Text

Unit - Pressure/Temperature Limits Report, Revision 4
	ML032040061
Person / Time
Site:	Crystal River
Issue date:	07/15/2003
From:	Terry J; Progress Energy Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	3f0703-09, ITS 5.6.2.19
	Download: ML032040061 (11)
	v • d • e

a0Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: ITS 5.6.2.19(d)

July 15, 2003 3F0703-09 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - Pressure/Temperature Limits Report, Revision 4

Dear Sir:

Progress Energy Florida, Inc. (PEF) hereby submits the Crystal River Unit 3 Pressure/Temperature Limits Report (PTLR), Revision 4, as required by Improved Technical Specifications (ITS) 5.6.2.19(d). The changes made to the PTLR are administrative in nature.

No technical information was changed. The revision number for calculation F-97-0013 was corrected to Revision 4. In addition to the corrected revision number, several minor format changes were made to the graphs on pages 6 through 10 to improve readability.

No new regulatory commitments are made in this letter.

If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.

Sincerely, t Ames H. Terry ()

ngineering Manager JHT/pei Attachment xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR - 72 ATTACHMENT Pressure/Temperature Limits Report (PTLR)

Revision 4

TABLE OF CONTENTS Pag Supporting Information .................................... 3 References .................................... 4 Allowable Pressure/Temperature Rates ..................................... 5 Plant Heatup Curve .................................... 6 Plant Cooldown Curve .................................... 7 Plant Inservice Leak and Hydrostatic Testing Curve ......................... ........... 8 LTOP Curves .................................... 9 Plant Composite Curve..............10i ......................................................................... 10 P/T LIMITS REPORT, Rev. 4 Page 2 of 10 F97-0013 Rev. 4

1.0 Pressure/Temperature Limits (Ref.4)

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 (PiT) limits have been developed using the methodology provided in the references (Ref. 1, Ref.2, Ref.3). Additional limits have been included which support the LTOP Technical Specification 3.4.11.

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 PiT curve 4 Plant inservice leak and hydrostatic testing P/T curve 5 LTOP P/T curves 6 Composite PiT curve 2.0 Fluence and Limiting Material Information (Ref.5)

T/4 Location l weld LNB to US Circ. Weld (ID 40%)

material SA-1769 fluence 4.27E+18 n/cm2 ART 213.0 F 3/4T Location {

weld LNB to US Circ. Weld (OD 60%)

material WF-169-1 fluence 1.55E+18 n/cm2 ART 144.5 F__

3.0 PTS Evaluation Summary (Ref.6)

Inside Surface weld LNB to US Circ. Weld (ID 40%)

material SA-1769 fluence 7.08E+18 n/cm2 RTpts 239.9 F 4.0 Instrument Uncertainties The values referenced by this document do not include instrument uncertainties.

Uncertainties must be applied based on the specific instruments being used to measure the parameters of interest.

P/T LIMITS REPORT, Rev. 4 Page 3 of 10 F97-0013 Rev. 4

5.0 References

1. B&W Owners Group, topical report BAW-1543A, Rev. 2, "Integrated Reactor Vessel Surveillance Program," May 1985, and Addendum 1, July 1987.

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

3. B&W Owners Group, topical report BAW-2241P, Rev. 0, "Fluence and Uncertainty Methodologies," May 1997.

4. FTI Document 32-5001746-01, "CR-3 32 EFPY PT Limits,"

November 2000.

5. FTI Document 32-5000218-00, "ART for 32 EFPY for CR-3,"

June 1997.

6. FTI Document 32-5000303-O0, "PTS Evaluation for CR3,"

June 1997.

P/T LIMITS REPORT, Rev. 4 Page 4 of 10 F97-0013 Rev. 4

ALLOWABLE HEATUP AND COOLDOWN RATES

a. For the temperature ranges specified below, the heatup rates are:

1. T > 2800 F

70'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, H. 2800 F 2 T > 850 F

50'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, iil. 850F 2 T > 600 F

150 F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

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

i. T > 2800 F S 500F in any 1/2 hour period, H. 0 280 F 2 T > 150OF < 250 F in any 1/2 hour period,

11. 1500F 2 T

250F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and,

c. A maximum temperature change of less. than or equal to 5 0F in any one hour period during hydrostatic testing operations above system design pressure.

