ML20071M647

Estimation of Fuel Failure,(Interim)

ML20071M647
Person / Time
Site:	Waterford
Issue date:	08/23/1982
From:	Mcgahal J LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20071M640	List: ML20071M647 W3P82-2579, Forwards Technical Procedure, Estimation of Fuel Failure (Interim), Per Ser,Incorporating Recommendations for Interim Procedures Contained in Referenced Document Re post-accident Estimate of Core Damage
References
NE-5-301, NUDOCS 8209270195
Download: ML20071M647 (16)

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WATERFORD 3 SES ~'

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b l OUISIANA POWER & LIGHT Eid s*vsYdU NE-5-301 POM VOLUME 14 REVISICJ 0 POM SECTION 5 APPROVAL DATE: August 23, 1982 EFFECTIVE DATE:

+e TECHNICAL PROCEDURE ESTIMATION OF FUEL FAILURE (INTERIM) l (

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RECEIVED NUCLEAR RECOftDG SEP 2 1982 ILN: -

PORC Meeting No. b 'b4 Reviewed: h -

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Technicci Proosduro NE-5-301 Estimation of Fuel Failure Revision 0 (Interim) '-

TABLE OF~ CONTENTS 1.0 PURPOSE

2.0 REFERENCES

3.0 DEFINITIONS s , .

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4.0 RESPONSIBILITIES -

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5.0 PREREQUISITES 6.0 PRECAUTIONS AND LIMITATIONS 7.0 INITIAL CONDITIONS 8.0 MATERIAL AND TEST EQUIPMENT 9.0 ACCEPTANCE CRITERIA 10.0 PROCEDURE 11.0 SETPOINTS 12.0 ATTACHMENTS 12.1 Power Correction Factor (2 pages) 12.2 Temperature Correction Factor (1 page) 12.3 Decay Correction (1 page) 12.4 Percent Fuel Failure (5 Clad Damage) (3 pages) 12.5 Examples (2 pages) 13.0 COMMITMENTS AND REFERENCES LIST OF EFFECTIVE PAGES Title Revision 0 1-15 Revision 0 t

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Technicci Proccdure NE-5-301 Estimation of Fuel Failure Revision 0 (Interim) ,

1.0 PURPOSE This procedure provides an estimace of the extent of fuel failure.

The estimate is based on the I-131 concentration measured in the Reactor Coolant System (RCS).

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2.0 e REFEREN CES .

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2.1 Waterford 3 FSAR, Chapters 11~and'12 '

2.2 Reactor Safety Study, An Assessment of Accident Risks in U.S. Com-mercial Nuclear Power Plants, WASH-1400, Appendix '.'II, pp. VII-13, 14, U.S. Nuclear Regulatory Commission (Oct. 1975) 2.3 American Nuclear Society, American National Standard Source Term Specification, ANSI N237-1976 2.4 L.L. Bonzon and N.A. Lurie, Best Estimate LOCA Radiation Signature, Part II, pp. 9-13, NUREG/CR-1237 (Jan. 1980) 2.5 A.P. Malinauskas, R. A. Lorenz, H. A11recht, and H. Wild, LWR Source Terms for Loss-of-Coolant and Core Melt Accident, Proceedings of the CSNI Specialists Meeting on Nuclear Aerosols in Reactor Safety, held at Gatlinburg, Tenn., April 15-17, 1980, NUREG/CR-1724, pp. 38, 39 2.6 Estimate of Failed Fuel Based on I-131 Concentration, Procedure AP/0/A-5500, Duke Power Company 2.7 Determination of Ertent of Core Damage, Procedure 7 8.000.15, Rev . O ,

The Detroit Edison Company 1

.s 3.0 DEFINITIONS 3.1 Fuel Failure - As used in this procedure, fuel failure may range from minor clad damage (resulting in I-131 gap inventory release to RCS) to severe fuel melting (resulting in major portions of the core I-131 inventory being released to the RCS).  ;

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. Tochniocl Proccduro - ' '.' NE-5-301 Estimation of Fuel Failure Revision 0 (Interim) 3.2 Iodine Spiking - A condition where larger than normal amounts of iodine are released from the fuel to the RCS upon a significant power change, E shutdown, or RCS depressurization.

