Text

Rev 1 to Pressure/Temp Limits Rept
	ML20211N177
Person / Time
Site:	Crystal River
Issue date:	10/11/1997
From:	; FLORIDA POWER CORP.
To:	;
Shared Package
ML20211N175	List: 3F1097-14, Forwards Rev 1 to Pressure/Temp Limits Rept, Per Requirements of TS 5.6.2.19.Rept Revised to Provide Consistency W/Normal & Emergency Plant Operating Procedures. TR BAW-2241P Has Been Submitted for Review.Commitments,Encl; ML20211N177;
References
	NUDOCS 9710160044
	Download: ML20211N177 (8)
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.

r ATTACHMENT B Pressure / Temperature Limits Report

!T>A *I88M Ms8ssola P PDR:

l 4

4 8 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 l

l PRESSUREffESIPERATURE LIMITS REPORT REVISION 1 l Referencing Improved Technical Specifications

, l 1.0 Pressure / Temperature Limits This Pressure Temperature Limits Report for CR3 has been prepared in accordance with the requirements of Technical Specification Section 1.1 and 5.6.2.19. The pressure / temperature (P/T) limits .. ave been developed using the methodology provided in the references. -

The following pressure temperature limits are included in this report:

1) Allowable plant heatup and cooldown rates

2) Plant heatup P/T curve

3) Plant cooldown P/T curve

4) P. ant inservice leak and hydrostatic testing P/T curve 2.0 Fluence and Limiting Material Infonnation

1. Predicted intide surface peak fluence at 15 EFPY : 0.499 E19 n/cm2

2. Limiting Material : WF-70 (Upper to Lower shell circumferential weld)

3. Adjusted Reference Temperature (ART): 203 deg F @ 1/4T 171 deg F @ 3/4T 3.0 References l

1. B&W Owners Group, topical report B AW-10046A, Rev. 2, " Methods of Compliance With Fracture Toughness and Operational Requirements of 10CFR50, Appendix G," June 1986.

2. B&W Owners Group, topical report BAW 1543A, Rev. 2,

" Integrated Reactor Vessel Surveillance Program," May 1985, and Addendum I, July 1987.

. 3. Babcock & Wilcox Company, report BAW-2049,

" Analysis of Capsule CR3 F Florida Power Corporation Crystal River unit 3," September 1988.

4, Babcock & Wilcox Company, report BAW 2091,

" Pressure-Temperature Limits for 15 EFPY for the -

i Crystal River 3 Nuclear Plant," August 1989

5. NRC Safety Evaluation Report supporting Amendment No.133 for Crystal River Unit 3 February 7,1991, l

l'/T l.lMITS llEI'OllT, itet, i Page 2 of 7 l l

i l

TAllLE OF CONTENTS

~ Pace -

Allowable Pressure /Temperatute Rates . . ......... ... . ..... ..... ......... .......... .......... .. . ...., . 4 P l a n t i 1 c a t u p C u n* c . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 P 1 a n t Co o l d o wn C u n c . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Plant inservice Leak and 11ydrostatic Testing Curve........ ................ .... .. ........... 7 lYl' l.lMITS 11El'OltT. Iter. I l'.Te 3 of 7 l

V Al.l.0WAlli.E IIEATUP AND C001.DOWN RATES

a. A maximum heatup of 50*F in any one hour period,

b. For the temperature ranges specified below, the cooldown rates are:

1. T > 280'F s 50'F in any 1/2 hour period, ii. 280*F 2 T > 150*F s 25'F in any 1/2 hour period, iii. 150*F 2 T s 10'F in any I hour period and,

c. A maximum temperature change ofless than or equal to 5*F in any one hour period during hydrostatic testing operations above system design pressure.

These limits are referred to by Technical Specification 3.4.3.

l l

l i

1 P/T IMilTS ItEI'OllT, lhv. I Page 4 of 7 l

REACTOR COOLANT SYSTEM PRESSURE. TEMPERATURE LIMITS FOR HEATUP FOR FIRST 15 EFPY 2000 .-4.. ;. . ..-

,4 .4 _ . 4 4 2500 DA1A PO!MS ,

y..- -;

_ -_ j Point Temp Press i-' * '

1 1' *-i' - i' -

l 2400 - -

a

+

.4

',1- -- :

A 60 303 -4 p

,, a..

4-. -

2300 -

8 126 303 . ,i . . . . ,1 - : M .-

-t-.

.p- .'.