These limits are referred to by Technical Specification 3.4.3.

PIT LIMiTS REPORT, Rev. 4 Page 5 of 10 F97-0013 Rev. 4

REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS FOR HEATUP FOR FIRST 32 EFPY 2800 . ..

. . . ,. l . . . . . . . . .

1 1 DATA POINTS I .

r-i- I-I11 I l r i l

r Il1_1 1_ H

-i- r i r --- r-i

l -riTi lii - I __ l -

i T -i-rr r-i- r- - r l i t -i- T-I I I I I I I I I I I -r r :- I s I I I I I I 2600 Point Temp Press A 60 368 j!L il

- J-j - ---n- lii r - 1 l111 j

lii

-r-r-t-

,,t ml r,, l i m-2 1 r- S

- l l

-,... - m-2400 B 120 368 l l i ~.I~~i lI ii I ..I. 1... L...L.. ...L I l II' i Ji 1 1I 1I II I5 l ii i I iI I l i i i C 140 383 D 160 416 2200 E 190 497 L I ~l .1l L ~I .I I 1 1I 1 li 2 2 1.1Ii1 l I1i i i

.I l11i i I .l l i i l l 2 l2 1 1 L 11 1 1 1 12@

F 220 547 2000 G 263 692 1 I1 1 5 1 1 1 1 1 1 IIl S Sll l 1 1 1 1 1- 1 . -15 H 300 909 I_*1 _1_ .._1 _ l__1,_1_*._1_ 1 -I_1_- --

1 -F I-I- _I_ _lF 1-+- _I _I_ . _ _I_.

I 325 1129 1800 J 350 1448 wa.

K 410 2772 r I -I r -- n- r, -r@ r r -r I I r -r T 1600 I II I o1 1 1 I II I t I1 I

I I 1 I I I I1rI I I II 0.

a, 1400 Il r n. l -. Ill l I . . ,. .1 . 1 1

i, - l -l ll - - 1 1 - I l S1 . . . . . , , .,,.

c i-II

' t'-

1I I - i 1 - -I

'- r i T -

-- wJ -i-I-i I I I 0 1200 _J_ t-=,_11, J-J J_-_1_ WLLJ__ .JLJJW JL__JL__XJL tlJLS___

a, _. . .+/- . . J . L .l . .l . L L . I ..

. I I.. L. . . J . L . .. ..J... L. .. L .S.. 1Jll1.Al. ..L .I. I .L ..L I ., L. ..I. .

1 . L L .. I.. I . L . L. .

1000 1 1 1 5I*

a - .

l I i- - -. 1 1 1 1 1 1lL... I .... . - -. l l J -L I 800 I l l s l ll l l l f l l lt i t > I' Il o l l I I Il 600

1 ~m 111. 1111 1 MUST be applied to this curve for 5

-nrs-

_- _l. ~s__ -r S- n Inr .t tr-r

'.' I II

-,_lrl_-

,.I ' I I.

-ir-s-

.r operational use (see note 2) 400

-n--TW--ngT~fi 1TT I Iat lill- t--

- - '*~~~~~~~~~~~~~~~~~~~~~~~~~~~~-'

,r-. -in~ r-r- -:4-ri-s -r T --r - -r o

T-r-

-- i

- r-, r-n ,r 200 1 1

_~~~~~~ 2 1 1 1 1 1 1 1 l Ii I III1 1 1 1 1 1 llllII 1lll 0

0 50 100 150 200 250 300 350 400 450 500 550 600 RCS TEMPERATURE (degF)

NOTES:

1. The regions of acceptable operation are below and to the right of the limit curve.

2. 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 operating procedures based on the specific Instruments being used to monitor the RCS conditions.