4.0 RES PONS IR TLTTT ER 4.1 Chemistry ' ' -

l Chemistry personnel are responsible for obtaining an RCS sample and ' -

l l analyzing it for I-131 concentration, using the gamma spectrometer.

4.2 Nuclear Operations Supervisor (NOS)' ' ~

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The NOS is responsible for requesting an RCS sample analysis in ac- '

cident (or other) conditions which indicate the possibility of fuel-i failure.

4.3 Nuclear Engineering (NE)

! Nuclear Engineering is responsible for maintaining this procedure.

NE is also responsible for evaluating the results of this procedure.

5.0 PREREQUISITES An RCS sample has been drhwn and analyzed with the gamma spectrometer for I-131 concentration.

6.0 PRECAUTIONS AND LIMITATIONS 6.1 The amount of fuel failure predicted by this procedure is only an estimate.

6.2 The equations and graph contained in this procedure assume equilibrium full power core iodine concentrations. If this procedure is performed during times of reduced power or near the time of a significant power change, the core iodine inventory must be adjusted accordingly with Attachment 12.1, Power Correction Factor, P 1 .

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NE-5-301 Estimation of Fuel Failure Revision 0 (Interim) 6.3 All values are normalized to normal RCS temperature and pressure.

To correct for other RCS temperatures or other RCS sample temperatures use Attachment 12.2, Temperature, Correction Factor, T.

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6.4 Iodine spiking may occur af ter a shutdown or significant power change. The spike generally peaks during the period _4 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> -

after the power change. I-131 concentrations can increase by a factor of 2 to 25 times above the equilibrium levels during these spikes, although an increase greater than a factor of 10 is unusual and would be seen only on a shutdown. Increases by E factor of 2 or 3 are typical for a significant power change (i.e., 1005 to 505 power). Do not interpret this temporary change as fuel failure if there are no other indications of core problems. Other indications which may help identify fuel failures are: indications of inadequate core cooling, loose parts indications, high core-exit thermocouple readings.

6.5 Chemistry samples and analyses shou)4 be performed as rapidly as possible after fuel failure is suspected. If more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> has elapsed, the sample should be corrected for decay to the time at which fuel failure is suspected to have occurred.

7.0 INITTA1. CONDITIONS 7.1 Accident (or other) conditions exist which cause fuel failure to be suspected.

72 The Process Radiation Monitor indicates that RCS gross gamma activity is high.

8.0 MATERT AT. AND TEST EOUIPMENT NONE 4

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NE-5-301 Estimation of Fuel Failure Revision 0 l (Interim) 9.0 ACCEPTANCE CRITERTA NONE 10.0 PROCEDURE 10.1 Obtain the RCS I-131 concentration from Chemistry and Environmental personnel. . _ , ..

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10.2 Calculate the Power Correction Factor, P g , using Attachment 12.1 if necessary.

10.3 Calculate the Temperature Correction Factor, T g, using Attachment 12.2 if necessary.

10.4 Correct the RCS I-131 concentration ~ for decay to the time of reactor shutdown or suspected fuel fri' A(to), using Attachment 12.3 if necessary.

10.5 Calculate the corrected RCS I-131 concentration from the sample by:

Ic =IxPgxT3 where: Ic = corrected RCS I-131 concentration g I = measured RCS I-131 concentration (corrected for decay, A(to), if necessary)

Pg = power correction factor T g = temperature correction factor 10.6 Use the result of step 10.5 to evaluate the lower limit, the upper limit and the best estimate'of the amount of fuel failure, using Attachment 12.4.

