ML20203K873

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Rev 0 to Training Lesson Plan LO-LP-36106-00-C, Radiological Aspects of Core Damage
ML20203K873
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-36106-, LO-LP-36106-00, NUDOCS 8608210391
Download: ML20203K873 (18)
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Text

-

GeorgiaPow POWElGEfeEMATIOpe j

, VOGTLE ELECTRIC GENERA veues .

TRAINING LESSON PLAN ao us- iez.

L.C = s P * $% tC t

TITLE: RADIOLOGICAL ASPECTS OF CORE DAMAGE NUMBER:  :: u cas

  • C6 5 C oP(MTZM 1YtA1mi g PROGRAM: -M m s m uc Coas oANAca REVISION: .x o AUTHOR: RICHARD D. BRIGDON DATE:  :/;/c; APPROVED:

REFERENCES:

M1f DATE: $/$-/g

i. NUREG 0737: ITEM II.B.4 2 MCD TRAINING, VEGP FSAR CHAPTER 13. ITEM 13.2.1.1.6 3 MITIGATING CORE DAMAGE, " RADIOLOGICAL ASPECTS OF CORE DAMAGE,"

WESTINGHOUSE ELECIRIC CORPORATION 4, MITIGATING CORE DAMAGE, " RADIATION MONITORING " GENERAL PHYSICS CORPORATION INSTRUCTOR GUIDELINES:

L.o-Ho-wo ob -oo -c.-oo g HANDOUT: " RADIOLOGICAL ASPECTS OF CORE DAMAGE." 45-n19-066 _

TRANSPARENCIES: -

COI

  • s rf- 3 6 6 0le -c0
  • C -

SR-TP-605-ioo? CALCULATION ASSIMPTIONS I

02-r-06,-b3 OPERATIONAL SOURCE TERMS AND CORE NUCLIDE INVENTORY "E '"1 00" by ACTIVITY CALCULATION SE-85 OS5-4eas' SELECTED EFFLUENT MONITORS

  • !- 5 ^?! ' W ILECTIVE EFFLUENT MONITORS (CONTINUED) ,

02-r--00" ". Q DOSE RATE CALCULATIONS 45-5F-486-4ect CONTAINMENT COIFIANINATION LEVEL CALCULATION Sh-TP=00 57ed ATMOSFRERIC RELEASE 0 O O~ r @ ATHOSFRERIC STABILITY CLASSES 45-9P-066-9918 INFINITE DOSE RATE CALCULATION St=fP-486-400iLSEMI-INFINITE CLOUD DOSE ESTIMATES 19t*TP=00S=ttoG I/Q ISOFLETES

, onyRADIONUCLIDES m m ED TO THE ENVIRONMENT AT TMI-2 Er%.

v;&q r;b; n,'y

., ;

  • v. ,,- -

06002103'?1 060P14

  • PDR ADOCK 0 5', 0 0 4 2 4 g **

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- _ _ _ _ _ . _ _ _ _ _ - - - _ - - - ._-_.a____ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . -

l LC -L.9- 1(e i C to --CC -C

=

. l. PURPOSE STATEMENT:

THIS LESSON WILL PROVIDE THE OPERATOR WITH AN UNDERSTANDING OF THE CONSE RELEASE OF RADIONUCLIDES FROM THE CORE BOTH INSIDE AND OUTSIDE THE PLANT.

1 l

l II. LIST OF OBJECTIVES:

T;._ ...i uo ecuve At " ;d ef G.is lesson, 6'ne operator will have su und. 6.udios ef 0.; me M u 'i '--da 1 ::::::;; feliv-lus = ==, jus assident.

..'==L'*-- n'"--tL:::

1. Estimate the airborne radioactivity inside containment for a rod burst and fuel melt situations.

g a .nsse d

2. Describe the effects of the above accidents on. process and areag nonitors.
3. Estimate the radiological hasards associated with:

i

- Sampling and Venting operations .. .

