ML20247H043

Revised Pages to Reactor Vessel Surveillance Capsule Z Analysis Rept

ML20247H043
Person / Time
Site:	Catawba
Issue date:	09/13/1989
From:	WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20247G950	List: ML20247G944 ML20247H043 ML20247H054
References
WCAP-11941-ERR, NUDOCS 8909190199
Download: ML20247H043 (26)

Text

_ _ _ _ _ _ _ _ _ _ _ _ - _

c.

~*

the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and therefore tend to reinforce any pressure stresses present. These thermal stresses are dependent on both the rate of heatup and the time (or coolant temperature) along the heatup ramp.

Since the thermal stresses at the outside are tensile and increase with increasing heatup rates, each heatup rate must be analyzed on an individual basis.

Folloaing the generation of pressure-temperature curves for both the steady-state and. finite heatup rate situations, the final limit curves are produced-by constructing a composite curve based on a point-by point comparison of the steady-state and finite heatup rate data. At any given temperature, the allowable pressure is taken to be the lesser of the three values taken from the curves under consideration.

The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist wherein, over the course of the heatup ramp, the controlling condition switches from the inside to the outside, and the pressure limit must at all times be based on analysis of the most critical criterion.

Finally, the 1983 Amendment to 10CFR50IA~#3 has a rule which addresses the metal temperature of the closure head flange and vessel flange regions.

This rule states that the metal temperature of the closure flange regions must exceed the material RT by at least 120'F for normal operation when the NDT pressure exceeds 20 percent of the preservice hydrostatic test pressure.

Table A-1 indicates that the limiting RTNDT of 10*F occurs in the head flange of Catawba Unit 2, so the minimum allowable temperature of this region is 130*F at pressures greater than 621 psig.

These limits are less restrictive than the limits shown on figures A-2, A-3, A-5, and A-6.

4.0 HEATUP AND C00LDOWN LIMIT CURVES Limit curves for normal heatup and cooldown of the primary Reactor Coolant System have been calculated using the methods discussed in section 3.

8909190199 890913 PDR ADOCK 05000413 P

FDC hh 'h

+-

2 To calculate ART at any depth (e.g., at 1/4T or 3/4T), the following NDT l

formula must first be used to attenuate the fluence at the specific depth.

l I

f(depth x)

• Isurface '

where x (in inches) is the depth into the vessel wall measu ed from the vessel inner (wetted) surface.

The resultant fluence is ther, put,to equation (4) to calculate the ART at the specific depth.

NDT CF (*F) is the chemistry factor, a function of cooper and nickel content. CF is taken from reference A-1.

Peak fluence is at the 25' vessel azimuth.

At this point the fluences are 18 2

19 2

9.52 x 10 n/cm and 3.05 x 10 n/cm for 10 and 32 EFPYs respectively. ART calculation were made for 10 and 32 EFPYs.

The limiting material were found to be the intermediate shell plate B8605-2.

For the limiting Vecsel Material, the chemistry factor is 44.0, based on reference (A-1). From equation (4), the ART at the inner surface is NDT equal to 44*F and 57'F for 10 EFPY and 32 EFPY respectively. Regulatory Guide 1.99 revision 2 provides formula and rules for establishing margin-

^

2

,,2 (6)

Margin = 2 o y l

Since the initial RT value for the vessel beltline plate is measured, the NDT temperature o is taken as 0*F.

The standard deviation c is taken as 17"F(A-1) g As a result, the margin is 2 / 0 + 17 = 34*F.

3 surface and margin, into Substituting the obtained values for ARTNDT Equation (3) gius the adjusted reierence temperature (ARI) for the inside surfste:

ART = 33 + 34 + 44 = 111*F for 10 EFPY ART = 33 + 34 + 57 = 124*F for 32 EFPY now=me io A-7 l

j

(-,

'Using the vessel thickness of 8.625 inches at the beltline, equation (3), (4),

i-and (5) are used to. calculate the ART at the 1/4 and 3/4 thickness locations.