3. Applicable for heatup rates of:

T > 280°F S 70°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, 280°F 2 T > 85°F S 50°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, 85°F 2 T > 60°F S 15°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

4. RC Pump Constraints for Heatup:

T > 263°F None, 263°F > T 2 220°F No more than 3 RCPs running, 220°F > T 2 85°F No more than 2 RCPs running, 85°F > T No RCPs running

5. Minimum Temperature for Criticality is 2 525°F (Reference Technical Specification 3.4.2).

6. This curve referred to by Technical Specification 3.4.3 P/T LIM1TS REPORT, Rev. 4 Page 6 of 1()

F97-0013 Rev. 4

REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS FOR COOLDOWN FOR FIRST 32 EFPY a a 2800 . . . . . . . . . .

. . .. I . ...

. . . . V--l1lVTT1TiI Hg . . . HI 1

1 H*H 1

a*uu g i g. I H

H HI I I

1l III HI H II H i l l I I I

H HI i---

- 1H DATA POINTS 'r7r n-r-r, n-ri-r -: -rr,-rl-:-rn-r -rT-r r-r7 r 1r7-r-r -ri-,-r-I I I l lII HI ll lI Il I I I I I HI lI I I I II I 2600 - Point t Temp Press

.. A 60 313 ,-r-,- . ,-, T T - - -ri . r@. , ,-r-m. - - r, i, r1-,- -,~rl~r i-rn-r -,-rg-r -. Trh-r -r-rTir ------ i-r -- r- r-,-r 150 313 I . lI I ILI I I I:_,.,i .H _II .l i i II HI I II . - I I I I I -

2400 -

'C 187 355 ,,..H H H ii III -L.H JIL I Ill, -,, .I H, i 0 217 441 ,I ,.,, gl H ,,II I ,,,, HI , . l Hl l lll H ill HI Hl 2200 - H 230 543 240 599 L ..L.. . J ..L .J...H J _L..jJ_. .l..L J L 1-lL L J .L . .LL...'.. ..L.L...H.. L . L .. l ... I. .L.L. HL .

F , , H i l H H H H I H I I I H H I Hi g , H4 ,H- H Ii 2000- 263 710 Ill il l H l l . H . ll i ... H ll. . * ~~~~~~~~~I l Il H . . .g .L L H 267 725 Ll..._I_ J_ L J._ . _LJ_.I..L L J L _I_H L JL _. J_1 L.L.H _.L.L..JL _ ._L.AIL _. L.L...LL.