- Containment Dose Rates from Airborne Nuclides

- Off-site Dose Rate Release Potential Hasards

4. List and describe the factors that affect the offsite dose rates. .
5. Estimate the surface contamination hasards inside containment.

1

6. Estimate, potential radiation hasards inside containment from measured external radiation levels.

i

" - r ';l : _ ,1,. . i.. ; f t" - --- ' -" M --f '- --> hy = =i = 4 - score of 80_

{ r -= == = waissum os vral --= ==caon.

. t . : .-

  • . ' ir "b '

,1,

(  ;

i- { ,

@ 4. .gwdl fi%%yyg su.~W ct i

e 2

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_ . _ _ , . _ _ _ _ . - . , . . _ _ , _ . _ ..._,,.._,_.c_-~_ .,.m_.

,, ko -t P- 3 4 c6-o o - c.

-Sa-u-ou.

lil. LESSON OUTLINE: NOTES I. INTRODUCTION A. Scope of lesson is to investigate: g,o ,7p. 3g e g ,,; _ c _ c, ,

1. Effects of a major accident on installed process and 0 3 3CC- " U area monitors, including:
a. Estimation of fission gasses and particulate
b. Interpretation of abnormal instrument indications
2. Use of measurements outside containment to determine "in-containment" conditions.

B. Analysis assumes all instrumentation operating properly

1. Not concerned with reliability or
2. Whether instruments will continue to operate following an accident.

C. Lesson Assumptions

1. Westinghouse FWR (3 loop) -SR-35 d &-1 TP-oo 2.
a. Core thermal power 2900 MWt

. b. System volume 8910 ft 3

N

c. 0 3 Free Conta h ant Volume 2.5 x 10 ft
2. LOCA with fission product release to containment atmosphere
a. ESF systems operate properly
b. 10 percent failed fuel rods with fission CO-Go ,-2 product released as defined in Table 2. TP-co.2

. A a escapes to containment N

II. CALCULAT CONCElfrRATION INSIDE CONTA '~;

A. Activity may be calculated using: 0 GW4 l

1. Activity = (MI)(EF)(FF)

N '

where: NI = core inventory of nuclide

  • EF = Escape Fraction FF = Failed Fuel Fraction V = Containment Free Air Volume 3

w-q - 33. .cr, ce -c-

' lit. LESSON OUTLINE: NOTES

2. Example calculation
a. Gap release accident equivalent to 10% failed 3 " " 005--3 fuel - calculate the Kr-85 concentration Tp- oo 4
b. 5 NI = 5.1 x 10 Ci  !?. T" OSS 2 T'P-c o3  :

EF = .03 Conversion = 2.83 x 10' al/ft3 A 5

c. Activity = (5.1x10 ci)(.03)(.10) 6 3 0 (2.5x10 fg )(2.83x10 al/f t3)

KR-85 alt.

= 2.16x10-2 ue/al of containment air = T" 005-3 7 ,,

3. Class exercise Calculate the containment activity concentration of Cs 134 and Cs 137 given:

~

EF = .05 ~

[Cs 134] = 6.8 x 106 Ci " en_vnaas_o (Cs 137] = 4.3 x 106 Ci .

FF = .1 Y,,,, = 2.5 x 106 gt 3 Conversion = 2.83 x 10' al/ft3

  • Answer = .84 uc/ml B. Containment Isotopic Concentration S=.- " ^" 5 3
1. Chosen on basis of:

. a.</4 e inventory

s~ ~

, (gas, particulate)

\ , ' .~24;

. e l '*i k

.d... z u :n x Magnitude of escape fraction

2. Remainder left to student calculations C. PERMS GR-38-0&E-4 # #

4R=TP=089-4r Tr-oo to

1. Only Containment Atmosphere monitors are likely to be on line.

OasEcrN[~2.

4

i oc _cP-3c.scG -ce - C.