)

2200 C 150 319 - : :- r--- - -t -- -

2100 0 175 3H f 't' 'i__ C,4_ 4' C

t 200 409 t i- ! <

a 4 >'

2000 r 225 492 'T ~P-~~~~~~T , t ,

~' ~

1900 -

0 250 611 - - H. J-- . -- t a ' i

+

-_.3_.-

4 q .t . . .

1800 - H 280 825 . - - - : _ - ___ . L . J.

t 300 1021 4 ! ; t '

- 1700 -

-+ ;

J 320 1242- L i 4- a-- J <

( ; ---e - K .. t; p m_ 1600 340 1535-

--,-- , 4 . 1 q. ,

r , s. ,

a 1500 -

L 355 1815

--f' 6 - - - - + - 4

!# 1400 - M 375 2275 __i - :

1

]' ..

4 3,

_.._j ~

.;i.

.d. ! 4

- 1300

.,i ,-

i e 1200

~

+- '+-- -- -- 4 --

5: < 4 i t 4 -

t g 1100 --- -

1-- 7 q M i000 --- - ---

. i

-- L-- r-o - -+I --- -l-- i--

900 -- --

", - R--,4- i

-~~ - t - --- -- i

( t-

- -- l, -----

i .

800 -- i, -- - - -+i - --

-- ~

700 - - - + - - - - - - -

-l ---- - -- .

+ ~ 0. __

. I. .

i i i 1 Specific Instrument Uncertainties -

600 -

-r,------+'-----+i--F i i MUST be applied to this curve for 500 - ~ ~ - - ~

- + --E -

operational use (see note 3) 400 -.o A. --B-C- ,

_._.g..-_..,. 7 .,_

300 -L i

, ' [ - D J--- 2-M-i i i -. " -+

I-f-'~ 1

. s .

200 r

"!~~- --+---i,--- --

r,,-- +-

- - ~ ~ - -- - - - - -

i j

r 100 --

l 1 0

0 50 100 150 200 250 300 350 400 450 500 RCS TEMPERATURE (degF)

NOTES:

1. The regions of acceptable operation are below and to the right of the limit curve. (see note 3)

2. Applicable for heatup rates of s 50'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and,

3. Margins are' included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Additional margins for instrument uncertainty are not included and must be applied to operatin0 procedures based on the specific irstruments being used to monitor the RCS conditions.

4. Minimum Temperature for Criticality is 2 525 degF (Reference Technical Specification 3.4.2).

5. This curve referred to by Technical Specification 3.4.3 l'rl' I,lMITS REl' ORT. Hs.- I l'ap 5 of 7

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITS ,

'. FOR COOLDOWN FOR FIRST 15 EFPY 2600 * * '* '

.2500 . DA1A PolN15 I' h ,

_____b 2400 -

Point Temp Press .

.L ,_,.2 ! _ , ,

__jn . '

_h -

A 60 285 +. .+ . t. ; l -4 ,

2300 -

8 150 285 ..; ,

]~ t~ - - - - ~

m- -

2200 -

c 175 338 ~ ~4 i a 1-- U -----. 1 1 2100 0 2p 412 2 I 1.*

F i _ .._.j i

2000 E 225 516 ~j- - , 6 4 j --*~" f F 250 674 .p W.

1 '

1000 a 280 en -J L - l j 4'

- -+

<.io i.

1800 H 320 1486 . -- : __

1700 1 38t 2275 _L _. <

l l ..J -d_.._

r

_ d' 4

,-. 1600 1

+ '

--H- I

- - - ~ -

1 1500

.t.

+r .' ~ a q ,

-- - p-

+ + -

g 1400 - " ; -l ----

--H - - - - -

d- , .2 m

5 1300 --- + --4 -,.

!~ -

.F . .

F . ..

1-.J y 1200 ---t--------,- r - .

a_ t , .

t e . < l j l- .

r 1100 A-~~

.=

t

,-o. - _ i,. .

2s. 1000 - -

.F '

-- qm ; _-%--__._

-i 000 -

- k ! '

! -- I 000 700 h

- - - + - ~

k--- .----- 1 F

i--

t h --i

' j.

~

i-w.I 1 i.

~ ' ' '

2

' ! I i Specific Instrument Uncertainties 600 - - - + - .

