ML20217Q459

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs 3.4.11,revising Pressure-Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90
ML20217Q459
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 08/28/1997
From:
CENTERIOR ENERGY
To:
Shared Package
ML20217Q457 List:
References
NUDOCS 9709030104
Download: ML20217Q459 (7)


Text

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

Attachment 3 PY CFlHilR-2206L Page I of 7 RCS P/T Limits f __._

3 f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .:. -. . . . . n . . n n n .;. n n . n : ' n ,

seco . .......y. . . . . . . . :. . . . . . . . g.. . . . . . .

s

.  :  : [ . . 7 :3...I..g.......:..  :. .: . . . . .t :o n.n i n: . . . n t. u n n.t n e n 1
:. :1  :.  :..  :.

. . 1.: # :.  :.  :  :

........(........>....... .

...I.t.......v.......l......4.....n4......8......

it I t':  :  :  :  :  :

........i 6300

: l4 i  :  :  :

........a.......:.........,.).J.i...........J.......a.......:.......*:......a:.......;:

: Aa. :  :
........:. 3 ... ,...... ......... . . . . . . , .

I : :

n  :  :  :

E i ii i i  !  !  !  !

........>........i......ei.....s.......i

: # .I  :  :

0 .......:...... 4 .. .... ...... ,:....... a: .......:.....  :

n  :  : i I;  :  :

J.......

a d  :  : r r:  :  :  :  :

13 000 . . . . . . . .y.......  :  :  :

3 ..... ...... ..y.......g.......,. . . . . . . . .y.......g.......g........y........g s

W  :  :  :  :  :  :

E  :  :  :  :  :  :  :

G - .......(........ 3.... . . g . . . . . . .  :> :. ...  :  :

3.......(........:>.......:3.......g........;:

W 1:  :  :  :  :  :  :

=  :  :  :  :  :  :  :

eoc -. . n . o 4 . . . .A a .

: . . . . : . . J.c:: - . . :a . . . :. . . : .: . . . . :. . J. .: . . . . . a . . . . . . . : . . . . . . . :. . . . . . . a: . . . .

n  :.  :  :  :  :  :

.......g............. . . .gn, . no n

. s1 u

.a .a l  :. i A - SYSTEM HYDAO 04 LEAK TEST w

g 400 I

- W :2 R

. LIMIT WITH FUEL IN VESSEL

.......i....... .... ..) ....{...**

8 - N N. NUCLEAR HEAtup/C00LOOwN

. . AND PHYSICS 1EST LIMIT Str.'s esls 4 j j C - trJCLEAR (C04E CRITICAL) LIMIT I

Aa'

i A'.S'.C'*A.S.C LIMITS AFTER 4 EFPY cc:  :

300 .......t...

. . . .y .. . . . . 3 .. . . . . . . t. u n . LIMITS DURING FIRST 4 EFPY j

  • j j
:  : = = = LIMITS BETWEEN 4 4 S EFPY

....... .., 3.......:.....

tug
:  : *
:* Yor:  :  :  :  :  :  :

/ I I I I I l l 1 1 I I

  • soo soo soo .oo eco MIN:MUN AEACTOR VESSEL METAL TEMPERATURE (*F)

REACTOR VESSEL PRESSURE versus METAL TEMPERATURE, VALID UP TO 8 EFPY Figure 3.4.11 J1 -

PERRY - UNIT 1 3.4-31 Amendment No. 69 9709030104 970820 PDR P ADOCK 05000440 PDR m

+

Attachment 3 PY-CEl/NRR 22061, Page 2 of 7 1400 INITIAL RTndt VALUES

' ARE 10*F FOR DELTLINE, 20'F FOR UPPER 1200 VESSEL, AND 10*F FOR

' BOTTOM HEAD HEATUP/COOLDOWN RATE 20*F/HR

.9 0 1000 8

9 d

" 800 so11ou - ( ELTLINE CUPVES E HEA0 70 F j AD JSTED AS SHOWN:

{ j EFPY UP TO 9 SHIFT (*F) 30.3 E 600 e-G l

= ,

3 e I b 400 -

10 l E

  • I 3 "*'" l UPPM WMR N BELTLINE LIMITS

- - BOTTOM HEAD 200 - RANGE LIMITS REGION 70*F 0

0 100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 3.4.11 1(a): Pressure Test Curve (Curve A)(Valid Up to 9 EFPY Unit 1)

PERRY - UNIT 1 3.4-31 Amendment No.

Attachment 3 PY-CElHRR 2206L Page 3 of 7 l

1400 ,

l I INITIAL RTndt VALUES l ARE 10*F FOR BELTLINE,

-1200 *I -

20*F FOR UPPER VESSEL AND 10'F FOR l BOTTOM HEAD HEATUP/COOLDOWN

.y I RATE 100'F/HR -

r .