??. 'J-G57

. i Ill. LESSON OUTLINE: NOTES

2. Instruments will be saturated for this accident o sccew s. " 7-condition 4
a. All vill indicate high 1

l

b. No method available for using these instruments l to measure the actual levels from this accident .
3. Even Containment Vent Monitors Saturate
a. Vented containment air diluted by a factor of 30 prior to detection by High Range m --

monitors.

b. Considering Xe-133 controlling fission gas
1) [Vant] = 6.5 ue/mi = .2 uc/mi 30
2) Within range of radiogas monitor
c. Air Particulate @
1) [e] = 10 uc/mi x 1/30 = .3 uc/mi ~
2) Monitor saturated
d. Iodine
1) CSS designed to remove 99% of iodine C8"** M from containment air. 85 W * *

~3

2) uc/mi

[] = (5 uc)(.01) ) = 2 x 10

3) Within detector range -
4) Spray will also help particulate levels.

D. Conclus

1. Mdet'mouss12p$eparating instrumentation will not

'giw ' / $ ation following this type of

2. Reg. guide 1.97 = regulations and guidelines for post accident monitoring system and sampling 6

requirements allows rapid evaluation of extent of the accident.

III. RADIOGAS EFFECTS ON AREA MONITORS GA-TP=099=$r

~TP oo &

A. Effects calculated by: .

0 6 5;e n J1. Z.

Qt* *r.)

. g cP- 36.cu -c0 -C.

!; :.r-00;-

i 111. LESSON OUTLINE: NOTES l 1- " " "*** -

' _3 <1.7x10-6) = arm /wr 3.6x10 where:

a. Sy = ganana source strength (Mev/cc-sec)
b. 3.6 x 10-5 ,,-1 = gasma mass absorption coefficient for air corrected for density
c. 1.7 x 10~0 = dose conversion factor R-en -see hr-Mev
2. Example calculation:
a. Kr-85 = .514 May gamma in 41% of disinte-grations
b. S 10 y, = (Activity)(3.7x10 dis)(.0041 )(.514 May, ,

Ci-sec dis gamma '

= 2.16x10-8 ggj,, g,,,yg,,, ,,1,,1,gg,,

a _

=

1.68 Nev/cc-sec

c. Dose Rate = ~0 1

1.68 Mev)(1.7x10 )

cc-sec 3.6x10-5)

= 80 ares /hr direct gamma dose

3. Class exercise M3
a. Calculate does rate for Ze-133 with .081 May l gamma 37 percent of time.

l I

b. Calculate [Ie 137] in atmosphere O C1 - : S aat-L TT-003

" .) N m'

??f'**W .. g Activity = (1.5x10 Ci)(.03)(.1) 6 3 0 (2.5x10 gg )(2.83x10 al/ft 3)

= 6.36 x 10 ~0 Ci/cc

. uc -cP. 3 5.c e . c e - c a-ec=ee5

. Ill. LESSON OUTLINE: NOTES l

c. Calculate S y C TT-063-3 S = -6 10 #~ 00 7 y 6.36x10cc Ci)(,37)(3.7x10 dis)(.0 M Mev)

Ci-sec dis 3

=

7.05 x 10 Mev/cc-see

d. Calculate DR Xe 133

= 7.05x10 3 ~0 cc-secMev) 1.7x10-5) 3.6x10

= 333 R/hr B. Conclusions

1. Calculations can be performed for other noble gasses and particulates. C-y .
2. Total rtirborne activity to area monitors is high but within range of High Range Monitor (Low Range Ssturated).

IV. CONTAINMENT CONTAMINATION LEVELS " SR-9P-986-6

'Tf -eo S A. Contamination can also be estimated from the data presented.

Given: Activity (curies)

Containment surface area (4x10 ft ) .

Activity SC = Surface Area B. Example Calculation for I-131

1. Assume all I-131 removed from the atmosphere by CSS and therefore deposited on containment surfaces.
2. ty
s. ,

ff

'AstiW g

  • 10 Ci)(.017)(.1) e,r .cf4; .