I l l H H i l IH l 1l 1 g H l Iii I Hl l i IH l l$

CD 1.800- I 280 865 i HI I Ii I iIH l i H

~~~~~~~~~

. L.1..

41'....

lX 300 1092 i ll l H l Ii I i s l I l l CD r -r -t -t-

,,, -t- - r i . -.,, I,, ., , . .,,. . . .4 .

=11 . K 320 1338 H II Hi l I H Il Ul 1. l i i i l i l i i I l H 1600- L 340 1666 C) 370 2297 il l Hi , i l -I - HF H gi g I F i i i -I - F I l l iF H

+- -FI -I-l (A

ce 1400- Hi i i .. H l

.l i H t . .Il I i Hi l i i . . Hi I l H H Hil l ii H l i il l i

@ll Hi H ll Ill H i Il l

a. 1200 -

uM rs-r- -T-r*~ -,r-r -,- -r- -i-ri~ .r-- rr-,-r -r-.-r -,- -rri I i i i H l i i l .H i i Hl , i .i l , ,I I , ,i il ,i i Is I i C,)

C.) 1000- ... H i l . i. .H I i H. .H i Hi HI i H Hi Hi . . . . I l I

lH ll l 1 iT-,-rT-

,_ _ _, I ,; I I iri-i- - -rl rIl -,-ii r-.-r Tr--r -rir -- r -r T

_ . . i ll n-lrl-vHTJU-r- ll 1, , l .l I Hi l l l 800 p a1 H HIll H liiiH H a H

,I ,_ -- :_ . Li _ Lf

.j_ -----!E

!_ -1l ! L I I

H.I I l I III Hi HI ' lHIlll 1 i!i !0iIF ' i I, il H HI Specific Instrument Uncertainties --

600 . . . . . . . . . . . . . . . . . . . . . .. . . ... . . . . . . . .

MUST be applied to this curve for H H I.II l .i H I i I.l lI I i I..i I I I I I II I I IIIl jI- J _ ' I j.. I.l iII. i i I I i ll .llk . operational use (see note 2) +/-.

400 - -

I I i II I i - I _,I I~vIil , I l i l L T -L T '1 - . T1LI I -

._LA'

.l .~

-_1_ IJ_I-

.J..

H ill

-J_

I.J_Al l l

- I-I 6--

I l i

-LJL I I II. I4 _.. J.. L J i J. ... H.. .. . . . . L

. I...L. .. L ... H.... 4. . . . . L 4.. .L. . . . ~ . L. L .......

200 . . II. . . f--II- . .- 47

. --. I . . . . . . . .- . . I I I I . . . I I I . . . I I Ii 1 I IiII H I 1 I I I I I I I I I I I I lI I I I Il l I i iIi HI H I I I I HII I H I 0

HI l l 1 I _l

... ~~~~~~~~~~~~~~~~~~~~~~~~.

Il l I J liI l 1 . ....

I jI l I I I i Hi iJ H

I I l l I

0 50 100 150 200 250 300 350 400 450 500 550 600 RCS TEMPERATURE (degF)

NOTES:

1. The regions of acceptable operation are below and to the right of the limit curve.

2. 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 operating procedures based on the specific instruments being used to monitor the RCS conditions.

3. Applicable for cooldown rates of:

T > 280°F

50°F In any 1/2 hour period, 280°F 2 T > 150°F 5 250 F in any 1/2 hour period, 150°F 2 T 5 25°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

4. RC Pump Constraints for Cooldown:

T > 263°F None, 263°F > T > 90°F No more than 2 RCPs running, 90°F 2 T No RCPs running

5. This curve referred to by Technical Specification 3.4.3 P/T LDIITS REPORT, Rev. 4 Page 7 of 10 F97-0013 Rev. 4

REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS FOR INSERVICE LEAK HYDROSTATIC TESTS FOR FIRST 32 EFPY 3800 . . . . ... ...I ~~~~~~~~~~~.

.. I I . -I I ..... ... ! . . .. I . .. .. ... ... I .,- , - .. I - T T-- .. . .- - .- -T...

-....-r

DATA POINTS _ll mI I Ii i g lii 1 1m m l li lii Ioul 3600 _ Point Temp Press - -I- 4 ~-I- Fill,_1-1 ~~~~~~~~I

__1 iiI1- I 1 I _1_il 1- -I- i - Il-l -I-o1I-4 1 1- _-Ill 4 I 1_4 II- _-- I '

3400 A 60 439 lII iI t I l 1.1...

i liii 11r1 1111 I I- I II I I - 1

. B 140 439 -- ri-i n-rnr I l-ri-r -i-ro-r -l-r Jr -r -i-r -lrT-l r -r IF-1 -r1-I-?-

3200 C 160 455 Il 1_ ..11 , . ......11 , 1 . ....11 ...

1II , I 1 . L

