ML20084K899

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Revised Procedure AP/O/A/5500/31, Estimate of Failed Fuel Based on I-131 Concentration
ML20084K899
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 02/14/1984
From:
DUKE POWER CO.
To:
Shared Package
ML20084K894 List:
References
AP-O-A-5500-31, NUDOCS 8405140237
Download: ML20084K899 (20)
v • d • e


Text

o.

.~ .

Form 34731 (10-81)

(Formerly SPD 10021) s DUKE POWER COMPANY (1) ID No: Ap/n PROCEDURE PREPARATION Change (s) o/A/44n0/31 to PROCESS RECORD q Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: Estimate of Failed Fuel Based on I-131 Concentration (4) PREPARED BY: r d DATE: 8//Y[1!f'Y (5) REVIEWED BY: DATE: /M 8 Cross-Disciplinary Review By: N/R:DMN (6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: _ , Date:

(7) APPROVED BY: W- Date: 2. V!t!

(8) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

{

E0E INE0RM.ATION .ONLY l

l -

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l g400140237 840511 i PDR ADOCK 05000413 PDR l E m - v ~w-

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  • Form 34912 (8-82) l
  • PAGE NO.

~

CNS l AP/0/A/5500/31 TABLE OF CONTENTS l i

Page No.

A. Purpose 1

,B. Symptoms 1 C. Immediate Actions 2 D. Subsequent Actions 2 Enclosure 1 7 Enclosure 2 8 Enclosure 3 9 Enclosure 4 to  !

Enclosure 5 12 Enclosure 6 14 ,

r 1

l l l

l l

l L

I

Ferm 34S12 (8-82)

PAGE NO.

CNS ESTIMATE OF FAILED FUEL ,

AP/0/A/5500/31 BASED ON l-131 CONCENTRATION 1 i s

A. PURPOSE The purpose of this r.rocedure is to provide a means of determining the quantity of failed fuel based on 1-131 Concentration in the NC System.

B. SYMPTOMS

1. Any of the following EMF's in alarm:
a. 1 EMF 48 " Reactor Coolant Monitor"
b. 1 EMF 18 " Reactor Coolant Filter 1 A"
c. 1 EMF 19 " Reactor Coolant Filter 1B"
2. Any condition in which the operator suspects failed fuel or '

want an estimate of the amount of failed fuel.

i e

- - - - - a -

e, - -_ ---

Ferm 34913 (8-82)

PAGE NO.

. CNS ESTIMATE OF FAILED FUEL AP/0/A/5500/31 BASED ON I-131 CONCENTRATION 2 s

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED C. IMMEDIATE ACTIONS

1. Have Chemistry Obtain A Sample Of The NC System Coolant and determine temperature of sample and time sample was drawn.
2. If, as a result of a LOCA, the containment sump level is not zero and ND pumps are taking suction from the sump (i.e.

unit is in recirc mode) then request the following:

A) Have Chemistry obtain a sample from the ND System (i.e. sump) and determine the time the sample was drawn; and B) Have Health Physics draw a containment air sample and determine the time the sample was drawn.

D. SUBSEQUENT ACTIONS

1. Have Health Physics analyze the samples for isotopic content and concentration.
2. Record sample concentrations and conditions on Enclosures 1 (NC Sample), Enclosure 2 (ND Sample), and Enclosure 3 (Containment Air Sample) as appropriate.
3. If I-131 Concentration is Greater Than 300 pCi/mi, Refer To RP/1/A/5000/01 (EMERGENCY CLASS DETERMIN,ATION) .
4. Calculate the density and inventory correction factors (X and Y) from Enclosure 4.

Fenn 34913 (8-82)

PAGE NO.

CNS ESTIMATE OF FAILED FUEL AP/0/A/5500/31 BASED ON l-131 CONCENTRATION 3 l

a ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. If the unit is in a normal operational mode and no suspected '

mechanically induced failure (e.g.

loose part) has occurred, then l go to 12.  ;

6. If safety injection has occurred  !

then calculate the dilution l factor Z from Enclosure 5. If this is not the case, then assume Z = 1.0.

7. Compute the corrected concentrations of the analyzed isotopes by completing Enclosure 6.

i l 8. If cladding damage is suspected due to an abnormal transient or mechanically induced failure and:

A) the corrected concentrations of Xe and/or Kr exceed the limits specified in '

Enclosure 6; and B) the corrected concentrations of '

I and Cs do not exceed the l limits specified in Enclosure 6; I and C) incore thermocouples have not ever exceeded 700 F; and D) RVLIS indicates no core uncovery; and no excess hydrogen is detected, E) ' then go to 14.

