 1.82 x 10 g

= .07 C1 Coitamination Level 12 9 2 Is(.07) 1x10 une 1 = 9x10 uuc/m Ci g 2 2

DR = 9x10' mec 2.8x10'I ar-m = 25 ares /hr

,2 unc-kr 15 minste exposure = 6 aren

~ ^~

1. 'ty Spilled x Fraction Airborne i Ny$l.5k@ " '*2 =

where fraction airborne = .001

2. For Iodine-131: '

3 AA = (.035 Ci)(.001)( 1 )( Im )(106 ,,)

3 6 C1 36m 10 ml

= 1 x 10 -0 ue/mi

. 11

, , - - , , - - - - - , - , - , , - - - - - - - , , , ,,--,,-,--,e ,--nr _ _ , , ,, ---,--,,,----,,n,-,---.,,,,------,-.--e w

e ue -L.# - %t c f - c 0 - (_

C" '." 0"'

Ill. LESSON OUTLINE: NOTES

3. Keep in mind critical organs vary with nuclide
a. I-131 - thyroid

~

b. Annual dose = 1.5 x 10 ares /uuCi inhaled S"-T" 0"' 13 4 066
c. Adult breathing rate = 1.5 x 10 al/ min.
d. Total inhaled

(* *

)( * "*)(15 min) = 23 uCi

e. Dose to thyroid 3

(.23 uc)(1.5x10 mr) 10 uuc) = 345 aren VIII.

SUMMARY

A. Estimates of the extent and nature of a fuel damage accident can'be made from the results of radiochemical samples following the accident.

B. Various mechanisms exist for fission product radio-nuclides to reach the coolant.

1. Diffusion through cracks or pinhole leaks in cladding during normal ops.
2. Release through ruptured cladding
3. Release through oxidized or melted fuel elements and cladding.
4. Leaching from broken and oxidized fuel rods.

C. Extensive hasards are associated with the sampling l operation. These hasards must be minimized by using l spec at and procedures which contain j the f shield the operator from dire sample.

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I dh -

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12 i

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