5

.- ai x 10 Ci

3. Calculate Scy,g3g 5 2

= (1.3x10 C1) g ft -3 3.5x10 Ci/cm 2 4x10 (ft ) 9.3x10 2 ,,2)

~

= g3.5x10 Ci) g10 unC1)(100) = 3.5x10II ""*

ca 100cm; I

7

-. L.c - LP- 3G c G -o c -C,

".2 L" OSS

111. LESSON OUTLINE: NOTES
4. This contamination level is extremely high Personal dose rate would be:
a. DR = SC x conversion
  • Conversion = 2.8x10 -9 mrem-m 2 *not; accurate uuc-hr 2

3.5x10 II uuc

~

b.

2 10'

,2 cm }(2.8x10 uuc-hr ' mrem-m }

100 cm DR = 9.8x10 mr/hr or 98 Ram /hr

c. Conclusions 4
1) Immediate iodine dose would hinder cleanup efforts
2) th = 8.05 days 1

3)' Cleanup could commence in short time 81 days - DR less than 100 ar/hr -

DE = DR,( )" where n = # of th I

C. Class Exercise for Cs-137 Calculate Cs-137 contamination and resultant dose i

1. Calculate activity:

l 0

Activity = T4.3x10 Ci)(.05)(.1)

= 2x10 Ci

2. Calculate SC g gt 2

...n 2 2 .

4x10 fe )(9.3x10 cm )

100

/cm (10 C1uue) 100)

= 5.38x10 10 unc/100 cm2

3. Calculate DE 10 ~9 R -

DR = (5.38x10 unc 10 cm2

)(4.2x10 3 uc-hr ar-e )(1000 A 100 cm m

= 22.6 Ram /hr 8

. tc -w?- 3e cq-co - c.

u-

Ill. LESSON OUTLINE: NOTES
4. Conclusions
a. Lower famediate DR than I-131
b. t is = 11000 days (approx. 30 yrs.)
c. Significant dose for very long period of time Approx. 230 yrs. to less than 100 ar/hr.

V. ESTIMATING IN-CONTAINMENT CONDITIONS FROM EXTERIOR atstexWC-MEASUREMENTS A. Simple Shielding Calculation B. Assumptions

1. Containment vall thickness
a. Concrete 3.25 ft.
b. Steel liner - 3/8 inch .
2. Nuclide of concern - Cs-137 (most instruments ..

I calibrated for Cs) -

X j C. Calculation .

j

1. t1/10 concrete = 10" therefore 4t1/10 concrete t1/10 steel = 4" therefore = .01 = negligible
2. DR 7

"o *

(1/10)*

DR 7 = 10 x DR,

. .e-VI. EFFECTS OF ENVIROBBENTAI, arr.RAAE gyndt, 4 A. Proper response of.off-site instrumentation to environ-mental re& ease

,h ,' cg of concern.

B. Impor .,

1.

ww4

' Wils&dtt to responsive to P nl x- .y:*. ,

s. Amount of activity released
b. How the release is dispersed based on existing atmospheric conditions
2. Factors to be considered SN
a. * ' '*di ***i'* "" lid **

Iin(Chi) = concsome cloud (Ci/m 5") point t'*** from the releasa.

e 9

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

, _ - , , . - - - , - . . - - . - - . . . - . . . , . - ,, ,- -.-w. - . -- - - . -

we - J - % s c h - CO - C.

OR -I "-0G3 i

ll1. LESSON OUTLINE: NOTES

b. Q = release rate of nuclides in cloud (Curies /sec)
c. X/Q=atmosphergedispersionofradioactive nuclides (cec /m ). Function of:
1) Wind speed
2) Lateral and vertical dispersion -

coefficients a) Dispersion is function of atmospheric stability b) Stability is function of atmospheric S" N-0"5-8 delta T (Pasquill Category) TP. e i e

3. Conclusions
a. If X/Q and release rate is known dose rate at point A can be calculated.
b. DR can be calculated roughly from: ,,
1) D (Ram /hr) = 900(X/Q)(Q)(E )
2) D, (Rem /hr) = 828(X/Q)(Q)(E )

. C. Example problem 100% of all Kr-85 released to containment is released 0 -r 000 0-to atmosphere during 100 seconds right after accident 7p_ o jg

