ML20005G112

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Proposed Tech Specs Re Pressure Temp Limits
ML20005G112
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 01/10/1990
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20005G108 List:
References
NUDOCS 9001180144
Download: ML20005G112 (26)
v • d • e


Text

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--ATTACHMENT 1 y'

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' Consumers' Power Company'.

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!?1 Big Rock Point Plant'

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Docket 50-155 t'

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.l PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES

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January 10, 1990

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i 9001180144 900110 i

.PDR ADOCK 05000155

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PDC 4 Pages i

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.:MI1289-0609A-BT01 m.

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(Contd) i (1) Operating Requirements j

l 1.

The average rate of vessel temperature change during normal heatup or cooldown should not exceed 100'F/h when averaged j

over a one-hour period.

1 2.

Control rod withdrawal _during power operation shall be such that the average rate-of-change of reactor power is less than

)

50 W per minute when power is less than 120 W, less than

[.

20 W per minute when power is between 120 MT ind200MT, and 2IO W.

t g

3.

Reactor vessel pressure shall be limited in accordance with j

5 Figures 4.1, (a), (b) and (c).

4.

The reactor shall not be made critical, with the exception of physic testing, at temperaturea below the criticality limit shown on Figures 4.1(b) and 4.1(c).

5.

The reactor water level shall not be permitted to decrease

~below the reactor vessel low water level set point at which reactor safety systems are actuated (Section 6.1.2) whenever fuel is in the reactor vessel. This requirement shall be considered a safety limit and decreases in reactor vessel water level below this set point shall be subject to the requirements of Section 10, Administrative Controls.

Subsection 6.7, " Safety Limit Violation."

4.1.2 Primary Coolant Recirculation System The primary coolant recirculation system shall consist of the reactor vessel, the steam drum, the reactor recirculation pumps, the interconnecting piping and valves, and the safety relief valves.

(a) Design Features Shall Be as Follows:

i l

Number of Recirculation Loops 2

Number of Recirculation Pumps per Loop 1

Approximate Internal Volume of 3830 System Excluding Reactor Core and Internals to Isolation Valves, Cubic Feet Approximate Volume of Coolant in 2689 System During 157 Mwt Operation.

l Cubic Feet Proposed MI1289-0609A-BT01

'i

'i Figure L.1(a) 1Ld SIG ROCK POINT NUCLEAR PLANT:

PRES 5URE TEMPERATURE LIMITS EFFECTIVE TO 18 EFFECTIVE FULL POWER YEARS FLANGE RTuor = 40'F HYDROSTATIC TEST CONDITION HYDROTEST TEMPERATURE: 1475 P54G 9 224'F 1525 P54G @ 229

  • F 1800 -

l 1700 -

1600 -

1500 -

[

i.

.1400 -

g 1300 -

O 1200 -

E u

1100 -

V 1000 -

900 -

E 800 -

l 700 -

b b

425 400 -

b-100 -

0 i

i 60 100 150 200 250 300 350 400 REACTOR VESSEL METAL TEMPERATURE,* F Proposed

-.... ~. -. - -.

i' * >

Figure L.1(b)

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,['

BIG ROCK POINT NUCLEAR M. ANT 8 PRES 5URE TEMPERATURE LIMITS EFFECTIVE TO 18 EFFECTNE i

FULL POWER YEARS FLANGE RTseof = 40'F COOLDOWN CONDmON 5000 UNES ARE NON4RmCAL CONDmON DASHED UNES ARE CRmCAL CONOmON 1500 -

1400 -

1 1

1300 -

fl i

\\

I l;

1200 -

p I

NON-CRmCAL

/

1100 -

UMmNG COOLDOWN g i

- ALL RATES

/

/

1 1000 -

/

/

/

t

/

900 -

/

/

I 000 -

/

CORE CRITICAL

/

UMmNG COOLDOWN

/

ALL RATES I

1 600 -

I b

_____a g_

5 i 100 -

l :

LOWER UMIT OF CRmCAUTY l

1 0

60 100 150 200 250 300 350 400 REACTOR VE5SEL METAL TEMPERATURE,'F Proposed

~

_ _ _. ~. _.. _.