9. If some fuel overheating is l suspected as a result of observing ,

several of the following conditions: '

A) RVLIS indicates partial l core uncovery (<55% level) for a short period of time

(<~ 30. minutes);

B) incore thermocouples have read >750'F;

Fenn 34913 (8-82)

PAGE NO.

CNS ESTIMATE OF FAILED FUEL AP/0/A/5500/31 BASED ON l-131 CONCENTRATION 4 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED C) Cs concentration exceeds the limit in Enclosure 6; D) Te and Ba concentrations do . l not exceed the limits in i Enclosure 6; or  :

E) excess hydrogen is detected, then go to 17. -

10. If some fuel melting is suspected l as a results of observing several  ;

of the following conditions: '

A) RVLIS indicates a severe case of core uncovery; B) incere thermocouples have read >1100 F; l C) Te and Ba concentrations i exceed the limits in Enclosure 6; or  !

D) excess hydrogen is detected, then so to 20.

11. If none of the previous .ets of conditions is met l exactly (e.g. concentration i vs. limit comparison is contradictory with other '

indications) then go to 14,17 or 20; whichever is determined ,

most appropriate.

l 12. Calculate the amount of failed i

fuel present during

{ normal operation using the

following

Percent  : Measured NC l-131 - X Y + 1.8 pCl/ml%

Failed Fuel Concentration (pCi/ml)

(Enclosure 1) '

=

l  % -

_- 1.8 Number of = Percent - 509.5 pins /%

Failed Pins Failed Fuel l

l pins = -

509.5 l

. - _ _ , . - ,__ _, __,____r , _ _ _

Fcrm 34913 (842)

PAGE NO.

. CNS ESTIMATE OF FAILED FUEL AP/0/A/5500/31 BASED ON l-131 CONCENTRATION 5 s

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: lodine spiking may occur as a result of normal operational transients. This may lead to a 2 - 10 times increase in 1-131 concentration while no increase in cladding damage had occurred.

13. Go To 21.
14. Calculate the amount of failed fuel due to clad damage using the following:

Percent = Corrected 1-131 - Y -!- 47.6 pCi/mi%

Failed Fuel Concentration (pCi/ml)

(Enclosure 6)

%=

  • 47.6
15. If percent failed fuel exceeds 100%, then assume that some overtemperature damage has occurred and go to 17.
16. Go to 21.

l 17. Calculate the amount of I failed fuel due to '

overtemperature  !

conditions using the following:

Percent = Corrected 1-131 - Y i- 1535 pCi/mi%

Failed Fuel Concentration (pCi/mi)

(Enclosure 6)

%=

  • 1535 '
18. If any of the conditions listed in' Step 10 are approached and the calculated overtemperature failed fuel percent is large or is >100% then suspect that some fuel melting has occurred and go '

to 20.

G y . _ _ . , _.- --- - - . -

_m_.-

Form 34913 (8-83)

PAGE NO.

CNS ESTIMATE OF FAILED FUEL AP/0/A/5500/31 BASED ON l-131 CONCENTRATION 6 l

l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

19. Go to 21.
20. Calculate the maximum estimated amount of failed fuel due to melting by using the following:

Percent  : Corrected 1-131 - Y 2790 pCi/ml:

Failed Fuel Concentration (pCi/ml) ,

(Enclosure 6)

%= -

2790 NOTE: Some of the 1-131 is due to fuel clad damage and overtemperature conditions. The Reactor Engineer should examine other indicators of Fuel Melting (such as Te and Ba concentrations) in order to refine the estimate.

21. Refer To Tech Spec 3.4.8 a. Refer to appropriate Tech And Ensure 1-131 Activity Spec Action Statement.

Is Within Guidelines. I

22. Inform The Shift Supervisor And Performance Section Duty  !

Engineer Of Tho Results Of This Procedure. The Reactor -

l Engineer will review the results in order to refine the estimates made in this procedure.

