ML18348A329

Transmitting Supplement 1 to Palisades, Core I ECCS Performance Results

ML18348A329
Person / Time
Site:	Palisades  (DPR-020)
Issue date:	07/09/1975
From:	Strimaitis J C-E Power Systems, Consumers Power Co
To:	Purple R Office of Nuclear Reactor Regulation
References
P-CE-4033
Download: ML18348A329 (15)

Text

Tel. 203/688-1911 Telex: 99297

_C-E Power Systems Combustion Engineering, Inc.

1000 Prospect Hill Road Windsor, Connecticut 06095 REGULAT~I~Y ~*oc.:~r:T FILE COPY ll!!!!m!!!!!POWER Iii& SYSTEMS Division of Reactor Licensing July 9, 1975 P-CE-4033 Docket,. 50-255 U.S. Nuclear Regulatory Commission Attention:

Mr. R. A. Purple Washington, p.c.

20555

Subject:

Palisades Plant ECCS Analysis, Docket 50-255, License DPR-20

Reference:

(a) Letter from Consumers Power Company, Mr.R.B. *Sewell to NRC-DRL, Mr. R.A. Purple, dated July 9, 1975, same subject

Enclosure:

(1) Palisades, Core I ECCS Performance Results, Supplement 1.

Gentlemen:

At the request of Consumers Power Company, Enclosure (1) is forwarded directly to the Division of Reactor Licensing, as discussed in reference (a).

This Supplement to the Palisades Core I ECCS Performance Results should be read in conjunction with reference (a).

JVS:RSB:nm Enclosure (40 copies) cc:

R. B. Sewell - CPC Very

~J. V. Strimaitis Project Manager

• Palisades Plant

'7441

~ -*"'.

Palisades, Core I ECCS Performance Results Supplement 1 It has recently been determined(l) that the containment heat sink data used in the Palisades FAC ECCS performance analysis may not have been conservatively calculated. This data was used in the break spectrum analysis of this report.

In order to demonstrate that the allowable peak LHGR determined by this analysis (ll.3 kw/ft) is valid despite the heat.

sink data uncertainties, a set of conservative containment physical data was compiled as per agreement with the Consumers Power Company and the NRC Staff(2). *Using this containment model, the worst break (l~O x DES/PD) hot rod transient was recomputed using the approved CE large break evaluation.

model(

3 )~ Although some change occurred in the reflood perio& clad temperature transient, the ~eak clad temperature (2198°F) occurred during.

the blowdown period. Therefore, there was no impact of the change in containment pressure on the allowable peak LH.GR.

The containment physical parameters used for. this analysis are shown in.

Table S-1.l. The following conservatisms have been included:

1.

Net free volume has been increased to 105% of the FSAR value.

2.

The. containment building and sump wall surface areas have been increased to 105% of the FSAR values~

3.

The initial relative humidity in the containment atmosphere has been assumed to be 100%. *

4.

The initial containment atmosphere temperature and pressure have been selected. at the minimum anticipated values.

5.

The.. containment spray flow rates have been maximized at the lowest head tested (247 ft.). The containment spray pumps are at an elevation. of 570 ft. and the spray nozzles are at approximately.

760 ft. The differential elevation is 190 ft. It is cons1dered reasonable, therefore, that the flow rate:.*data at the minimum head tested is the maximum flow which could be expected from the containment spray system.

6.

The containment fan cooler heat removal rate has been based on the minimum service water temperature of 30°F.

7.. The internal passive heat sink information has been derived from Branch Technical Position CSB 6-1.

In addition to the above conservatisms, the actuation time for the active heat removal systems was selected at 0.0 seconds.

The results of this analysis, foi the 1.0 x DES/PD break, are presented in figures as designated in Table S-1.2.

The effect of the different containment physical models can be assessed by comparison of figures beginning with the designation S-1 and those beginning with the designation II.9 in this report. It is noticed that the contajnment pressure is lower using the.conservative physical data model.

This lower containment pressure*

had the fa 11 owing impact:.

1. The peak clad temperature was unaffected since it occurred during the blowdown period.

2.

The maximum change in the reflood period clad temperature was.from 1996 to.2055°F which occurred in a non-limiting hot.rod node.

3.

The peak local clad oxidation for the 1.0 x DES/PD break increased from 4.98% to 6.10%;

In the break spectrum analysis of.this report, the highest local clad oxidation was 5.74% which occurred for the 0.6 x DEG/PD break. Therefore, using the.lower containment pressure, the peak local clad oxidation for the 0.6 x DEG/PD break may be expected to increase *by ~l.. 1% but would be far below the 17% limit of 10 CFR 50.46.

Si~ilarly, the highest core-wide clad oxidation.

can be expected to increase slightly from the maximum value of 0.53%

reported for.. the 0.6 x DEG/PD, but would be well below the 1.0% limit.

Therefore, it is concluded that a very conservative treatment of the*

containment physical rriode1 does not alter the allowable peak LHGR (11.3 kw/ft) as determined by the break spectrum analysis presented in this report~

.:i.*

~* '..

- ~:.

-~*..