1 Fdcure k.1(e) 1L3

)

\\

t.

BIG ROCK POINT NUCLEAR PLANT; j

PRES $URE TEMPERATURE LIMITS EFFECTIVE TO18 EFFECTIVE

)

FULL POWER YEARS PLANGE RTwor = 40*F HEATUP CONDmON 5000 LINES ARE NON-CRmCAL CONDmON DASHED UNES ARE CRmCAL CONDmON

/

1600 -

I l

I

,I 1500 -

I l

1M -

g

/

1300 -

NON-CRITICAL f

LIMmNG HEATUP f

ALL RATES f

1200 -

f 1

/

1100 -

/

/

4

/

1000 -

f

/

/

% CORE CRmCAL 900 -

/

/

UMITING HEATUP ALL RATES

(

300 -

I e

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6M -

b b

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_____m s

100 -

I LOWER UMIT OF CRITICAUTY I

t 0

60 100 150 200 250 300 350 400 REACTOR VESSEL METAL TEMPERATURE,* p Proposed

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( I 'i ATTACHMENT 2'

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Consumers Power Company Big Rock Point Plant Docket 50-155 N,

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-EVALUATION OF GENERIC LETTER 88-11 J-

- ON BIG ROCK POINT TEMPERATURE / PRESSURE LIMITATIONS o

January 10, 1990 L.

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20 Pages l

b MI1289-0609A-BT01 1;-

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$2

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BIG ROCK POINT NUCLEAR PLANT ga.NL-88-59-01 f

ausmaanM ENGINEERING ANALYSl5 WORK SHEET sheet I g 20 Title EVAWATION OF GENERIC LETTER 88-11 ON BIG ROCK POINT TDEERATURE-PRESSLTRE LIMITATIONS 1

l INITIATION AND REVIEW j

initiated Rev Method Check (@

Technically Rev'd Aev c,'i, n) ey Date 8

Description 8y Date O

Original issue

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REFERENCES:

1) Generic Letter 88-11
2) Reg Guide 1.99, Rev 2. May 1988
3) WCAP-97, September 1980
4) MTEB 5-2 5) 10CTR$0.61
6) Combustion Engineering Dwg. E-201-794-8
7) Meso, Jenk 41-77
8) Standard Review Plan 5.3.2
9) ASME Sect III. Appendix C
10) ASME Sect III Appendices. Table I-2.1
11) Strength of Materials 11. S. Timoshenko, 3rd Edition D. VanNostrand Company Inc., 1968 OBJECTIVE:

To assess the impact of Generic Letter 88-11 requirements on the pressure-temperature limitations of Big Rock Point.

ASSUMPTIONS:

1) Fluence at 18 ETPY is derived by staple ratio of data contained in Ref. 3 above.
2) Temperature T is vessel metal temperature taken froe L-thersocouples on reactor 0.D.

M11088-0531A-BT01 BRP 090 0221/88.

7 BIG ROCK POINT NUCLEAR PLANT EA.wt-es-9-on ENGINEERING ANALYSl5 CONTINUATICN SHEET sheet L of._29.

i se rmanns Rev# 0 l

assumaars passasas l

CALCULATIONS:

Per equation (1) of Generic 1,etter 88-11. the Adjusted Reference Temperature (ART) is the sus of the initial reference temperature E T, the change in reference temperature at any given time RT ET, and the statistical margin to accomodate scatter in experimental ART data. This is then expressed ast (EQ.1)

ART = INITIAL RTET + ARTE T + N'#8I" EQ.1 aust be evaluated for both weld metal and base metal (plate) of the reactor vessel.

Initial RT f r veld and base metals are given ET below.

We14:

Initial RT

= -56'F (Ref. 5)

[

ET Base Plate:

Initial RT

= +30*F (Ref. 4)

ET Flange Initial RT

= +40*F ET are derived by The margin (M) for both the initial and change of RTET the following formula o

seO-M11088-0531A-ST01 SAP 091 02/01/88

~.