These are:

1/4 T, 10 EFPY, ART = 104*F 3/4 T, 10 EFPY, ART = 92*F 1/4 T, 32 EFPY, ART = 118'F 3/4 T, 32 EFPY, ART = 106*F The above analysis was used to develop the Catawba Unit 2 heatup and cooldown curves shown in figures A-2 thru A-7.

nowosase in A-8

[

>i

.i.

I o.

MATERIAL PROPERTY BASIS CONTROLLING MATERIAL:

INTERMEDIATE SHELL PLATE B8605-2 COPPER CONTENT:

.07 WT %

NICKEL CONTENT:

.61 WT %

INITIAL RTNDT:

33 F RT AFTER 10 EFPY:

1/4T, 104*F NDT 3/4T, 92*F 2500 m

, m I

r r

i i

Leak Test J

2250 Limit

/

)

i f

f I

1 I

2000

)

I I

I

{

'750 Unacceptable t

l

^

Operation

/

/

1 I

G_ 1500 i

g,

/

/

[1250 Heatup Rates

/

Up To

/

/

l a

e 60*F/Hr j

j g

+4 n.

1000 ll 2

2 4

i h

/

i i

j v

75e Is i<

j

/

Criticality Linit Sased on

j l

i 500 Inservice Hydrostatic Test l

l Temo. (235 F)

, p' !

+

. a..., -4..

gg g

Acceptable r d UD Te

{'

Operation

.....E ii '.

i i i i i lii !

g i

0 50 100 150 200 250 300 350 400 450 Sc:

INDICATED TEMPERATURE (DEC.f) 1 CONIAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Figure A-2.

Catawba Unit 2 Reactor Coolant System Heatup Limitations Applicable for Heatup Rates up to 60*F/HR for the Service Period up to 10 EFPY m.am

A-10

7

~

I-MATERIAL PROPERTY BASIS

. CONTROLLING MATERIAL:

INTERMEDIATE SHELL PLATE Bfl605-2 T

COPPER CONTENT:

.07 WT %

-NICKEL CONTENT:

.61 WT %

INITIAL RTNDT:

33'F RT AFTER 10 EFPY:

1/4T, 104*F NDT 3/4T, 92*F 2500 m

i,y ll l

/

/

/

I i

2250 l

Leak Test l

Limit i

i 1

[

T 2000 l

l 1

1 I

i 1750 Unacceptable-Operation _

/

/

7 1500 j

j I

I L-w I

I I

l w 1250 l

5 Neatup Rates

/

/

-i Up To

{3,co 100 *F/Hr r

r j

1 750

/

Criticality Limit Based on e

Inservice 500 Hydrostatic,iest Temp. (235 F) for the Service i

250 i

Acceptable Period Uo l

Operation 7 w eenv J

lll

!!ililli;;;;lll l

!l l

,0 50 100 150 200 250 300 350 600 650 500 INDic. FED TEMPERATURE (DEG.F) 1 CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS 1

Figure A-3.

Catawba Linit 2 Reactor Coolant System Heatup Limitations I

Applicable for Heatup Rates up to 100*F/HR for the Service Period up to 10 EFPY am. ame io A-11

'y n.

'8

.E <

gt' L

MATERIAL PROPERTY BASIS CONTROLLING' MATERIAL:

INTERMEDIATE SHELL PLATE BB605-2 COPPER CONTENT:

.07 WT %

NICXEL CONTENTi

.61 WT %

INITIAL RTNDT:

33*F

.RTNDT. AFTER 10_EFPY:- 1/4T, 104*F 3/4T, 92'F 2500 i

I I

2250 I

2000 f

J I

(

1750 I

'G 1500 A

Unacceptable

/

S.

Operation i

g1250

/

51000 o

__,CColdowel Rates

[

- : *F/Hr Acceptable j

20; 3

Operation v

75o 2

c 0

40 ' "

500 60 $

_100 250 i

a s

1 I

• ]

~

ji I

..l,,

l o!-

i

.ini s i 1.

,, 1

,, i i,

t,,,,

O 50 100 150 200 250 300 350 400 450 500 IN0icATED TEMPERATURE (DEC.r) i p

CONTAINS NO MARGIN FOR FOSSIBLE INSTRUMENT ERRORS L

Figure A-4.