1. Assumptions
a. Atmospheric conditions extremely stable 3
b. X/Q = 10 sec/m
2. Cal _

.d'oc:

. - +e;xd*v c 2 h a _

sec 5

= (5.1x10 C1)(.03) (.1) 100 sec

= 15.3 Ci/sec 10

w -nP-sc.ascs,~oO-C. l C" 1" 005 -

l i Ill. LESSON OUTLINE: NOTES I

b. Calculate cloud concentration cc = (X/Q)Q

" (10

~0 sec/m 3

)(15 3 Ci)(1012 ,,,)

= 1.53x109 une 3

m

c. Dose Rate l S

"( 3.6x10" -5) (1.7x10~0)

~0 3 10 ~0 (1.53x10" Ci)(10 m )(3.7x10 dis)(.0041 ) .514 Mev); 1.7x10 )

a cc Ci-sac dis gasuna 1

~

3.6 x 10 DR = 5.63 ar/Lr D. Class exercise - calculate the DR resulting from a Xe 133 release given:

release time = 100 sec.

X/Q = 10 decay release is .081 Hav gamuna 37% of time '

1. Calculate Q
a. Activity = (BI)(IF)(FF) 100 sec 0

= (1.5x10 Ci)(.03) (.1)

.,yggfy 100 see 500 Ci/sec 2.

4![h'f,e & _ _

~

=

centration (I)

, . %'~

I I( g .. g pf I/q)q 3

= (10 sec/m )(4500 Ci/sec) 3

= .45 Ci/m

3. Calculate DR i

i 11

'. u -4 P- hi c b -CO -C.

.. . . m s Ill. LESSON OUTLINE: NOTES

"( 3.6x10' -5) (1.7x10-6) 3 10

S - la di y (.45 C1)( 3) .081 Mev)(.37 gamma)(3.7x10 s)

,3 6 10 cc gamma dis ci-sac

= 4.99 x 10 I

DR = (4.99x10 )(1.7x10-0) 3.6x10-5

= 23.5 Rea/hr conclusions

1. Xenon 133 presents a significant dose hazard.

I

2. Meteorological tower used to measure:

- wind speed

- direction

- atmospheric delta T AT moAv*88 **

go a swatA. M*

D. Measuring offsite dose pa, 1%4 P-

'{n

1. RMS used to calculate release rate Q , .. -
2. Meteorological tower used to measure: 5
a. wind speed . Jt[ c f.
b. direction *
c. atmospheric delta T /
3. I/Q dispersion factors pre-tabulated on series of St 5 00, overlays Tf-o 43
a. Dose rates calculated by: SR-33-086-M-

. "'n TP-onn.

[l'E f:, Q)(Q)(E )

& *, ;x ~~ -

. .~ .' X )

.* *' ,.g;&J Q)(Q)(E or is release coefficient Conservative results
b. Offsite rad monitoring team can measure actual radiatiosi readings and calculate source strength.

D q.

900(1/Q)(E )

12

. us-c P- m co - co -c, x =-=

111. LESSON OUTLINE: NOTES III. COMPARISON WITH TMI-2 A. Radiation and Contamination Levels -0R ""i-005 12

1. Aux. Bldg - limited ac::ess severely
a. 1000 Roentgen

, b. 100 dpa/100 cm 2

2. Offsite release 0
a. 10x10 C1 (10% of inventory) Noble gasses released during first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. -

~.

B. TMI Auxiliary Building Radiation Levels Following the Accident

1. Note: Review Chapter 9. section H of General Physics MCD text (pages 9-14 through 9-20)
2. Below a'e r several excerpts from NUREG 0600 which

~

demonstrate the potential radiation hazards to

" ~

operators, auxiliary operators and radiation /

chemistry technicians following an accident in which core damage has occurred. These events occurred at TMI-2 on March 28, 1978.

a. At 0521, the Supervisor, Radiation Protection and Chemistry, and Radiation / Chemist Technician I proceeded to the 305 fe elevation of the auxiliary building to take a gas sample
  • and remove the charcoal cartridge from monitor EF-R-227. As the technician loosed the wing nuts that secured the charcoal cartridge holder, water began to spray with enough force to propel the cartridge from the holder. The technician caught the cartridge and forced it

-~ ~

back the holder and secured the wing nut.

ray contaminated his hand. He was insted. The Supervisor returned

$b.