BIG ROCK POINT NUCLEAR PLANT EA.E-88-59-01 sheet L-6f 2A.

I ENGINEERING ANALY515 CCNTINUATION SHEET nov # O sowsass sammans pasassa (54 2) a Margin = M = 2 @ ga,,g standard deviation for initial RT and i

Where o a gy g

i standard deviation for the change in RTg (ARTNDT o =

g The values for o and o are given below:

l g

g Welds o = 17'T g

o = 28'F g

Base Flater o = 17'T g

o = 17'F g

i ART is derived in both cases (weld & base plate) by:

l g

l l

(EQ.3)

ARTNDT " (

Where CF = Chemistry Tactor (Ref 2) 3 9 n/cm, E>1MeV) 8 f = fluence (10 CF is taken f rom Table 1 for veld metal and Table 2 for base metal.

Both tables are in Reference 2.

1 KIl088-0531A-BT01 l

SRP 001 02/0148 l

_.-... _.y

.,3 e

m" [$

BIG ROCK POINT NUCLEAR PLANT EA,n-as-n-

$heet ef:

ENGINEERING ANALY565 CONTINUATl8N $HEET

. Rev, 7 q

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)

I;

\\

Fivence f 'is calculated at the 1/4 'and 3/4 thickness locations of j

i the reacter vessel wall.

l i

i The attenuation of f tt. rough the vessel wall is derived by:

j l

1 1

(EQ.4) f, = f,,,g,,,

( e~'*)

(Ref. 2)-

t I

Where is the depth in inches from the wetted surf ace (Vessel ID) to the 1/4t & 3/4t locations.

The data from Big Rock Point to support the above equations is as f0110wst

DATA, Ddtial RT

= -56'T (Weld)

ET Initial RT,7 = +30'F (Base Plate)

Flange RT

= +40'T (Closure Flange) g Weld 1 Cu =.27 (Ref. 3)

Weld 1 Ni =.10 (Ref. 3)

Base Plate ! Cu a.10 (Ref. 3)

L Base Plate ! Ni =.18 (Ref. 3) e ens se Y

mil 088-0531 A-ST01 BRP091 02/0WOB

7

-.g

^f

..[

-s s 7.,

..(

,g

.f d[

BIG ROCK POINT NUCLEAR PLANT-

- EA K-AR-bg

Sheet 1 'of M Ws, A[

INGINEERING ANALY$li CONTINUATICN SHEET neu a

~+

x

.I y,

Wald C? e '127'F'(Interpolation.. Table 1. Ref. 2) l

i l:

\\

Sase CF = 56'F (Interpolaties, Table 1. Ref.- 2)

J J

l H

66'F 8

' Welt Martin = 2 420' + 17

=

h]

'i BasePlateMargin=2,jl?'+17'=48'F F

ETPY to 2/79 = 8.625 l.

i

'l 1

8 to 2/79 = 2.27 (10 ' n/ca, E>1Mev Ref. 3) fcap cap /EFFY.=' 2.27/8.625 =.263 x 1019 n/ce*/EFPY f

-3 I

18 n/ca' 19 14 = 4.737 x 10 cap /Wf 18 EFFY =.263 x 10 f

l t

Beltline Wall Thickness = t = 5.40625 inches J

1/4t =.25 (5.40625) = 1.3516 inchen 3/4t =.75 (5.4062$) = 4.0547 inches Operating Pressure = 1335 psig t

Pressure Measurement Error a 115 psi i

Temperature Measurement Error = 25'F i-I a

f-3-1 ee e e i

M11088-0531A-ST01 SAP 091 0241/88

,r.-,-.-

...w-.v,-------.--y, oy-

- -. - - -.. -~.w--m-,,

y ff A ' ' e y, l{;

7' SiG ROCK POINT NUCLEAR PLANT ra.wt-es-se-o'