... ~~~. .. L1. .. .. l.,, l .l ...

i i

D 190 52.0 n-r 1-l- i,-rn~i- n-rnr i-rn-r n-rn - irvr - T-- r r-t-P-r -r1-I-r 3000 E 220 625 II I I I I 'I I 111 1 ,l Ii r 11. , 1 l, l, l , loll 11..

2800 F 263 956 J G 300 1242 I11, 1I ll -TI11 2600 j H 340 1767 0 4 I 370 2389 .lii,,. 11 , . 1 l 1 1Ill . .1 . l . l. l l

. lll . . . l1v

. .. l1 0 l ,,ll II I II 110

. . ll 1 1 2400 J 395 3115 lii illI I I11 1 ll f11 II gt l l mii e111 1111 2200 ,51 la M

c -r i-- -r-r -l -Ir,-r i- rT-I- T I- T -ri -- -

l, 2000 11-L 1 11L 1 I 1 I I rr LJ 4 1 rr -1 r~r'

-- - - L -rTo-r LIsrmr-rmr- -1 , L -rTl- i l -r7rr li i l .I-r1i-rr1 I I l...L. ..I.. !L L ..'.. .... Ls 0..27 I J I.I ....... J ..L..E L.. L i co 1800 .1 CC 1600 4_L1 J_J __LJ_ . A L.~lA -- LJI

_ J_ L JL- J-_LJL -__JL__JL__ILllL___

1_

Q II I I rrI I II I I II II I I iT 1111 T11 r 1 1 I I I I I I I I a) 1400 Q' Ill I lIll l1 l l ii1111 1111 oli 11l II I 1200 1111 1111 f i l l 1 1 I 1 l 1 1 _ .... .... .. .

1000 .111 1111' ' ' , ...

1111 ....

liii .

liii ,Specific

-' Instrument Uncertainties 1 f l l l .o llI.1 Ii I rl . . I f f ilT~ I~T~I~

ifii~ .

'-i-I- .... -- .. I. .. ~~~~~~~4-.

rdioir-.'--,- -.I- rl - r,,....' r. MUST be applied to this curve for

800 T n ir L. n- r-- -I- T- operational use (see note 2) - '

600 JiJ0__& .J-L.-1L J...LI...l J1 -e '_LJ_. JLiJL 1L12.. ._.LL LL ._

_.'_ JLiiI _L1JL_ _'. .1.i .LJ...'..+/-

400 1 T1 D rI lI 1 -r i I - 1- - 1 1-200 . i ii r I I - I ' 11 1

1_, L.L...L ...LLI..L .LL.... _.__1__.._

..L..LL ..LAJ... .. J..+/- L.L._.__._. ...L.+/-...L.L.<:_1 ...LL.L..L. -.. _LL+/-.. .. _ 1I - 41I A

0 50 100 150 200 250 300 350 400 450 500 550 600 RCS TEMPERATURE (degF)

NOTES:

1. The regions of acceptable operation are below and to the right of the limit curve.

2. 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 operating procedures based on the specific instruments being used to monitor the RCS conditions.

3. Normal heatup and cooldown restrictions should be used with this curve as applicable.

4. This curve referred to by Technical Specification 3.4.3 P/T LIMTS REPORT, Rev. 4 Page 8 of 10 F97-0013 Rev. 4

REACTOR COOLANT SYSTEM LOW-TEMPERATURE OVERPRESSURE PROTECTION LIMITS FOR FIRST 32 EFPY 1000 . -. . -- . - . . . . . . . . . . . . . : r. ::r--i-. . : -i- -, I 10 Minute Transient

.Analytical Limit

- -- I -- I--

I r- 4 I __1 I

- I

_1_4____

I- I": -I'- - -I- - - r - - P - :t- - :: - - - - - I - - t : - P- - - I- - -

-I - -I.. _1__: : - .1 - : t. -- I..- -I- - - - - .4 - - + - P. - : .. : -

Point Temp Press 4-I Point Temp Press 4. - - - - -- - - 4 - 4. - - - - I- -

900 -

A 60 300 4--

-I K 60 458 1. -

L-:L _: 4 ~4 :~O ... ... L - L.....I...

B 85 300 -I L 85 458 1. L -J L L LI:L C 100 305 M 100 467 =A.L:.L -L D 125 317 N 125 487 L L L -- - I I 800- E 150 334 --

O 1S0 517 7~~~~~~

I I I I IITI--r I -Ir F 180 364 j-I P 180 567 r r I- I-; I I- ~ -r - -- T - -

G 200 393 -II-Q 200 617 700 - H 220 421 -I- R 220 664 I 240 471 S 240 751 cn 1--

J 263 551 -I-T 263 888 Cf 600 -- J -L __ L - -::

w - . - -. .l . .- 00- LI I

-- J - -1 I

__ L - :LL L L I I I . I 11__ :1::L::L::

I I I 0C co 500

- . ~~r--l--n__n__

-_l_-n--n--T-- *~ --r a--n-- d----r--r~n~~( --T- r r~-r-- --n---~ -r--r-L 400 ~-r-m--n__:_ _ L.-_-I-_-_ - -- -- -