{-1000 f-5 .

c '-

.O J ' -

u 800 I. '

h 8

- BELTLINE CURVES '

b- f ADJU3TED AS SHQWN.

D- # EFPY SHIFT ('F) 6 a:

m uou- /) UP TO 9 - 30.3 600 sexo ye.p , _,

E b.

i

)

E <

= /

E -400 s i E -

UPPER VESSEL AND l

BELTLINE LIMITS 200 - - - BOTTOM HEAD LIMITS (iLANec RWiON WP g.

-o 0 100- 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

Figure 3.4.11-1(b): Non-Nuclear Heatup/Cooldown (Curve B)(Valid Up to 9 EFPY- Unit 1)

PERRY - UNIT 1 3.-1 31 a Amendment No.

Attachment 3 PY CEl/NRR-2206L Page 4 of 7 1400 i

INITIAL RTndt VALUES ARE 10*F FOR BELTLINE, ,

20*F FOR UPPER 1200 VESSEL, AND 10'F FOR BOTTOM HEAD HEATUP/COOLDOWN RATE 100*F/HR

.9

- - - o 1000 .

8 s

d

  • l 800 4-BELTLINE CURVES

@ ADJUSTED AS SHOWN.

g EFPY SHIFT (*F) .

g UP TO 9 30.3 E 600 -

E e

b 400 e

E Minimum >

Criticality Temperature ~ BELTLINE AND 70*F NON-BELTLINE ,

200 LIMITS O

O 100- 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 3.4.11 1(c): Core Critical Operation (Curve C)(Valid Up to C EFPY - Unit 1)

PERRY-- UNIT 1. 3.4-31 b Amendment No.

Attachment 3 PY-CElHRR 22061.

Page 5 of 7 1400

. l

, INITIAL RTndt VALUES

! f ARE 30*F FOR BELTLINE, 1200 l

  • 20*F FOR UPPER VESSEL, AND 10*F FOR f BOTTOM HEAD l HEATUP/COOLDOWN

.2 I RATE 20*F/HR L

  • _o 1000 '

s2- - 2 1-f ,.

8 s ii s

m 800 s

--y*[ - --

sonow [

HEAD 70*F BELTLINE CURVES

/

g ,!

i ADJUSTED AS SHOWN. ^

EFPY s

E / UP TO 18 SHIFT ('F) 91.9 600 <-

E __

e i E. '

E I b 400

-a i k '

_ I"#

  • l UPPER VESSEL AND BELTLINE LIMITS 200 -

runoe - - BOTTOM HEAD REGION 70*F LIMITS 0

0 100 200 300 400 MINIMUM Figure 3A11-1(d): REACTOR VESSEL METAL TEMPERATURE (*F)

Pressure Test Curve (Curve A)(Valid Up to 18 EFPY . Unit 1)

PERRY - UNIT 1 3.4-31c Amendment No.

Attachment 3 PY-Clil/NRR-2206L Page 6 of 7 1400 , ,

I e

INITIAL RTndt VALUES ARE -30'F FOR BELTLINE, I

' 20*F FOR UPPER 1200 VESSEL, AND 10'F FOR l BOTTOM HEAD

, HEATUP/COOLDOWN RATE 100*FiHR E 8 g 1000.

-l-5 .

I 8

I d

m e00 -

l-h 8 BELTLINE CURVES g / ADJUSTED AS SHOWN:

, EFPY SHIFT (*F) 6 Ir. 600 1

ev uou -

sego yo.y --

/ UP TO 18 91.9 E ,

e i h'400 w l ,

UPPER VESSEL AND l BELTLINE LIMITS

- - BOTTOM NEAD 200 LIMITS

[I LANGE RF.GiGN Mt - l 0

0 100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 3.4.111(e): Non Nuclear Heatup/Cooldown (Curve B)(Valid Up to 18 EFPY Unit 1)

PERRY - UNIT 1 3.4-31 d Amendment NO.

' Attachment 3 -

PY CEl/NRR 2206L Page 7 of 7 14C0 ,

INITIAL RTndt VALUES -

ARE 30*F FOR BELTLINE, 20*F FOR UPPER VESSEL, AND 10*F FOR 1200 BOTTOM HEAD HEATUP/COOLDOWN RATE 100'F/HR TP

- _ 1000 t

8-800 BELTLINE CURVES h~ ADJUSTED AS SHOWN:

b- EFPY SHIFT ('F)

UP TO 18 91.9 !

U 000 E-w$ -

g_ 400 f Ninimum Criticality

~ BELTLINE AND 3-Temperature NON BELTLINE 70*F LIMITS 200 i

1

.0 200' 300 400 0- 100 MINIMUM REACTOR VESSEL NETAL TEMPERATURE ('F)

Figure 3.4.11 1(f): Core Critical Operation (Curve C)(Valid Up to 18 EFPY Unit 1)

PERRY - UNIT 1 3.4-31 c Amendment No.

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