~

. ENGINEERING ANALYSl5 CONTINUATION SHEET-Ihut 6,, 2 t

{

,,wuwe Rev # 0 m

m a nsary peammass

- FLUDICE CALCULATIONS l

From Equation 4i l

l

. l

- )

' f,l*Tgg(e'.84')

h

- f1/4 a 4.737 '(e'.84(1 3614))

l

-?

f1/4 s 4.737 le'.8f44)

(1/4 s"4.737 [.723]

l-1 8

(a 10 ' n/es, E)1Mev) f1/4

  • 3.425 t

l ' rt j

I f3/4 s 4.737 (e'.24(4,os47)l (3/4 = 4.737 [e." 88) f3/4 s 4.737 (.3779) 1 8

(s 10 ' n/cm, E)1Mev) f3/4 = 1.790 Weld ART iros Equation 3:

g I'8 4)I g [f g, (.88* 80

/

ART for 1/4 t veld s C.F j

a 127 13.425 (.sa,so los

))

g t

= 127 13.425.8888) l-a 127 [1,323)

= 167.85

  • 168'T l

l

.o.

M11088-0531A-BT01 SRP091 02/0148 e-,p

'3w.wh yr e--

sm--w-V

--w-dMT-w

+w e.

w a

m

,m.,__,_,_,_.,_

m.

,_____m.___________2

,. -.. m v

^

o

BlG ROCK PolNT NUCLEAR PLANT

' tA x-na-se.oi_

m M...

ENGINEERING ANALYSi5 CONTINUATl8N SHEET sheet 7 of 2A.

pewsasse nev s o me.asmurs sessanas

'Ag

-o F

g (f aje (.as* se los isjs)!

AR7 for 3/6 t veld a CF gg

= 127 (1.790 (.as,no lot i,,so);

s a 127 (1.790.888)

= 127.(1.'160) 147.3 % 147*F i

l ART for 1/4 t base plate = CF,33g (fij. (.as,so los fijeH g7 8

= 56 (3.425 ( sa, no los.4:s))

= 56 (3.425.nses)

= $6 (1.322)

= 74*r arf for 3/4 t base plate = CFgg (f g

(.58* 1s l'8 f84))

/

j yg

= 56 (1.79 (.as,so los 1.79))

a 56 (1.79.asey

= $6 (1.16)

64.9 % 65'T l

^

Weld Margin s 2 /0 8+o 8 3

3

  • 2 #288 + 135 s 2 46TT

=2 (32.76)

=

65.5

  • 66'T MIt088-0531A-8T01 GRP 091 02/01/OS

- - ~

n f

3' BIG ROCK POINT NUCLEAR PLANT EA A -ss-s,-Oi I

ENGINEERING ANALY515 CONTINUATION SHEET Sheet 8 cf - 29 ~

Rev f.0 J

m m em J

~

o.

Base Plate Margia = 2478+ 17T

]

= 2 VITI' l

= 2. (24)

L 43*y (1

RT FOR 18 EFFY & f = 4.737 x 10H n/ca8 DiMev l

NDT

(

RT r 1/4t veld =~ Initial RTg + ARTNDT * "*'8I" NDT

= -56'F + 164* F + 66'F

178*F RT or 3/4C veld

. 56'F + 147'T + 66*F NDT i

= 157'T RT for 1/4t base plate = 30*F + 65'F + 48'F yp7 143*F

=

RT or 3/4t base plate = 30'F + 48'F + 48'T NDT 126'F

=

MIt088-0531A-BT01 SAP 091 -0241/88

P Bl3 ROCK POINT NUCLEAR Pt. ANT EA.n-as-se-ci

'~

Sheet.1 cf 20.

i ENGINEERING ANAL.YH5 CCNTINUATGN $HEET nov, _ a sassans massans suseams i

REAT-UP/C001.DOW/NYDR0 TEST EQUATIONS

rpf For Reference 8. Section 3.C. the expression for heat-up and cooldown i

. pressure-tempersture limits is as follower i

(EQ.5)

K = 2Kg (pressure) v Kg (thermal) < K,

g g

1 or

,s IR > 2Kg (pressure) + Kg (thermal)

From Reference 9. K 18 818 8xPressed ast IR K

= 26.78 + 1.233 exp [.0145 T-RTET + 160]

gg i

Since the reactor vessel experiences aesbrane hoop stress that 1.-

pressure induced and thermal stress from through wall temperature gradients, the stress intensity factors for those parameters are given ast l-i and Kg (pressure = Kgg Kg (temperature) = KIT Therefore.