300 --~A~ ~ ~ ~~~~~IL- Specific Instrument Uncertainties

. , I, . . . . . . .-- --r-n__-~~~~~~~~~-

__t__.---------

_ , 1 . -*--r^-i-_.---

. F--r----- ---- +----r-

__________ ----------------- MUST be applied to this curve for 200 I I- r operational use (see note 2) --

___J_ _J___ ___IJJ_ ____J_ _____t_

-pT - 1r1 _ _ _ _ _ _ _ _ _ _

100 .4--4 -I -I --- i -I~~~~~~~--------

. - .1., 1J..L....

, , . E__ -: 4 0

0 50 100 .- 150 200 250 300 RCS TEMPERATURE (degF)

NOTES:

1. The regions of acceptable operation are below and to the right of the limit curve.

2. 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 operating procedures and Technical Specification Umits based on the specific Instruments being used to monitor the RCS conditions.

3. The LTOP curve applies to operation below the enable temperature of 263 0F.

4. The LTOP 10 Minute Transient Curve is established based on at least 10 minutes of operation of the limiting transient without exceeding the LTOP Analytical Umits with an initial pressurizer level of 160 in.

5. The PORV setpoint is established to protect the LTOP Analytical Umit Curve.

6. This curve referred to by Technical Specification 3.4.3.

P/T LIMTS REPORT, Rev. 4 Page 9 of 10 F97-0013 Rev. 4

REACTOR COOLANT. SYSTEM COMPOSITE PRESSURE-TEMPERATURE LIMITS FOR FIRST 32 EFPY 2800-I I. . . . I a_ ;_a I; i 1m;_;I

I;i 1

1 la. 1- i £ _14 ;;; m m - m --a ;] l

~r m

.;11 i DATA POINTS -i iI- rv a- r i -r ar r-rr rT- r r~bTm ri r r?-r-II I ff I I I I 1i I m I IamImamI Ia aImII 2600 -

Point Temp IPress A 60 300 Vi- 1ai-1a ai-~i~i- ~mr i- i-r-- mT- i-ra1 i~aTT B 85 300 2400,- C 100 305 D 125 313 2200 - E 150 313 -I I I..- .... 4..L.L ..L IL -I iJ I -L I I F 187 355 2000 - G 200 393 H 220 421 I 240 471 0-.

J 263 551 K 263 692 wj 1600 - L 300 909 H 325 1129 .I..LJ..L

.J..LL..L ..a..J..L .... L.a.. ..... .J.L ..

L. . ... . L. .. . . . .L..... .L .LJ n) 1400 - N 350 1448 0 389 2322 0.U U,

ot 12000-I_

a- a ma a -m a1Ia a a a a m ~I' a1 ala 800 -

- {1rrrla-mal m.a l a Specific Instrument Uncertainties :

I MUST be applied to this curve for 600- a aa a aa a a a aIa a aI - a- -a a a a a ~.

a a a a ala- T a aaa maaa

-7 a Ia1Imaa ram a i ~mmmJaa Irama Iam mmi.qm -' a- mljamal a-amaIT-I

a. operational use (see note 2) -t ma . Ia a . 1 1I 1 I 11a I .aI ¶aI a l I Ia I I . .

400-

-- ------ - - --- - a -- L .... L...- - - - - -. -L.m. . . ..

.L 200 LJ. ~..

J11 1 I .J....L.

.~.LL. -. l. £* ,.I.. . 1A -- L.J....L. - L1 -a-L - A L -LAL.A-1.

0 D50 100 15Q 200 I 250 ~: .3,00 '350 400 450. S00 550 600 RCS TEMPERATURE (degF)

NOTES

1. The regions of acceptable operation are below and to the right of the limit curve.

2. 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 operating procedures and Technical Specification Umits based on the specific instruments being used to monitor the RCS conditions.

3. Normal heatup, cooldown, and LTOP restrictions should be used with this curve as applicable.

4- The COMPOSITE curve applies to heatup, cooldown, ISLH, and LTOP.

5. This curve envelopes the heatup, cooldown, ISLH, and LTOP curves referred to by Technical Specification 3.4.3.

PIT LIMTS REPORT, Rev. 4 Page 10 of 14 3 F97-0013 Rev. 4

ML032040061

Text

Subject:

Dear Sir:

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