-END-l 1

s

--~m ,-n- - -, ,--,--e+- , , , , m ,- - --, . , - , , - - - - . , , - , , , a-., - - - --

Form 34912 (8-82)

PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 1 7 F

I NC System Sample Sample Time Analysis Time Sample Temperature *F NC Loop Sampled isotope Measured Concentration (pCi/ml) 1-131 Kr-87 Xe-133 i

Cs-134 Te-132 Ba-140 t

Hydrogen Additional:

L I

r I

l l

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Ferm 34912 (8 82)

, PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 2 8 s i ND (Sump) Sampic Sample Time Analysis Time Sample Temperature

  • F ND Loop Sampled isotope Measured Concentration (pCi/ml) '

l-131 Kr-87 Xe-133 Cs-134 Te-132  !

Ba-140 2-Additional:

[

i

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1 <

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t I

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r - -

y . - - - - - - -----w* e------w-m -w ---- --c-w- ---em.---ww ----e-- - - ---* --r= w ----m--

Form 34912 (8-82)

PAGE NO.

i CNS .

j AP/0/A/5500/31 ENCLOSURE 3 9 l l

I l

I 1

l l

1 Containment Air Sample '

i Sample Time Analysis Time I 1

I Temperature "F Pressure psig i isotope Measured Concentration (pCi/ml) l l

i l

t l-131

[

Kr-87 i

Xe-133 i

, Hydrogen ,

l  !

l Additional:

l li l

i t

i e

w r-- - -

,,--r--

Form 34913 (8-82)

PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 4 10 k-

1. X Determination NC SAMPLE TEMPERATURE 'F 80 90 100 l

100 .996 .998 1.00 150 .983 .985 .987

.NC 200 .966 .968 .970 250- .945 .947 .949 System 300 .921 .923 .924 350 .894 .895 .897 Temperatu re 400 .862 .864 .865 450 .827 .828 .830

  • F 500 .787 .788 .790 550 .739 .740 .741 560 .728 .729 .731 ,

570 .717 .718 .719 580 .706 .708 .708 590 .693 .694 .695 600 .680 .681 .683 NOTE: Assume NC Sample Temperature is 90'F If  ;

This Information is Not Available.

X=

2. Y Determination if power change is less than 10% within 22 days Y= 100 = 100 =

% F.P. at time of failure ( )

Other times Y= 100 =

gp(,-t A) + NP (1 - e-tA)

Where Y = Correction Factor OP = The % Full Power Before The Power Change

Fcrm 34912 (8 82)

.. PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 4 11 NP = The % Fall Power After The Power Change At Which Time The Fuel Failure Has Occurred A= Decay Constant For 1-131 --- 0.0864 day 'I t = One Half The Time To Make The Power Change Plus The Time After The Power Change Until Damage is Suspected. (In Days) ,

l i.e. 2 Hours For Power Change And 16 Hours To Damage.

t = 2 + 16 = 17 Hours = .708 Days 2

i.

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t t

s "a

Form 34913 (8 82)

PAGE NO.

. CNS AP/0/A/5500/31 ENCLOSURE 5 12

  • Z (Dilution Factor) Determination
1. If the NC System has remained pressurized and no safety injection has occurred then Z = 1.0.
2. If safety injection has occurred but recirc from the containment sump is not occurring then perform the following:

a) Determine the amount of injection flow:

Initial FWST level (%) prior to injection =  %

FWST level (%) at Sample Time =

% Level Change = Initial - Final Level

% =  %-  %

Gallons injected = [(% Level Change

  • 3.76)+ 15.42]
  • 10' gal.

(1) gal. = [(

  • 3.76) + 15.42]
  • 10' gal.

b) Add any accumulator injection flow if NC pressure has remained above 1240 psig:

(2) Accumulator Volume = 0 gal.

If NC pressure has dropped below 1240 psig but remained above 450 psig:

(2) Accumulator Volume = 13400 gal.  ;

if NC pressure has not remained above 450 psig:

(2) Accumulator Volume = 43400 gal.

! c) Calculate Z:

Z = 1

  • Total injected flow NC Volume Z = 1 + [(1) +

(2)] 92000 gal.

__=1+[' +

] 92000 gal.

i

R Form 34912 (8-82) i l

, PAGE NO. I CNS AP/0/A/5500/31 ENCLOSURE 5 13 i

l l

3. If safety injection has occurred and recire is occurring from the containment sump then perform the following:

a) Determine the volume of coolant in the containment sump:

Sump Level at Sample Time = Ft.