(EQ.6)

IR

  • 2EIN

'M11088-0531A-BT01 8AP 091 0241/88

~

1 2

, ;f", ' s '

e s

) I.

(fpf BIG ROCK POINT NUCLEAR PLANT EA.E-88-59-0 l

Y -@

Sheet I' of DL i

ENGINEEWING ANALY545 CONTINUAT10N SHEET I-Rev 8 -

i i.

.masmus ensemas L

l From Reference 9.

t.

1 to rM * "M (Membrane stress) t

.d KIT " M (ATaax) where 47,,, is the

{

t magnitude of the through wall

,j temperature gradient.

1

'Serefore.

I i-Kgg>2Mg (Membrane Stress) + Mt (AT,)

[

i l-i no temperature gradient profile (data) for SRP is in Table 1.

From Reference 9, Figure 6-2214-2 M =.268 g

To determine N, the ratio of' o/oy must be determined.

g t

t (EQ.7) n (1+, ) (g,f, g g)

Since o = a y

'l Where P = Internal Pressure = 1335 pois

~

g

= Inside Vessel Radius = $3.0625 inches a=r g b'=t

= outside vessel Radius = 58.46875 inches o

r = rijg = Radius at 1/4t = 54.414 inches and r 7, = Radius at 3/4t = 57.117 inches 6

MIt088-0531A-I'T01 RRP 081 02/0148 1

,e

-...-,,.-,,.,---e

-,-w.,--

-,.r.m---,,---nn-.-

.,y c

3 e

i l

[-

Y BIG ROCK PolNT NUCLEAR PLANT EA s-88259-Ol ENGINEERING ANALYSl$ CONTINUATION SHEET sheet Ll_ cf-21 i

a

persasus

^

amenars mesasas Rev # 0 h reforer.

i 8

e3jgt = -(53.0625)8 P (3, 58.46875 )

W a

r 54.414'

,(58.46875'

.53.0625')

4

= 2815.629 P II + 3418.5947 )

I 602.966

-2960.8834 y

= 4.6696 Pg (1 + 1.1546) m:-

= 4.6696 Pg (2.1546)

= 10.061 P g

.t y

43 4 58.46875 ')

.l 8

o3fst = (53.0625)8 P

i 57.1173 8

(58.468758 - 53.0625.)

1;

.l

= 2815.629. P II + 3418.5947 )

I 602.966 3262.3517

= 4.6696 Pg (1 + 1.0479)

= 9.5628 P p

g l

o.

$y for.6A-302 8 MOD at 585'F is taken f rom Ref.10 as i

43.8 + [44.5 - 43.8).15 = 43.905 s 43.9 KSI A.306 Now e/cg = 4 9 Nrefore from Ref. 9, l

i M

=.2.22 g

l i

.M11088-0531A-ST01 i

SAP 091 C2/0148

p s

,y," ' *

,-,,,.z h hp' E

. ENGINEERING ANALYSIS CONTINUATION SHEET

. sheet J2._.cf 29.1 BIG ROCK POINT NUCt. EAR PLANT?

' EA A-es-59 '

sessans

- nev # 0 ammaans passess

-i 0

RewridingEquations6_678:

.i Jh:-

K i 2Kgg _ + KIT i

gg O

er.

,;a Kgg >:2 eNh+0 eaa h

- l k;

'J Therefore'at 1/4Tt i

gg

  • 2 00.061)' P g + AT,,, _.y~

5

.K g

t t

.and

-s.t'3/4T::

-KIR

  • II' 0 Ib + A man b

~

i Soiving for P:-

l t

4 s

For 1/4T:

P-5 K, 7 g AT,,,

g

~~

2(10.061) 4 h

ls

/p.