Catawba Unit 2 Reactor Coolant System Cooldown Limitations Applicable for Cooldown Rates up to 100*F/HR for the Service i

Period up to 10 EFPY newo o... in A-12

6 J

MATERIAL PROPERTY BASIS i

CONTROLLING MATERIAL:

INTERMEDIATE SHELL PLATE BB605-2

'CDPPER CONTENT:

.07 WT %

NICKEL CONTENT:

.61 WT %

INITIAL RTNDT:

33*F RT AFTER 32 EFPY:

1/4T, 118*F NDT 3/4T, 106*F 2500 k

l l

l t

2250 1

Leak Test i

Limit

/

/

/

2000 1

1 I

I

/

/

1750

[

- Unacceptable r

i Operation y 1500

/

/

i

/

/

[1250 Heatup Rates l

i f

Up To e

i 60 'F/Hr

/

/

w t 1000 l

l l

3

/

i 2'

750

/

Criticality f-Linit Based on Inservice 2

500 Hydrosta tic i

Test Temo.

l Acceptable (260 F) for 250 Operation the Service i

ceriod Up i

l l

to 32 EFPV j

0 J

O 50 100 150 200 250 300 350 600 450 500 levo tCAf t0 f tWPERATURE (DEC.r)

CMTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Figure A-5.

Catawba Unit 2 Reactor Coolant System Heatup Limitations Applicable for Heatup Rates up to 60*F/HR for the Service Period up to 32 EFPY m.ause in A-13

tf 4

MATERIAL PROPERTY BASIS CONTROLLING MATERIAL:

INTERMEDIATE SHELL PLATE B8605-2 COPPER CONTENT:

.07 WT %

NICKEL CONTENT:

.61 WT %

INITIAL RTNDT:

33*F RT AFTER 32 EFPY:

1/4T, 118'F NDT 3/4T, 106*F 2500 m i um,j_i i i i f

,iiiiiii,,i, I I I I I I I i

j f

j I

f f

2250 Leak Test i

i Limit l

l I

I I

2000 I

I

?

r 1750 i

i i

Unacceptable

/

/

Operation

/

/

3 1500 i

l l

t

- w 1250 3eatup Rates l

/

/

Up.To j

g 100*F/Hr

't 1000

.a w

~.

/

y 750 e

i Criticalit:i ! init Based on Intervice e

'a Hydrostatic Test 500 Terrp (250*F) for the Service 'eriot-250 up to 32 EFFr Acceptable Operation jjlji,ii,jiii ifffffffre,,,,,

0 0

50-100 150 200 250 300 350 400 450 500 l

IwolcATED TruptnA7ctt (Dtc.r) i CONTAINS NO MARGIN FOR POSSIBLE INSTRUMENT ERRORS Figure A-6.

Catawba Unit 2 Reactor Coolant System Heatup Limitations Applicable for Heatup Rates up to 100*F/HR for the Service Period up to 32 EFPY 32C?scD6048910 A *d

MATERIAL PROPERTY BASIS L

CONTROLLING MATERIAL:

INTERMEDIATE SHELL PLATE B8605-2 L,

COPPER CONTENT:

.07 WT %

NICKEL-CONTENT:

.61 WT %

INITIAL RTNDT:

33*F RT AFTER 32 EFPY:

1/4T, 118'F NDT 3/4T, 106*F

'2500 m i 2250 I

2000 r

i 1750

/

l l

7 1500

/

~

r b

l

.g.1250 f

a Unacceptable

/

Operation

/

Acceptable

[.,gon ::

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(

Operation

Cooldown O. 750 ::: Rates a

--- *F/H r

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~

0 m

500 20 7/

40

_ /

60 i

250

.100 i !

l 0

50 100 150 200 250 300 350 400 450 500 sese cATED TEMPERAfunt (DEC.r) 1 CONTAINS NO MARGIN FOR POSSISLE INSTRUMENT ERRORS Figure A-7.

Catawba Unit 2 Reactor Coolant System Cooldown Limitations Applicable for Cooldown Rates up to 100*F/HR for the Service Period up to 32 EFPY w.ume in A-15

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