ML20092H314

Rev 1 to Engineering Departmental Procedure EDP-ZZ-00005, Assessing Core Damage

ML20092H314
Person / Time
Site:	Wolf Creek, Callaway, 05000000
Issue date:	05/16/1984
From:	Bryant K STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:
Shared Package
ML20092H307	List: ML20092H314 NRC-84-0094, Forwards Revised Core Damage Assessment Procedure & Addl Info Re Capability of post-accident Sampling Sys to Perform in Postulated post-accident Environ Per NUREG-0737,Item II.B.3
References
EDP-ZZ-00005, EDP-ZZ-5, NUDOCS 8406260071
Download: ML20092H314 (35)

Text

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,-v ENGINEERING DEPARTMENTAL PROCEDURE .

EDP-ZZ-00005 ASSESSING CORE DAMAGE RESP. DEPT. [A % W PREPARED BY k b (N' M T U O APPROVED BY k DATE E !/7 f gY

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W f DATE ISSUED This procedure contains the following:

Pages 1 through 4

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7. - - ASSESSING CORE DAMAGE 7 1.0 PURPOSE AND SCOPE 1.1 This procedure provides a methodology for determining the extent of core damage fol-lowing an accident using the Post Accident Sampling System (PASS). Preliminary esti-mates may also be made based on H2 concen-tration in the containment, core exit ther-mocouple readings, reactor vessel water level, and containment radiation readings.

i 2.0 DEFINITIONS 2.1 Clad damage - Clad damage is characterized by the release of fission products which have accumulated in the gap between the clad and the fuel. The fission products which diffuse to this gap are the volatile ones such as the noble gases, the iodines,.and the cesiums.

2.2 Fuel overheating - Fuel overheating is characterized by grain boundary release and diffusion from the UO 2 grains. This is es-timated to be 20-40% of the noble gas, iodine and cesium inventories.

2.3 Fuel melt - Fuel melt leads to rapid release of many noble gases, halides and cesiums remaining in the fuel after overheating.

~

Significant release of the strontium and barium - lanthanum groups distinguishes this condition.

3.0- NOTES AND PRECAUTIONS 3.1 This procedure may be copied so that it can be used more than once. Attachment 1 will have to be copied for each isotope to be used in the analysis.

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3.2 -

During accident conditions, it is not known ' -i s[3[

in what order that information will become- "J ~ 7 available. Therefore, this procedure does

,not have to be completed in the order that it is written.

3.3 If hydrogen recombiners or the hydrogen purge system are operating, core damage es-  !

timates based on hydrogen in the containment may be inaccurate.

3.4 Use as many indications as possible to diff-erentiate between the various core damage states. Because of overlapping values of release and potential simultaneous condi-tions of clad damage, overtemperature, and core melt, considerable judgement needs to be applied.

4.0 PROCEDURE 4.1 Obtain an estimate of core damage using con-tainment hydrogen concentration, core exit thermocouple readings, reactor vessel water level, and the containment radiation monitor.

4.1.1 Hydrogen Concentration 4.1.1.1 Record containment hydrogen concentration.

4.1.1.2 From Attachment 9, obtain the %

l zirconium-water reaction and record here.

l l 4.1.2 Core Exit Thermocouple Readings l

4.1.2.1 From Attachment 8, estimate the core damage based on core exit thermocouple readings.

Core damage:

4.1.3 Reactor Vessel Water Level

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! 4.1.3.1 Record the duration of core uncovery. "g,' g;q;gg Duration: minutes ,,

6'~ _ y mM$

9) 1 1 4.1.3.2 From Attachment 8, estimate whether core

! damage has occurred based on core uncovery.

Core dmnage:

4.1.4 Containment Radiation Monitor 4.1.4.1 Record the Containment Radiation Monitor level R = R/hr.

! 4.1.4.2 Record the 30-day average power (from Attachment 2) P=  %

4.1.4.3 Calculate the normalized dose rate 100%

. I Normalized Dose Rate ='3.66 x 10 4 xRx P =

R/hr -MWt 4.1.4.4 Record the time'since the accident hours.