10 7 If the results from step 10.6 place the amount of fuel failure in the region where clad damage and fuel melting may both exist, request that Chemistry personnel analyze the sample for the presence of isotopes of Sr, Ba or La (especially Sr-92 and La-140).

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/ 'Tochnicc1 Procedura NE-5-301 Estimation of Fuel Failure Revision 0 (Interim) 10.8 If the above isotopes are found in greater than normal amounts (based on previous isotopic analyses of the same cycle'), bias the estimate of fuel failure toward fuel melting.

11.0 SETPOISTS NONE

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12.0 ATT4CHMENTS .

12.1 Power Correction Factor 12.2 Temperature Correction Factor 12.3 Decay Correction 12.4 Percent Fuel Failure (5 Clad Damage.)

12.5 Examples 13.0 COMMITMENTS AND REFERENCES I

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• POWER CORRECTION FACTOR Case I To correct the iodine inventory if fuel failure is suspected to have oc-curred during periods of operation at any power level (except 05) where the power level has not changed greater than 410% within the last 40 days (approximately 5 half-lives of I-131), use the following equation:

P 100 1 = % Full Power at time of fuel failure Example: The plant has been at 755 full power for the last 30 days when fuel failurc is suspected. Therefore: -

, P g=1pg=1333 ,

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case TI j To correct the iodine inventory if fuel failure is suspected to have oc-I curred at times other than those in Case I above, use the following i equation:

P 3

= 100

[j Pj(1 - e* * *3) e' 0 * (

,, where: PJ = steady reactor power in period j (5) j tj = duration of period j (days) l l tj=timebetweentheendofperiodjandtime

! of reactor shutdown or suspected fuel

! failure (days) i n NOTE

[tj=40 days;j=1,2,...,n

. j:1 40 days is approximately 5 half-lives of I-131, which gives sufficient accuracy.

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l NE-5-301 Revision 0 7 Attachment 12. 1 ( lof 2) l l

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Example: The plant was at 755 power for_22 days, 505 power for 17 days end 1005 power for 2 days when the reactor tripped and fuel failure was suspected to have occurred during the trip.

NOTE

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~_75(1 e-"W)(e-""20S) + so(1-e-***'2W)(e-* *= m)+1oo(1-e-""24)(e-a a aa) .

P g= 100 12.3919' + 32.3618 + 15.8358 P g=

• 100 = 1.6491 60.6373 3

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NE-5-301 Revision 0 ,

8 Attachment 12. 1 (2 or2 )

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TEMPERATURE CORRECTION FACTOR .

RCS Temp Primary Sample Temperatui e at time of sample ,

degrees F den ees F 3D SQ .1D.Q 100 0.996 0.998 1 150 0.983 0.985 0.987

! 200 0.966 0.968 0 970 i 250 0.945 0 947 0.949

! 300 0.921 0.923 0.924 I 0.894 0.895 0.897

350 400 0.862 0.864 0.865 l

450 0.827 0.828 0.830 i

1 500 0.7 87 0.788 0.790

! 550 0 739' O.740 0.741 1

560 0.728 0 729 0.731 l 0.718 0.719 570 0.717 580 0 706 0.708 0 708 590 0.693 0.694 0.695 l

I 600 0.680 0.681 0.683 i

Find the appropriate RCS temperature at the time of suspected fuel

, failure. Find the primary sample temperature. The intersection of the two numbers is the temperature correction factor, T g.

J NOTE Normal primary sample temperature is approximately 80 degrees F. Use this temperature if no other information is available.

NOTE If the RCS or sample temperature falls between the l

values listed above. little error will be intro-duced by using the closest value.

NE-5-301 Revision 0 9 Attachment 12.2 (l ofi )

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DECAY CORRECTION If less than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> have elapsed from the time of reactor shutdown (or from the time fuel failure is suspected to have occurred), failure to correct the sample for decay will introduce less than 55 error.