E- +--m- MUST be applied to this curve for

+ i ! ! ,

500 - -

-- - t-

[~ operat,ional uso (see noto 3) 400 4 -

+ A --- - B C -i - --D- ~. ~+i-i-

4 -

2 i

1--

i ,

.-.1----,-..._

1 d

+

3 300 --

~

. - - -a . - -- -

i !

t . i 200 -a --- --+ - L . - - .- " . .r. - - - -

100 -+------~.)- e j

i 1

d - -. q -___~'. -- -

0 0 50 100 150 200 250 300 300 400 450 500 RCS TEMPERATURE (dogF)

NOTES:

1. The remions of acceptable operation are below and to the right of the limit curvo. (soo noto 3)

2. Appt for cooldown ratos of; l '8200*F s 50*F in any 1/2 hour period, 280'F 2 T > 150'F c 25T in any 1/2 hour period.

l 150*F r T s 10*F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period l-

3. Margins are included for the pressure differontial between point of system pressure measurement i

and the pressure on the reactor vessel region controlling the limit curve. Additional margins for instremont uncertainty are not included and must be applied to operating proceduros based on the specific instruments being used to monitor the RCS conditions.

4. A maximum step temperature change of 25'F is allowable when removing all RC pumps from operation with the DHR system operating. The step temperature change is defined as the RC ,

temp, Tc, (prior to stopping all RC pumps) minus the DHR return temp, Tout (after stopping all RC oumps).

5. This curvo referred to by Technical Specification 3.4.3 IYI'l.lMITS REPORT Iter. I Pap 6 ol' 7

- ~ _ _ _ ~ . _ . , _ __, _ . . _ _ _ . . - _ . . _ - . . - . . __ ____ _ . _ _ _

REACTOR COOLANT SYSTEM PRESSURE. TEMPERATURE LIMITS FOR INSERVICE LEAK HYDROSTATIC TESTS FOR FIRST 15 EFPY !

i 2600 -

-)

2500. -

. DATA POINTS ~[ --

_h iL* )'

j&

d' -F l*-

F int Temp

{ 1 1, 1-Press 2400 -

q. a 4 A 60 416 " e 4

.- i -i- .

+

2300

,q.,

B 150 416 :

.[ _;. j.

..L 4 -

2200 !

c= 182 513 -

0 205 513 ! ++ -+

f -

=K- j- 1- 4 j.

2100 -

E 2M 612 t e i< t t 4 -

1- 4 2000 -

F 225 691 4- . q i.

1900 -

250 848 l . . >b. . - U G .

'~

1900 - H 280 1132 [

"p -

~

1700 -

3 300 1391 -

i ' '

J 320 1684 -4

.{- 4 4 m 1600 ~

K 340 2067 .J .

j ; r 31500 L 30 2525 2 . ,

g- l q.

_. 1400 - --4 -

$ 1300

+ '

Y '

1 Ee 1200 .; , .t. .' '

G 1100 -

l M 1000 900 --

] ;

_t f-

~

800 ! L I

N]

700 I E ' -- 1 Specific Instrument Uncertainties .-

600 -

fA % '

[ .

MUST be applied to this curve for ,__

f opera,tional use (see note 3)

~

500 __ -.

400 -j- - g-- ;

-- ~4

-7 m- --

300 -: p ,

F- q---

200 ~ -- t -- l L- ,

-L---~-- : .-

100 -

f ' -I' -

f - -- d.--- l 0-O 50 100 150 200 250 300 350 400 450 500 RCS TEMPERATURE (degF)

NOTES:

1, The regions of acceptable operation are below and to the right of the limit curve. (see note 3)

2. Applicable for heatup rates of s 50'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and.

Applicable fbr cooldown rates of:

T > 280*F s 50*F in any 1/2 hour period, 280'F 2 T > 150'F s 25'F in any 1/2 hour period, i 150'F 2 T s 10'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

3. Margins a.e included for the pressure differential between point of system pressure measurement i and the pressure on the reactor vessal region controlling the limit curve. Additional margins for instrument uncertainty are not included and must be applied to operating procedures based on the specific instruments being used te monitor the RCS conditions.

$ 4. - A maximum step temperature change of 25'F is allowable when removing all RC pumps from operation with the DHR system operating. The step temperature change is defined as the RC temp, Tc, (pnor to stopping all RC pumps) minus the DHR retum temp, Tout (after stopping all RC pumps).

5. This curve referred to by Technical Specification 3.4.3 l'Tl' l.I, tilts REI' ORT, Rev. I Page 7 ot' 7

. . _. _ -

ML20211N177

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