4.1.4.5 Using Attachment 10, estimate the core damage.

Core damage:

4.2 Estimation of core damage using PASS sample results.

! 4.2.1 As sample results become available, complete a copy of Attachment 1 for each isotope. If an estimation of core damage was made in 4.1, then preference should be given to i those isotopes which are indicative of that I type of core damage. Attachment 3 provides I a list for this purpose.

l 4.2.2 Using the percentage of inventory released and the fission product ratio from Attach-l ment 1, and using Attachment 8 and 11 to 23, estimate the damage and record below.

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!  !  ! Fission  ! Estimated.

Sample ! Fission 1; Percentage  ! Product  ! Core Time  ! Product  ! Released  ! Ratio  ! Damage

! 1  !  !

! 1  !

5  !  !  !  !

5.0 REFERENCES

! 5.1 Westinghouse Owner'O Group Post Accident

! Core Damage Ased iment Methodology 5.2 FSAR Tabl* .?-

5.3 Table of 160 topes; Lederer, Hollander &

Perlman s

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' J:0 CALCULATION OF PERCENT e, '%

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OF CORE INVENTORY RELEASED 1.0 Isotope 1.1 Decay constant (from Attachment 3) A =

1.2 Half-life (from Attachment 3 ) T /2 1

=

2.0 Time and date of shutdown .

3.0 POWER CORRECTION FACTOR 3.1 Determine the power history using Attachment 2.

3.2 For steady-state power (except Cs-134), com-plete the appropriate section of 3.3. For transient power history (except Cs-134), com-

. plete the appropriate section of 3.4. For Cs-134, complete 3.5 3.3 STEADY STATE EXCEPT Cs-134 3.3.1 Half Life <1 day Power Correction Factor (PCF) =

Steady state power percentage for prior 4 days 100

=

3.3.2 Half Life >l day l

Power Correction Factor (PCF) =

l Steady state power percentage for prior 30 days l

100 l

=

! 3.3.3 Half Life > 1 year Power Correction Factor (PCF) = EFPD Total days of operation =

ATTACHMENT 1 Page 1 of 8

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! 3.4 TRANSIENT EXCEPT Cs-134 ~.

I 3.4.1 Total period of operation > 4 x T 1 /2 Power Correction Factor (PCF)=Ij[Pj (1-e-Atj )e-At*j ]

=

100 I where tj = operating period in hours at power Pj where power does not vary more than 10 percent power from time average value (Pj)

Pj = percent power during operating period tj tj = time between end of period j and time of reactor shutdown in

! hours.

! 3.4.2 Remaining transient cases Power Correction Factor (PCF) =

Ij[Pj(1-e- )e- ] _

100(1-e ^1 )

! 3.4.3 T > 1 year

! Power Correction Factor (PCF) = EFPD

! Total days of operation =

! 3.5 POWER CORRECTION FACTOR FOR CS-134 Power Correction Factor (from Attachment 6) =

(Use average power during entire period of operation from Attachment 2) 4.0 RCS ACTIVITY 4.1 Sample Data 4.1.1 Time and date of RCS sample

! 4.1.2 Time since shutdown t = (hours) 4.1.3 RCS volume ( from Attachment 4 ) V= fta 4.1.4 RCS temperature TI = F.

4.1.5 RCS water density ratio (from Attachment 7) pl/pstp =

ATTACHMENT 1 Page 2 of 8

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.3 4.1.6 Sample result Cm = pCi/cc 7, 4.1.7 Sample temperature T2 = *F 4.1.8 Sample water density ratio (from Attachment 7)

! p2/pstp = _

4.2 Decay correction of sample to time of reactor shutdown At 4.2.1 Cc = Cme = Ci/cc

! 4.3 Parent-Daughter Correction Factor Fr

! NOTE For isotopes which must have a

! parent-daughter correction

! factor applied, the parent

! isotopes are listed in Attach-

! ment 3. If no parent isotope

! is listed, then Fr=1. If 2

! isotopes are listed as parents,

! then a correction factor must

! be calculated for each parent

! (Fr A and Fr B }*

! 4.3.1 Fr A

! 4.3.1.1 Parent isotope A ( from Attachment 3 )

! 4.3.1.2 Parent isotope A decay constant (frcm Attach-

! ment 3)A =

! 4.3.1.3 Parent isotope A 100% source inventory ( from

! Attachment 3) Q =

! 4.3.1.4 Daughter isotope 100% source inventory (from

! Attachment 3)Q =

! 4.3.1.5 Decay Branching Factor (from Attachment 3)KA"

! 4.3.1.6 A- -A t -At A

! Fr =K A ~A O * ~* =

A A A

! 4.3.2 Fr Fr B

=0 if only one parent is listed in

! At$ac(hment 3) 1

! 4.3.2.1 Parent isotope B ( from Attachment 3 )

ATTACHMENT 1 Page 3 of 8

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! 4.3.2.2 Parent isotope B decay constant (from Attach- ,

I ment 3 ) AB"

! 4.3.2.3 Parent isotope B 100% source inventory (from

! Attachment 3 )Qg =

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! 4.3.2.5 I -A t -At (A

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! 4.3.3 -At

! Fr = Qe Q'e At + FrA + FrB

! 4.3.4 Corrected sample activity

! C p =C x Fr = pCi/cc c

! 4.4 Temperature correction of sample

! 4.4.1 p /pstp C=C X P2/pstp = pCi/cc F

! 4.5 RCS Activity A(RC) 4 =

! 4. 5.1 - A(RC) = V x C x 2.83 X 10 Ci 5.0 CONTAINMENT SUMP ACTIVITY 5.1 Sample Data 5.1.1 Time and date of containment sump sample

! 5.1.2 Time since shutdown t= (hours) 5.1.3 Containment sump volume (from Attachment 5)

V= fta 5.1.4 Containment sump temperature T1 = F 5.1.5 Containment sump water density ratio (from Attachment 7) p l /pstp = l 1

1 5.1.6 Sample result Cm = pCi/cc ATTACHMENT 1 Page 4 of 8

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I l NO 5.1.7 Sample temperature T2 = *F 7, 5.1.8 Sample water density ratio (from Attachment 7)

! p2/pstp =

5.2 Decay correction of sample to time of reactor shutdown 5.2.1 Cc = Cm x e = pCi/cc

! 5.3 Parent-Daughter Correction Factor Fr

! NOTE For isotopes which must have a

! parent-daughter correction I factor applied, the parent

! isotopes are listed in Attach-

! ment 3. If no parent isotope

! is listed, then Fr=1. If 2

! isotopes are listed as parents, I then a correction factor must

! be calculated for each parent

! . (Fr and Fr B A

! 5.3.1 Fr g

! 5.3.1.1 Parent isotope A (from Attachment 3)

! 5.3.1.2 Parent isotope A decay constant (from Attach-

! ment 3 ) A A =

! 5.3.1.3 Parent isotcpe A 100% source inventory (from

! Attachment 3) Q* =

! 5.3.1.4 Daughter isotope 100% source inventory (from

! Attachment 3)Q =

! 5.3.1.5 Decay Branching Factor ( from Attachment 3 )KA *

! 5.3.1.6 / A__ 1 / -A A

~A ~"

! Fr A *KA(A A' 9 '

! 5.3.2 Fr Fr =0 if only one parent is listed in B

! Atkac(hment 3)

! 5.3.2.1 Parent isotope B (from Attachment 3)

! 5.3.2.2 Parent isotopo B decay constant (from Attach-

! ment 3)A B

• ATTACHMENT 1 Page 5 of 8 ,

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'I t 5.3.2.3 Parent isotope B 100% source inventory (from ~,

! Attachment 3)Qg=

! 5.3.2.4 Decay' Branching Factor (from Attachment 3)KB t

! 5.3.2.5 _'. ( -AB t -Ati

! FrB OB * ~* *

• b A ~ ^B '

I 5.3.3 -At

! Fr = 9o*

! Q*e + FrA + FrB

! 5.3.4 Corrected sample activity

=C pCi/cc

! C F c x Fr =

! 5.4 Temperature correction of sample

! 5.4.1 pt/pstp C=CF'X P2/pstp = pCi/cc

! 5.5 Containment Sump Activity A(CS) 4

! 5.5.1 A(CS) = V x C x 2.83 x 10 Ci 6.0 CONTAINMENT ATMOSPHERE ACTIVITY 6.1 Sample Data 6.1.1 Time and date of containment atmosphere sample

! 6.1.2 Time since shutdown t = (hours) 6.1.3 Containment atmosphere temperature T1 = F 6.1.4 Containment atmosphere pressure Pl = psia 6.1.5 Sample result Cm = pCi/cc 6.1.6 Sample temperature T2 = F 6.1.7 Sample pressure P2 = psia l 6.2 Decay correction of sample to time of reactor shutdown ATTACHMENT 1 Page 6 of 8

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! 6.3 Parent-Daughter Correction Factor Fr

! NOTE For isotopes which must have a

! parent-daughter correction

! factor applied, the parent

! isotopes are listed in Attach-

! ment 3. If no parent isotope

! is listed, then Fr=1. If 2

! isotopes are listed as parents,

! then a correction factor must

! be calculated for each parent I (FrA and Fr B)*

I 6.3.1 Fr A

! 6.3.1.1 Parent isotope A ( from Attachment 3 )

! 6.3.1.2 Parent isotope A decay constant (from Attach-

! ment.3)A A *

! 6.3.1.3 Parent isotope A 100% source inventory (from

! Attachment 3) Q =

! 6.3.1.4 Daughter isotope 100% source inventory (from

! Attachment 3 )Q* =

! 6.3.1.5 Decay Branching Factor (from Attachment 3)K

• A

! 6.3.1.6 / A__ [ -AA t -At

! Fr A

• K A kA

-A A } Ok k "

1. ~* / *

! 6.3.2 Fr '

=0 if only one parent is listed in

! Atkac,Fr B hment 3)

! 6.3.2.1 Parent isotope B ( from Attachment 3 )

! 6.3.2.2 Parent isotope B decay constant ( from Attach-

! ment 3)A B

! 6.3.2.3 Parent isotope B 100% source inventory ( from

! Attachment 3)Qg=

! 6.3.2.4 Decay Branching Factor (from Attachment 3)K

• B

! 6.3.2.5 A__

I

/ -ABt -At

! Fr ^ OB " ~*

• B B ~^B4 /

ATTACHMENT 1 Page 7 of 8

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! 6.3.3 -At .

i Fr = Q.e I

Q*-At e + FrA + FrB

! 6.3.4 Corrected sample activity 1 C p =C c

x Fr = mci /cc t 6.4 Temperature and pressure correction of sample

! 6.4.1 P

-1 x (T2 + 460) mci /cc C=C p x Pg x (Ty + 460) =

! 6.5 Containment Atmosphere Activity A(CA)

! 6.5.1 A(CA) = C x 7.075 x 104 = Ci 7.0 TOTAL ACTIVITY A 7.1 A = A(RC) + A(CS) + A(CA) = Ci 8.0 INVENTORY AVAILABLE FOR RELEASE 8.1 Uncorrected inventory (from Attachment 3)

! Q* = Ci 8.2- Power Correction Factor (from section 3)

PCF =

! 8.3 Corrected inventory Q* = PCF x Q = Ci c

9.0 PERCENTAGE OF INVENTORY RELEASED

! 9.1 Percentage of inventory released = A x 100% =  %

QC 10.0 ACTIVITY RATIO 10.1 If the isotope is a noble gas, complete 10.2.

If the isotope is an isotope of iodine, com-plete 10.3. Otherwise don' t complete this section.

10.2 Noble gas ratio = A/A(Xe-133) =

! 10.3 Iodine ratio = A/A(I-131) =

ATTACHMENT 1 Page 8 of 8

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. . m POWER HISTORY  ?.

1. 30-day power history I Days Before Shutdown Average Power (%)

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 15 17 18 19 20 21 22 23 24 25 26 27 28 29 30

! 30-day average power

2. Total number of days of operation D=

3. EFPD =

4. Average power during entire period of operation

! P = EFPD x 100% =

D ATTACHMENT 2 Page 1 of 1

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NUCLIDF T\ 1 Q" (Curies) PARFNT

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, ,[ M) 1-135 6.68h .l04h' '-l.8E8 . g:-

_g CS-134 2y 3.96E-5h 2.3E7 FUEL - -  ; ,

CS-137 10V 2.64E-6h I.lE7 OVERHEAT

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DAMAGE RATIO READINGS (OF)

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