1 room and informed Unit 2

~d t Technical Support of the 1 _

attempt. l l

'A r coolant sample collected about 0643 indicated a gross gamma activity of 140.73 uCi/al. The Unit I nucIsar sample room area radiation monitor EM-G3 alarmed (2.5 mR/hr) during collection of this sample. Radiation /

Chemistry Foreman B surveyed the area and I

found 200 mR/hr on contact with the sample lines. The primary coolant recirculation flow was turned off. The nuclear sampling room air monitor, RM-A12, was inoperable during this period of time.

13

w - u'- s e . c c -oo - c.

u

s Ill. LESSON OUTLINE: NOTES

c. About 1100 Shift Foreman A entered the 305 ft elevation'of the auxiliary building to c1gse electrical breakers that permit operation of the decay heat suction valves. This individual carried a survey meter, which he remembered indicated exposure rates in his work area of 2 R/hr. He stated that his entry took about 5 minutes, and on leaving the building he was found to be contaminated.

Review of the individual's TLD results indicate that a dose of 550 mren gamma and 660 aren beta may have resulted from this entry.

d. Shift Supervisor C and Radiation / Chemistry Technician entered the auxiliary building at about 1300 to transfer radioactive water.

Both dressed in full protective clothing and wore self-contained breathing devices, high-range dosimetry, and TLDs. Upon entering the auxiliary building, their radiation survey ma'ter (RO-2) pegged full scale (5 R/hr). Both withdrew to the health physics area and waited until a Teletector was available. When the " ~

Teletector arrived from Unit 1, the two individuals reentered the 305 ft elevation and proceeded to the radweste operating panel.

The general area dose rates were 8-10 R/hr.

The shift supervisor was unsuccessful in starting pumps to transfer water. On exiting the area, a survey revealed both were contaminated. Their high range pocket '

docimeters indicated about 1 R of exposure.

a. In the afternoon on March 28, Radiation /

Chemistry Technician I and an electrician entered the 328 ft elevation of the auxiliary building to make an electrical breaker lineup.

The fo11aving servey data was taken with a

-;7;- :and recalled by the technician:

1

.* p k g* 9

[ f Rxposure p6 ,.,,,

'g'h!Betramesseauxiliary

"*** (*/h')

305 5-7 R/hr building Bottom of west stairs 305 10 R/hr to 328-ft level Top of west stairs 328 20 R/hr Motor control centers 328 50-100 R/hr Motor control centers 328 20 R/hr average 14

s a t.18- % tc 6 - O c - C

-.~

s Ill. LESSON OUTLINE: NOTES They did not finish the job because they ran out of air. They left the building and returned to the Unit i decontamination area.

The radiation / chemistry technician stated that he was so contaminated that he pegged the RM-14/HP-21 monitor (50,000 cpa) at a distance of 3 feet. He measured 35 mR/hr with an E-520 on contact with his head. Both men showered, but the radiation / chemistry technician had residual contamination'of 1500 cpu on his hair.

The electrician received a gamma dose of 1.33 ren, the Radiation / Chemistry Technician a dose of 1.76 rem by TLD data.

f. At about 2100 March 28, Auxiliary Operator I was directed by a Shift Supervisor B to repressurize the core flood tanks with  !

nitrogen.

l He listened to radiation protection personnel '

discussing dose rates and concluded he might be entering fields of 100 to 150 1/hr. The auxiliary operator dressed himself in

~

[f protective clothing and donned a self-contained breathing apparatus at the step-off pad outside the entrance to the auxiliary '

building, picked up a Teletector, and entered the building.

He entered on the 305-ft elevation, noting an ' '

exposure rate of 20 R/hr, proceeded upstairs  !

to the 328-ft elevation, then back through the fuel handling building to near the penetration room door where the core flood nitrogen valves are located. He recalls dose rates of 70, 100, 30, and finally to 10 R/hr in the valve area. Es estimates it took him between 5 and or the total job.

=

" )On',14;dthe building, he found his 0-200mR 3

@]

- . . to ter was off scale. He returned

- trol room and, on entering,

aM Bi-14/HP-210 count rate meter on

, the table. Assuming his clothing to be contaminated with gaseous activity, he decided to return to the auxiliary building and attempt to transfer water to Unit 1.

A radiation / chemistry technician observed Auxiliary Operator I alarm the RM-14/HP-120 probe and told him he would have to go to Unit I and decontaminate. This comment reaffirmed 15-

., la_U cc -c_

= c =:-

s Ill. LESSON OUTLINE: NOTES his decision to reenter the auxiliary bsilding  ;

at that time before decontaminating himself l since he thought he would become contamit ated again.

g. He once again entered the auxiliary building. 3 This time he walked the 305-ft elevation '

through the swite.h gear room, hoping the exposure rates would be lowered. He Tamembered 30 R/hr as he passed the makeup tank room and 10 R/hr at the radwaste panel.

The pump would not start so he called the control room to reset a trip. He then waited 1 i

in the model room (3 R/hr) for 2 or 3 minutes l before attempting to again start the pump.

The pumps still did not energize, so he ,

checked the breakers, found they were tripped, '

and left the building. He estimates about 10 l

minutes for this entry.  !

On exiting the area, he discovered his pocket  !

dosimeter was again off scale. He undressed 1 and returned to the Unit 2 control room. Ha "

again alarmed the RM-14/HP-210 probe. He ~

l informed the Shift Supervisor D that his dosimeter had gone off scale. The shift j

supervisor told him he could not be used any more and to return to Unit I and decontaminate. The auxiliary operator was about to shower when a radiation chemistry technician told him that, because of high airborne activity, he should wear a mask while showering.

After decont==ination, tha operator's TLD was read, indicating a gasma dose of 3.170 ram.

3. Key point to renseber:

. a, pf.sQ in very short exposure times in

+ building.

.C completely inaccessible.

We

_$9 , . ,

ce sampling exposure levels to a minimum.

VIII.

SUMMARY

A. Noble gasses, air particulate and contamination levels can be extremely high for even small core damage accidents.

i 16

i L.;, - 4 2- 3 (o t C 6 - 0 C - C

-tg-ces s Ill. LESSON OUTLINE: NOTES B. A relatively small fuel rod rupture accident (1-10%)

will most probably saturate the PERMS.

C. Noble gasses (i.e., Xe-133) contribute significantly to the dose rate seen by installed area monitors.

D. Contamination levels contribute significant hazards to cleanup efforts.

E. Inadvertent environmental release can pose significant radiological hazards to the general population.

O 9

, m*$

<p. . " 1 .

- _ .h r 'p - -

- - m., w l

17

t.

TRAINING MATERIAL ROUTING j cc -cP N r.,6 ec -

kMATERIA]LREVISEMATERIAL ISOR E. K2moced /

REASON FOR REVISION:

MAJOR REVISION DUE TO ERRORS OR OMISSIONS. l REVISION DUE TO CHANGES IN EQUIPMENT.

x. REVISION DUE TO CHANGES IN FROCEDURES/0FERATING INSTRUCTIONS OR FOLICT. I DESIRE ADDITIONAL GRAPHICS / HANDOUTS FOR THIS TRAINING MATERIAL l OTNER COMMITTMENTS: TES X NO DRAFTING REQUEST FILLED OUT. TES NO K DATE SUBMITTED FOR SUPERVISOR'S REVIEW 7 / Lt.

REVIEW SAT UNSAT AFFROVAL SIGNATURE i f.O % M DATE

          • DATE NEED E FOR EW FR(Ni TYF I *****

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