.For 3/4T:

P5Kgg'- GAT,,,_

2(9.563) My l

y and multipling by 1000 Substituting the values of Mg&MT B

(kei to poi), the equation becomes:

At 1/47 :

J, gg - 6.0 AT,,,

P5[K

- AT,,, - (. 2W ) 0 000 5 22. 386 K gg L

(20.122) (2.22) i At 3/47:

- 6.312 AT,,,

P5[E

- AT,,, (.268) ] N O) 5 23. M2 KIR gg (19.126) (2.22) mil 088-0531A-BT01 BAP001 02/01/N

p

wi(

~ ~L~

7

- ^

..y j j.~ j 7

BIG-ROCK POINT NUCLEAR PLANT;

' EA.wL 5 9 : ENGINEERING ANALYS15 CONTINUATION SHEETL sheet i3 cf 29.

T eswease Rev# 0

S A '

autasers passess y

,I

-8 tace the tolerance on pressure is't 15 ps18 the heat up/cooldown equation'ie writtea as follows:

A Atl1/4T P'5 22.386 E

- 6.0 AT,, ~

gg At'3/4T: P s 23.552 K

- 6. 312 - AT,,, - 15 gg n.

3 p

B.

IN-SERVICE HYNtETATIC' TESTING' CRITICALITY TEMPERATURE

~

l:

Since the hydro is performed with the core not critical, heatup rates'are low and thermal gradients through the well are negligible. Therefore, the isothermal heatup condition will i

be employed _ for theitest pressure limits.

.V L Only heatup rates need to be considered for the hydro and,

,l during the hydro according to Reference 8,- the equations for' Kgg are:-

L; IR =-26.78 + 1.233 exp (0.0145. (T - RTuDT + 160)]

I 3

(EQ.8)'

I :

Kgg> 1.5 g og

~

brefore._ using Equations 7 and 8:

At 1/4T: P $ 29.848 K

-15 gg for 0*F/IDt heat up n

At 3/4T: P $ 31.403 K

-15 gg I'

e h

mil 088-0531A-BT01 g

t SAP 091 02/0 2

+..

, *'*i/

f,hi E

. BIG ROCK POINT NUCLEAR PLANT EA.E 59-01 14 W 20

ENGINEERING ANALYSIS CONTINUATION SHEET.

Sheet 1 .,

pewsase Rev # ' 0 marmaams passess

, TABLE 1

- BEAT UF/ COOL DOWN TEMPERATURE CRADIENTS 1

6).

Temperature Change Rate 4736 ATyg AT 7

oppgy.

ey op op J.

0 0-0 0

20 2.71-4.92 5.19 l

40 5.42 9.84-10.39

~

60 8.12 14.76 15.58 3

80 10.83 19.68 20.77

~

100 13.54 24.60 25.96-P ATgjg = Absolute value ~of temperature dif ference between inside of b

. reactor vessel vall-and a point one-quarter of the way through the' vessel wall, ATsj = 2. Absolute value ~of temperature dif ference between inside of g'

i o

reactor vessel vall and a point three-quarters of the way

- through the vessel vall.

' AT*** = L Absolute value of temperature dif ference between inside of reactor vessel wall and a point on the vessel outer diameter.

~

e n-e e

  1. 4 e

M11088-0531A-BT01

.R, 0.i 0= =.

i.4 w.

7 3

E.,

L g,,

gen l81G-ROCK-POINT NUCLEAR PLANTL EAA-88-5601

~

ENGINEERING ANALYSl5 CONTINUATION SHEET-Sheethof"

+

a.a p-r FORMULA

SUMMARY

I i less:than the weld metal RTgg,onlyveld Since:the base e t 1 RTg7 metal formulas are given as they are' limiting._ Notest The AT ters has' been deleted _ since the 1/4t section is in compression upon heat-up;

,l 2)l 1/4t. istalways limiting ior - cooldown. '

Weld' Metal K g = 26.74 + 1.233 EXP [.0145 (Tx.-177 +160 -5' + (afman - 671/4)) l.

j

' Heat'up g 1/4t:

i P = 22.386 K a -15 l

i Heattup t 3/4tt Kgg.= 26.78 + 1.233 EXP (.0145 (fx -156 +160 -5 + (67.a - AT /4)) l.