If Sump Level is <10 Ft. then:

Sump Volume = [ Level (Ft)

  • 50. + 40. ]
  • 10' gal.

(3) _ gal. = [ Ft.- 50. + 40. ]

  • 10' gal .

If Sump Level is >10 Ft. refer to Curve 7.31 in the Unit One Data Book (OP/1/A/6700/01) or the appropriate curve in Unit Two Data Book (OP/2/A/6700/01) to obtain Sump Volume: l (3) gal.  ;

b) Evaluate the ratio of concentrations:

I Concentration ratio = 1.0 if ND Sample is not available.

Concentration = Measured ND l-131 X Measured NC l-131 Ratio Concentration (uCi/ml) Concentration (uCi/ml)

(4) =

c) Calculate Z:

Z = 1.0 + Sump Volume - Concentration Ratio NC Volume Z = 1.0 + [ (3) *

(4) ] 92000 gal.

I

_=1.0+[ *

] 92000 gal.

4

  • e l _

Form 34913 (8-82)

PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 6 14  ;

1

1. Dilution corrected concentrations:

t Assume dilution Factor Z is a constant for all isotopes.

Dilution Corrected = Measured NC

  • Z (Enclosure 5)

Concentration (pCi/ml) Concentration (pCi/ml)

(Enclosure 1)

Measured NC Dilution Corrected Isotope Concentration (pCi/ml)

  • Z = Concentration ipci/ml) 1-131 K r-87 _

Xe-133 _

Cs-134 Te-132 Ba-140 _

l -

l i

NOTE: Individual Z Factors may be calculated for each isotope using the method of Enclosure 5, if desired. In this manner, an improved estimate '

j of Z may be obtained.  :

l s

Ferm 34912 (B-82)

PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 6 15 l

+

l

2. Density corrected concentrations: e Density Corrected = Dilution Corrected
  • X (Enclosure 4) I Concentration (pCi/ml) Concentration (pCi/ml)

Dilution Corrected Density Corrected Isotope Concentration (pCi/ml)

  • X = Concentration (pCi/ml) 1-131 _

Kr-87 _

Xe-133 _ [

Cs-134 _ (

l Te-132 -

Ba-140 -  ;

f i

[

1.

6 I

i

?

- - __ _ _________ ___.___ ___ ___ _ ____. --- _ _ - - - , . - ,__y. .,- .--y

Fe,rm 34912 (8-82)

)

. PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 6 16 l

3. Airborne activity corrected concentrations:

Concentrations = 0.0 if no containment air sample is available. -

Volume Correction Factor = Containment Volume = 97.

NC Volume Corrected Airborne = Containment Air

  • 97.

Concentration (pCi/ml) Concentration (pCi/ml)

(Enclosure 3)

Containment Air Corrected Airborne lsotope Concentration (pCi/ml)

  • 91 = Concentration (pCi/ml) 1-131 97.

Kr-87 97.

Xe-133 97.

Cs-134 0. 97. O.

Te-132 0. 97. O.

I l

Ba-140 0. 97. O.

97.

97.

97. '

1 P

' Form 34912 (8-83)

. . PAGE NO.

o CNS AP/0/A/5500/31 ENCLOSURE 6 17 l

4. Final corrected concentrations:
  • The corrected concentration is the sum of the density corrected and airborne concentrations. I Density Corrected +

Corrected Airborne Corrected Isotope Concentration (pCi/ml) Concentration (pCi/mi) = Concentration (pCi/mi) 1-131 K r-87 Xe-133 '

C s-134 0.

re-132 0.

Ba-140 0. -

NOTE: No correction for decay has been included. A decay correction i should be factored in if elapsed time from transient to analysis exceeds 2 days. In the case of Kr-87 (76 min. half-life), apply a decay correction after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

)

- -r - - - - -

Form 34912 (8-82)

+

PAGE NO.

CNS AP/0/A/5500/31 ENCLOSURE 6 18

5. Comparison with concentration limits: ,

Concentration = Corrected 2* Limit Limit Fraction Concentration Concentration Corrected , Limit Concentration isotope Concentration (pCi/ml) T Concentration (pCi/ml) = Limit Fraction 1-131 4700.

Kr-87 1.0 Xe-133 5.0  :

Cs-134 300.

Te-132 300.

Ba-120 1000.

t NOTE: Limit for Kr-87 includes provision for a 1 - 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> sampling l and analysis delay.

I l

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