References:

l. Letter from R. B. Sewell (Consumers Power.Company) to R. A. Purple (NRC}

RE:

Palisades Plant Containment Building Data, Docket 50-255, June 16, 1975~*

2.

Telephon*e Communication Between J. Longo, Jr. (CE) and C. H. Berlinger (NRC) RE:

Containment Physical Data Appropriate for ECCS Performance Evaluation of Palisades Plant, July 2-3, 1975.

3.

CENPD-132, 11Calculative Methods for the CE Large Break LOCA Evaluatiori Model", August, 1974 (Proprietary)!

.CENPD-132, Supplement 1, *"Updated Calculative Methods for the CE Large*

Break LOCA Evaluation Model", December, 1974 (Proprietary)~

./

Table S-1.l Palisades Core I Containment Physical Parameters Net Free Volume (105% of Nominal)

Ini ti ati on Time for:

Spray Fl ow.

Fan Coolers..

. Containment Initial Conditions:-

• Temperature (lowest anticipated operating temperature)

Pressure (lowe~t anticipated operating temperature)

Relative Humidity._

Conta.i nment Spray Water:

Temperature Fl ow Rate' (Total, 2 pumps)

Expected run-out flow)

Fan Air Cooler Capacity (per cooler)*

Based on expected minimum service water, 0

temperature of 30 F.

• Vapor Temperature (°F) 30 104 184 244 283 l. 722 x 106 ft3 0.0 seconds*

0.0 seconds

-0.2 psig.

100%*

0 40 F.

4840 gpm Capa~ity (BTU/sec.)

0 3,850 19,470 33,000 44,775

Table S-1.l(Cont'd}

Heat Sinks:

External Surface Area (105% of Nominal}

Containment Dome Containment Dome Base Containment Wa 11 Containment Base Slab*

Internal Surface Areas:

The internal heat sink surface areas are based on NRC Branch Technical Position CSB.6-1 Internal Heat Sink Area of Steel (3/8 11 plate) 6 3

Based on Net Free Volume of 1.72 x 10 *ft Internal Heat Sink Area of Concrete, (l 1 thick slab}

For External Walls Thermal Conducitvity (Maximum}

and

• Volumetric Heat Capacity (Maximum}*

7,634 square f ee1; 11,550 square feet 57,120 square feet 8,640 square feet*

360,000 ft2 160,000 ft2 Thermal Conductivity (BTU/hr-ft-OF}

Specific Heat (BTU/lbm-°F}

Volumetric Heat Capacity *

{BTU/ft3..;0F} *.

Organic Protective Coatings Inorganic Protective Coatings Stainless Steel Liner Plate~

Carbon Steel Liner Plate*

Structural Concrete 0.3 2

11 28 0.9*

0.12 0.12 0.23 62

. 62 59 59 33

"\\*~...

Table S-1.1 {Cont'd).

For Internal Walls:

Heat sink thermophysical properties of NRC Branch Technical Position CSB 6-1 are used.

Thermal Conductivity

{BTU/hr-ft-Of)

Concrete 0.92 Steel 27.0 Heat Transfer Coefficients:.

Specific Heat

{BTU/lbm-°F)

o. 156

0. 12

a. Containment atmosphere to sump:

500 BTU/hr-ft2-°F b:

Sump* to base slab:

20 BTU/hr-ft2-°F Volumetric Heat Capacity.

{BTU/ft3-0 F) 22.6 58.8.

c. Containment structure to enclosure building atmosphere:

10.0 BTU/hr-ft2-°F *

~~;:.:.._.~_...:::7."1\\?.r*~'-...::;..,.;~~:,::.;,..,,;;,~ {"*" * ',;,*L....,,,.,..... ;,, * ** =-c b 1 ;;.;d'* *.-a'*1Af.y.:.:: *.*.:.. _:.... ~~:..:;~

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Table S-1.2 Variabl.es Plotted as a Function of Time for the l~O x DES/PD Break Variable Containment Pressure Mass Added to Core During Reflood Peak Clad Temperature Local Clad Oxiation Heat Transfe~ Coefficient During Reflood.

Containment Temperature*

Sump Temperature /

Figure Designation S-1.l-F S~ l. 1-G.

S-1. 1-H

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FIGURE S-1.: 1-F PALISADES CORE 1 REANALYSIS 1.0 x DOUBLE ENDED SLOT BREAK IN PUMP DISCHARGE LEG CONTAINMENT PRESSURE 60aOOQ I

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FIGURE S-1.!1-G:

I PALISADE:S CORE 1 REANALYSIS i

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FIGURE S-1.1-0 PALISADES CORE I REANALYSIS

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I FIGURE S-1.* l-R PALISADES CORE I REANALYSIS I. 0 x DOUBLE ENDED SLOT BREAK IN PUMP DISCHARGE LEG HOT SPOT HEAT TRANSFER COEFFICIENT DURING REFLOOD

-* -1 U..1 o:

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FIGURE S~l.il~T' 1

PALISADES CORE 1 REANALYSIS

~ 1.0 x DOUBLE ENDED SLOT BREAK IN PUMP DISCHARGE LEG I. JI.

SU MP TEMP ERA TU RE

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