~

3 3

P = 23.552 Kgg =-6.312 Atas -15 i

Cooldown f L1/4t t' Kgg

  • 26.78 + 1.233 EXP [.0145 (Tu -177 +160: (afm - AT1/4) >)

4

.P = 22.386 K a -6.0 67m -15 i

cooldown 4: 3/4t: Kgg = 26.78 + 1.233 EXP (.0145 (TN -156 +160 _(ATu, - 673/4) >}

P = 22.552 Kga -6.312 ATm -15

/

Mydro-Test 41/4tt Kgg = 2'6.78 + 1.233_ EXP [.0145 (TN -177 +160 -5)]

_e*P/ma)

(

P = 29.448 tra -15 Nydro-Test 9 3/4tt Egg s' 26.78 + 1.233 EXP (.0145 (TN -156 +160 -5))

-(0*P/HR)

P.= 51.403 Kgg -15 r.

L

' NOTE:

5'F is added to temperature ters to accomodate the temperature seasurement tolerance.

4 4

5 M11088-0531A-8701 BAP 091 02/01/88

= ~-

o BIG' ROCK POINT NUCl. EAR PLANT EA.n-s8-59-01:

_j lM

. ENGINEERING ANALYSl5 CONTINUATION SHEET Rev#_0 16 d 20 sheet pousase y

assamrs ensensas g

. TABLE 2 - HEAT UP L-WELD METAL - 1/4T LOCATION Pressure (psig) at Metal Temperature ('F)

Temperature:

s Change Rate-

F/Hr 60'F-100'F 150'F 200*F 250'F 275'F i

0-632 670 761 949 1337 1666 (28.9)

(30.6)

(34.7)

(43.1)

(60.4)

.(75.1) i

-20 634 673 767 962 1365 1706 p

(29.0)

(30.7)

(35.0)

(43.7)

.(61.6)-

(76.9)

,1 p:

40 636 676 774 976 1393 1747 (29.1)

(30.9)

(35.3)

(44.3). (62.9)

(78.7)

L l

I60 637 679 781 990 1423 1789 (29.2)

(31.0)

(35.6)

(44.9)

(64.3)

(80.6) 80 639

'683 788 1005 1454 1834 (29.3)'

(31.2)

(35.9)

-(45.6)

(65.6)

-(82.6)

-100 641 686 795 1021 1485 1879

-(29.3)

( 31'. 4)

(36.2)

(46.3)

(67.0)

(84.6)

L L

H M11088-0531A-BT01 l

SRP091 02/01/u8

~

4

,,'4 :4 k s N

BIG' ROCK POINT NUCLEAR PLANT EA.NL-88-59-01 ENGINEERING ANALYSIS CONTINUATION SHEET sheet 12 of 20. -

l

/*f,

pewsame nev # ' o '

assumurs missasas

}n!..

I TABLE 3=- REAT UP t.

WELD METAL 9 3/4T LOCATION Pressure (psig) at Metal Temperat'ure ('F)

Temperature Change Rate i

'F/Hf 60'T 100'F 150'F 200'F 250'F 0

684 737 867-1.135 1689 (29.7)-

(32.0)

(37.5)

(c48. 9)

_(72.4) l 20 651-705 835 1105 1661

\\

'(29.7).

(32.0)

(37.5)

(48.9)

(72.6) o 40 619 673 804 1074 1632 L

(29.7)

(32.0)

(37.6)

(49.0)

(72.7)

~~

60 586 640 772 1043 1604 (29.7)

'(32.0)

(37.6)

(49.1)

(72.9) 80 554 608-740 1013 1575 L

(29.7)

(32.0)

(37.6)

(49.2)

(73.1) 100 521

-576 748 982 1547 (29.7)

(32.1)

(37.7)

(49.3)

(73.3)'

l' 4

l l

mil 088-0531A-BT01

. SAP 091 02/01/88

m gy..

EA NL-88-59-01 '

W BIG-ROCK POINT NUCLEAR PLANT f',.,'

ENGINEERING ANALY515 CONTINUATION SHEET Sh'et Cf 20 38

' +

,senass Rev#

muassays pasassas i

TABLE 4 COOL DOWN Ii

. c i

WELD METAL - 1/4T LOCATION L

Pressure (psig) at Metal Temperature ('F) j 1.

L l1 l--

Temperature Change Rate 150'F 200'F-250'F 275'T

'F/Hr 60'F 100'F 0

632 670 761 949 1337 1666 (28.9)

(30.6)

-(34.7)'

(43.1)

(60.4). (75.1) 3 20

'599

-635' 723 905 1279 1596 (28.8)

(30.5)

(34.4)

(42.5)

(59.2).(73.4) 40 566 601 686

  • 861 1222 1528' (28.8)

-(30.3)

(34.1)

(41.9)

(58.1).(71.7) 60 533 567 649 818 1166 1461 (28.7)

(30.2)

(33.9)

(41.4)

(57.0)

(70.2) 80 501 533 612 775 1111 1396-L (28.6)'

(30.1).

(33.6)

(40.9)

(55.9)

(68.6)

}

100 468

.500 576 733 1057 1332 (28.6).

(30.0)

(33.4)

(40.4)

(54.9)

(67.1)

}

mil 088-0531A-BT01 SRP 091 02/01/88

=

Y 'h BIG ' ROCK POINT NUCLEAR PLANT EAJt-se-59-oi sheet 19 cf 20 ENGINEERING ANAL.YSl5 CONTINUATION SHEET Rev # _ 0 esesass

+

a semaa n m esasas TABLE 5 -' COOL DOWN WELD METAL - 3/4T LOCATION Pressure (psig) at Natal Temperature (*F)

Temperature Change Rate

' F/Br 60'F 100'F 150'F-200'F 250'F 275'F 0

684 737 867 1135 1689 2158 (29.7)-

(32.0)

(37.5)

(48.9)

(72.4)

(92.3) 20 651-704 833 1101 1652 2120 (29.7)-

(31.9)

(37.4)

(48.8)

(72.2)

(92.1) 40 617 671

-800 1066 1615 2081 (29.7)

(31.9)

(37.4)

(48.7)

(72.0)

(91.8) 60 584 637 766 1031 1578-2042 (29.6)

(31.9)

(37.4)

(48.6)

(71.8)

(91.5) 80 551 604 732 996 1541 2003-(29.6)

(31.9)

(37.3)

(48.5)

(71.7)

(91.3) 100 518 571 698 961 1504 1965 (29.6)

(31.9)

(37.3)

(48.4)

(71.5)

(91.0)

\\

M11088-0531A-BT01 BRP 081 02/0148

y

[

E BIG ROCK POINT NUCLEAR PLANT EA.NL-88-59-01.

.g ENGINEERING ANALYSl5 CONTINUATION SHEET sheet 20 og 20

'4. >

,,,,umus Rev # 0 surmaars pasustas y;;

TABLE 6 - HYDRO TEST

~

WELD METAL - 1/4T LOCATION

" Pressure (pois) at Metal Temperature ('F)

Temperature Change Rate P

'F/Er 60*F 100'T 150'F 200*F-250'F i

1 L

0 848 898 1019 1270 1788 (28.9)

(30.6)

(34.7)

(43.1)

.(60.4)

~'~

WELD METAL - 3/4T LOCATION Pressure (psis) et Metal Temperature ('F) l-Temperature Change Rate

  • F/Br 60'F 100'F 150'F 200'F 2_502 5

P 0

917 988 1161' 1519 2255 (29.7)

(32.0)

(37.5)

(48.9)

(72.4)

L l.

1.

1 eDG mil 088-0531A-BT01 SRP001 02/01/08

-

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