XI = A(tc) = A(ts) e *"***

where: t, = time of shutdown or suspected fuel failure ,

ts = time of sample analysis 4 t = tg - t, = time from shutdown or suspected fuel failure to sample analysis (days)L. ,

A(t,) = activity WCi/g) at t'. {~

A(ts) = measured sample activity ( Ci/g) ,

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DERIVITION OF EQUATIONS FOR GRAPH A7. ,3, = 8.46 x 10 Pgj Ci P = 3560 MWt

.L = 0.028 for I-131 7

Ay .j3; = 8.43 x 10 ci FSAR Table 12.2-1R A y.,3 =8.96x10ci=8.96x10%ci RCS Mass (FSAR Table 11.1-1) = 5.56 x 10 1b ,= 2.52 x 10's Equilibrium Full Power Core I-131 Inventory = 3 56 x 10'pci/g Best-Estimate Fission Product Release Fractions for I-131

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Lower Limit Nominal Upper Limit Lower Limit Nominal Upper Limit 0.001 0.017 0.20 0.492 0.883 0 983 Fuel Failure UL LCi/a) BE (J i/r) LL (mC1/r1 0.1% clad 3.56 x 10 6.05 x 10* 7.12 x 10' 1% clad 3.56 x 10* 6.05 x 10' 7.12 x 10*

10% clad 3.56 x 10' 6.05 x 10* 7 12 x 10' 2 #

100% clad 3 56 x 10 6.05 x 10' 7.12 x 10 1% melt 1 75 x 10' 3.15 x 10' 3.50 x 10'

! 10% melt 1 75 x 10 3.15 x 10' 3.50 x 10 100% melt 1.75 x 10' 3.15 x 10' 3.50 x 10

• The upper limit of the release (gap or meltdown) produces the lower limit of predicted fuel failure. The lower limit of release produces the upper limit of predicted fuel failure.

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NE-5-301 Revision 0 13 Attacnment 12.4 (3 of 3) l

n .-,.---~.d--,.-__. _-_,.y,.e.,,_.,,..,..---,..-,..n EXAMPLES I. The plant was at 755 power for 22 days, 50% power for 17 days, and 1005 power for 2 days when the reactor tripped due to an RCP trip.

Fuel failure is suspected to have occurred during the reactor trip.

Solution: These are the same conditions as in Attachment 12.1; therefore:

P3 = 1.6491

1. RCS sample reads 10 j C1/g I-131 -

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2. Pg = 1.6491

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3 Calculate T3 .

RCS temp = 550 degrees F (at time of sample)

Sample temp = 90 degrees T3 = 0.740

4. Decay correction is not necessary.

5. Calculate corrected I-131 concentration:

Ic = I x Pg xT 2

= (10jaCi/g)(1.6491)(0.740)

Ic = 12.20 j Ci/g

6. From Attachment 12.4:

LL 0.0165 clad damage BE 0.205% clad damage UL 3.500% clad damage NE-5-301 Revision 0 14 Attachment 12.5 ( 1 of 2 )

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II. The plant has L*an operating at 1005 power for the last 53 days when a pressurizer safety valve inadvertently opens. The reactor trips on low pressurizer pressure. Fuel damage is suspected as a result of the transjent. A chemistry sample is taken 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> af ter the ,

reactor trips.

Tj ,4 = 600 deg F I y.fy, = 350f 4ci/g Ts rk.= 80 deg. F

1. 350fu ci/g

2. Pg is not needed because the plant was at 1005 power for a long _

period and at the time of trip. ,

3. Find Tg from Attachment 12.2. .

4. Decay correction is not required.

5. Ic = I x Py x T3 = 350 x 1 x 0.680 Ic = 238,uci/g

6. From Attacnment 12.4:

LL 0.345 clad damage BE 4.005 clad damage UL 70.005 clad damage NE-5-301 Revision 0 15 Attachment 12.5 (2 or2 )

_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _