Text

Proposed Tech Specs Exchanging P-T Limits Curves Currently Located in Unit 1 & 2 TSs & Deleting Current 8,10 & 12 Effective Full Power Yr Hydrostatic Test P-T Limits Curves & Adding New Ones
	ML20133F431
Person / Time
Site:	Brunswick
Issue date:	01/07/1997
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20133F357	List: BSEP-96-0344, Application for Amends to Licenses DPR-62 & DPR-71,revising P-T Limits Curves Currently Located in Units 1 & 2 TSs & Deleting Current 8,10 & 12 Effective Full Power Yr Hydrostatic Test pressure-temp Limit Curves to Add New Ones; ML20133F374; ML20133F431;
References
	NUDOCS 9701140180
	Download: ML20133F431 (45)
	v • d • e

_- - .--- . - . _ .. _. _ _ _ . _- -- . . - - -. -

i REACTOR COOLANT SYSTEM 3/4.4.6 PRESSURE / TEMPERATURE LIMITS l i

REACTOR COOLANT SYSTEM l LIMITING CONDITION FOR OPERATION 3.4.6.1 The reactor coolant system temperature and pressure shall be limited in accordance with the limit lines shown on (1) Figure 3.4.6.1-1 for heatup by non-nuclear means, cooldown following a nuclear shutdown, and low power I PHYSICS TEST; (2) Figure 3.4.6.1-2 for operations with a critical core other I than low power PHYSICS TESTS or when the reactor vessel is vented; and '

4 (3) Figures 3.4.6.1-3a or 3.4.6.1-3b, as applicable for inservice hydrostatic I i or leak testing, with:

a. A maximum heatup of 100'F in any one-hour period, except for inservice hydrostatic or leak testing at which time the maximum j heatup shall not exceed 30*F in any one-hour period.

b. A maximum cooldown of 100*F in any one-hour period except for l inservice hydrostatic or leak testing at which time maximum cooldown shall not exceed 30*F in any one-hour period.

c. A maximum temperature change limited to 10*F in any one-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves, and ,

d. The reactor vessel flange and head flange temperatures greater than or equal to 70*F when reactor vessel head bolting studs are under tension.

APPLICABILITY: At all times.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of the reactor coolant system; determine that the system remains acceptable for continued operations, or be in at least H0T SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.6.1.1 The reactor coolant system temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

9701140180 970107 PDR ADOCK 05000324 P PDR BRUNSWICK - UNIT 1 3/4 4-13 Amendment No. 1

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.1.2 The reactor coolant system temperature and pres:ure shall be determined to be to the right of the criticality limit line of Figure 3.4.6.1-2 within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality.

4.4.6.1.3 The reactor material irradiation surveillance specimens shall be removed and examined to determine changes in material properties at the intervals shown in Table 4.4.6.1.3-1. The results of these examinations shall be used to update Figures 3.4.6.1-1, 3.4.6.1-2, 3.4.6.1-3a, and 3.4.6.1-3b, as I applicable. The cumulative effective full power' years shall be determined at least once per 18 months.

1 BRUNSWICK - UNIT 1 3/4 4-14 Amendment No. l

l l

FIGURE 3.4.6.1-1 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL l

1200 , , ;

n 1 r '

r 1100 1000 ;

l I

S e

e' 900

@ r E

/

8 800 I

d e

i r l y 700 [

W

, , )

/

h NORMAL OPERATION S 600 F

CORE NOT CRITICAL - UNIT 1 m

550 peig

/

HEATUP / COOLDOWN

p. ( UMITING CURVE 500 5

a m

E 400 f OPERATE TO RIGHT ANDOR BELOW

, tiuirino tine 0 '

E / "# "

300 .

/

[113 $ ____,I'f,C

1. FUEL IN REACTOR I 2. s 16 EFPY j 3. 7.1 X 10" NCMI> 1MEV j 4. RTNOT = 93*F (1/4 "i)

I 5.15 PSIINSTRUMENT LOCATION 100 CORRECTION INCLUDED BOLTUP 6. REG. GUIDE 1.99 REV. 2 70*F 0 . . .

0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F) l BRUNSWICK - UNIT 1 3/4 4-15 Amendment No. I

FIGURE 3.4.6.1-2 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL ,

1200 l l

1100 i 1

1 1000 To a

8' 900

, O w

j r I

8' I o 800 e f ,

ni i l m r l y 700 [

h Q 600 J

! NORMAL OPERATION CORE CRITICAL - UNIT 1 m

% 560 poig

[ HEATUP / COOLDOWN E LIMITING CURVE i b 500 OPERATE TO RIGHT AND/OR BELOW f LIMITING LINE f

k I OPERATION IN CROSS-HATCHED AREA 3 400 ,' PERMITTED ONLY WHEN WATER LEVEL m f ISWITHiN NORMAL RANGE FOR POWER g fj OPE *ATION 300 r r/! 1. FUEL IN REACTOR V/ '

fHs 2. 5 16 EFPY 200 j$$ 3. 7.1 x 10" N/Cu2 1uEv ff//n

[

{ 4. RTNDT = 93'F (1/4 T) 100 '

5.15 PSIINSTRUMENT LOCATION h/ ,r[,[gf 1'"//////s CORRECTION INCLUDED

6. REG. GUIDE 1.99 REV. 2 JL//////!

0 193 210 70 ,

O 100 200 300 400 500 600

) MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

BRUNSWICK - UNIT 1 3/4 4-16 Amendment No. I

FIGURE 3.4.6.1-3a PRESSURE-TEMPERATURE LIMITS

, REACTOR VESSEL 4

1200 ,

c

! r

/

1100 /

3 A

J 1000 /

/

? I 8 900 /

Q /

d g 800 /

d '

s v) J y 700 /

.s P'

,, a o 600 8 7 P'* "

6 E

3 t- 500 3 HYDROSTATIC g PRESSURE TEST - UNIT 1

@ 400 uurTING CURVE E

E OPERATE TO RIGHT ANDOR BELOW Q -

313 peng LIMITING LINE 300 BASES.

1. FUEL IN REACTOR 200 2.s 14 EFPY 8

3. 2.39 X 10" N/CM > 1MEV (N16 Nozzle)

4. N16 NOZZLE RTNOT = 86.3*F (1/4 T)

5. BOTTOM HEAD REGION RTNOT = 10*F (1/4 T) 100 ; 6, BELTLINE REGION RTNOT = 85.4*F (1/4 T)

"BOLTup 'COERECO NTL .)

,7, ,,,

8. REACTOR NOT CRITICAL 0 ... .. ,, . . .. . . ,. .

60 70 80 90 100'110 120 130 140 150 160 170 180 190 200 210 220 230 240 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

BRUNSWICK - UNIT 1 3/4 4-17 Amendment No. I

FIGURE 3.4.6.1-3b PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL 1200 ,,

i f

d' 1100 /

r f

1000 V

/

h 3

J k

900 2P

/

W

/

8

~

80c ,

i d d w a y 700 p g

p ms

/

y 600 3 ,8 %

0:

E t- 500 3 HYDROSTATIC g PRESSURE TEST - UNIT 1 400 LIMITING CURVE Q.

OPERATE TO RIGHT ANDOR BELOW

-313 M LIMITING LINE 300 BASES.

1. FUEL IN REACTOR

2. s 16 EFPY 200 I

3. 2.73 X 10" N/CM > iMEV (N16 Noule)

4. N16 NOZZLE RTNDT = 89.7*F (1/4 T)

5. BOTTOM HEAD REGION RTNOT = 10*F (1/4 T) 100 6. BELTLrNE REGION RTNDT = 85.4*F (1/4 T) 7.15 PSI INSTRUMENT LOCATION

-$BOLTUP CORRECTION INCLUDED

- 70*F 6. REACTOR NOT CRmCAL j 0 '?' ,,- .- , , , , .- , , i 60 70 80 90 100 '110 120 130 140 150 160 170 180 190 200 210 220 230 240 MINIMUM REACTOR VESSEL METAL 1EMPERATURE (*F)

BRUNSWICK - UNIT 1 3/4 4-18 Amendment NO. I

1 i

l THIS PAGE INTENTIONALLY DELETED. I BRUNSWICK - UNIT 1 3/4 4-19 Amendment No. I

i REACTOR COOLANT SYSTEM j BASES 1

PRESSURE / TEMPERATURE LIMITS (Continued) start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent I with the design assumptions and satisfy the stress limits for cyclic operation.

i 1

During heatu). the thermal gradients in the reactor vessel wall produce

! thermal stresses w1ich vary from compressive at the inner wall to tensile at the outer wall. Thermal-induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure. During cooldown, thermal 1 gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.

The reactor vessel materials have been tested to determine their initial RTuor . The results of these tests are shown in GE NEDO 24161. Revision 1. l l Reactor operation and resultant fast neutron. E>1 Mev, fluence will cause an I increase in the RT Therefore, an adjusted reference temperature, based l upon the fluence, uor.can be predicted using the proper revision of Regulatory l Guide 1.99. The pressure-temperature limit curve Figures 3.4.6.1-1, 3.4.6.1- 1

2. 3.4,6.1-3a and 3.4.6.1-3b include predicted adjustments for this shift in RTu or at the end of indicated EFPY. as well as adjustments to account for the location of the pressure-sensing instruments. !

The actual shift in RTnor of the vessel material will be checked periodically during operation by removing and evaluating. in accordance with ASTM E185-82 reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius vary little. the measured transition shift for a sample can be adjusted with confidence to the adjacent section of the reactor vessel.

The pressure-temperature limit lines shown in Figures 3.4.6.1-1.

3.4.6.1-2. 3.4.6.1-3a. and 3.4.6.1-3b have been provided to assure compliance I with the minimum temperature requirements of the 1983 revision to Appendix G of 10CFR50. The conservative method of the Standard Review Plan has been used for heatup and cooldown.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.

BRUNSWICK - UNIT 1 B 3/4 4-4 Amendment No. I

1 ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 '

OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS PRESSURE-TEMPERATURE LIMITS CURVES l

l l

1 l

l

_ TYPED TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 2 l

j

REACTOR COOLANT SYSTEM

! 3/4.4.6 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.6.1 The reactor coolant system temperature and pressure shall be limited in accordance with the limit lines shown on (1) Figure 3.4.6.1-1 for heatup by non-nuclear means, cooldown following a nuclear shutdown, and low power PHYSICS TEST; (2) Figure 3.4.6.1-2 for operations with a critical core other than low power PHYSICS TESTS or when the reactor vessel is vented; and (3)

Figures 3.4.6.1-3a or 3.4.6.1-3b, as applicable for inservice hydrostatic or I leak testing, with:

a. A maximum heatup of 100*F in any one-hour period, except for inservice hydrostatic or leak testing at which time the maximum heatup shall not exceed 30*F in any one-hour period.

b. A maximum cooldown of 100*F in any one-hour period except for inservice hydrostatic or leak testing at which time maximum cooldown shall not exceed 30*F in any one-hour period.

c. A maximum temperature change limited to 10*F in any one-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves, and

d. The reactor vessel flange and head flange temperatures greater than or equal to 70*F when reactor vessel head bolting studs are under tension.

APPLICABILITY: At all times.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of the reactor coolant system; determine that the system remains acceptable for continued operations, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.6.1.1 The reactor coolant system temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

1 BRUNSWICK - UNIT 2 3/4 4-13 Amendment No. I

l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1 4.4.6.1.2 The reactor coolant system temperature and pressure shall be determined to be to the right of the criticality limit line of

+

Figure 3.4.6.1-2 within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality.

4.4.6.1.3 'The reactor material irradiation surveillance specimens shall be removed and examined to determine changes in material properties at the.

intervals shown in Table 4.4.6.1.3-1. The results of these examinations shall I be used to update Figures 3.4.6.1-1, 3.4.6.1-2, 3.4.6.1-3a, and 3.4.6.1-3b, as I applicable. The cumulative effective full power years shall be determined at least once per 18 months. :

4 i

1 l

l 1

I BRUNSWICK - UNIT 2 3/4 4-14 Amendment No. I

FIGURE 3.4.6.1-1 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL I 1200 i

f 1100 I

I 1000 J

9 n b

1 900 2 !

E i g 800 l ,

d l '

700 ,

e i S / NORMAL OPERATION o CORE NOT CRITICAL - U.', ~ 2 600 Goo p.,

f h HEATUP / COOLDOWN 500 ,f ' " " ' " ""*"

a '

ul I h

g 400 y f OPERATE TO RIGHT ANDOR BELOW tiuirino ting E

300 N

/

1 1. FUEL IN R EACTOR I

Il

2. s 16 EFPY f

3. 7.1 X 10" NCM 8> 1MEV f

[ 4. RTNDT = 81.4*F (1/4 T) 100 , ,, S.15 PSIINSTRUMENT LOCATION i ,ii CORRECTION INCLUDED BOLTUP 6. REG GUlOE 199 REV. 2 To*F 175 ' '

O 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

BRUNSWICK - UNIT 2 3/4 4-15 Amendment No. I

i FIGURE 3.4.6.1-2 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL 1200 o ,

i

?

0 1100 I

i 1000 [ ,

1 6 E f 6

{ fi i

~

900 ,

I

[' l i

z -

l l h 800 /

d i e

y 700 ,, ,f c '

660 psig I S NORMAL OPERATION U i CORE CRITICAL - UNIT 2 600 h HEATUP / COOLDOWN Z LIMITING CURVE

!- 500 . OPERATE TO RIGHT AND/OR BELOW 2 '

L!MITING LINE 1 OPERATION IN CROSS-HATCHED AREA

] 400 .f PERMITTED ONLY WHEN WATER LEVEL u) g IS WITHIN NORMAL RANGE FOR POVER g f OPERATION. i 1 #

BASES.

300 ,/j

/> 1. FUEL IN REACTOR )

iA l IfA 2. s 16 EFPY f^ )

200 ,

i/vu 3. 7.1 x 10" N/CM2 > 1MEV II/i4 )

I,VI I p 4. RTNOT = 81.4*F (1/4 T)

/ M I'A '

100 5.15 PSIINSTRUMENT LOCATION l' #[#7 j'l/ iA V /i CORRECTION INCLUDED

6. REG. GutDE 1.99 REV. 2

/ A Yl/6/ A

~ ' ^

0 . . .

70 181 210 0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) 1 BRUNSWICK - UNIT 2 3/4 4-16 Amendment No. I

1 1

i FIGURE 3.4.6.1-3a l PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL 1200 , ,f i 1 '

I I /! I j i

1100 ,

,,/ ' '

i i t, is l' ,

1000 n/

I/

i il l

l 3 .

/ li u

1 i

, ,/

m g 900 ,

, , , ,,'l g if i i i

, x -

/ .

l l

Ei e

800 , / '

Ei m /

[

i h 700 _

'I

/

2 e /

o p /!i 6 l 4 o f, o i , ,

600 f ,

? 6 , ,,

iti.

it lv i ;

e i i

i g , i E 541 pst 4 l j l y 500 , l' l i a HYDROSTATIC tu PRESSURE TEST - UNIT 2

@ 400 LIMITING CURVE 4 % OPERATE TO RIGHT AND/OR BELOW C- LIMITING LINE 313 psig ,

300 --- !

BASES.

I !

1. FUEL IN REACTOR e i 2. s 14 EFPY 200

) -

l T-ll T l ', [' ll ll l' l l 12.39 X 10 17N/CM >2 1MEV (N16 Nczzle)

4. N16 NOZZLE RTNOT = 78.6*F (1/4 T) i i i 1

. b I '

I

5. BOTTOM HEAD REGION RTNDT = 40*F (1/4 T) 100 } _' ,,,, n,l , , l 6. BELTLINE REGION RTNDT = 81.8'F (1/4 T) t iiiI Iili I 4 7.15 PSI INSTRUMENT LOCATION l CORRECTION INCLUDED

-BOLTUP

8. REACTOR NOT CRITICAL T- - 70*F l 0 , . . . . . . . . . . . .

60 70 80 90 100 110 120 130 140 150 150 170 180 190 200 210 220 230 240 i MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) 1 l BRUNSWICK - UNIT 2 3/4 4-17 Amendment No. I

j FIGURE 3.4.6.1-3b PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL i

1200 , , , ,/ _

i i is e e i

! . t 6 11 fi

' ' "/"

1100 1 ! ! i ! I tt/

' l 1 i l If 6 i fi I l 1 fi l 4

1000 'l ,

i g

g ii i

,l

.i if n[',

in i . .

3 W i

I II i .

l i

Ifl

/ 8ll llt!

S ' ' ' " "" ' '

a 900 ni i i ii , u f. un '

i i '/ I lill ]

! i 4

z i i . i r ,

i i I / I i

,- .h 800 i

u if

/ ,

i

.a l /

2 uJ W I /t i !

0 ' ' ' '" '

i

> 700 n / ni n l'/ in l j e '

11

O

)

/ l l l

$ H ' ' "

1 6 600 i un o e i ii !

,4 e ! u ti li/n i i _ t 3 541 prag -( ; l,l l s 500 niiiiii o i i ni ii 5

2 n

-i

~h, 'yN n',r r, ,, ~ -

HYDROSTATIC

y l l l PRESSURE TEST - UNIT 2 8 400 ,,, ,,,, ,l , , , LIMITING CURVE

$ I Ii 'Ii i i i 4

C I '! II ' '- ' { OPERATE TO RIGHT AND/OR BELOW Q- II !I ' II 313 psigh LIMITING LINE y; l i

, . 300 .

BASES.

j ---

l l l l i ; 1. FUEL IN REACTOR

ii i i 2. s is EFPY 1 200 j

-y-y i i l'

i ll l' e i l l

4. N13 NOZZLE RTNOT = 82.0*F (1/4 T) 2

3. 2.73 X 10'?N/CM > 1MEV(N16 Nozzle)

'EI i! I 5. BCTTOM HEAD REGION RTNOT = 40*F (1/4 T) j 100 l l ', , , l, I I'l,

, 'l

, , ,' ,, ,, 6. bel TLINE REGION RTNDT = 81.8'F (1/4 T)

"7 till illi i g i i i -

i 7. SPS TR N ATION

. .L -BOLTUP :

7 p-y - 70*F ,!' 8. REACTOR NOT CRITICAL

, , l j 0 . . . , , . . . . . . . . .

60 70 80 90 100 110 120 130 140 150 150 170 180 190 200 210 220 230 240 4

i MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F) l

.i 4

4 BRUNSWICK - UNIT 2 3/4 4-18 Amendment No. I

i i

l l

i l

l THIS PAGE INTENTIONALLY DELETED. I 1

1 1

1 l

l BRUNSWICK - UNIT 2 3/4 4-19 Amendment No. l

REACTOR COOLANT SYSTEM

\

mu i

! PRESSURE / TEMPERATURE LIMITS (Continued) i i

start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent i with the design assumptions and satisfy the stress limits for cyclic operation.

During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at 1 the outer wall. -Thermally-induced compressive stresses tend to-alleviate the tensile stresses induced by the internal pressure. During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.

l The reactor vessel materials have been tested to determine their initial RTuor. The results of these tests are shown in GE NED0-24157, Revision 2. I Reactor operation and resultant fast neutron, E>l Mev, fluence will cause an l increase in the RTuor. Therefore, an adjusted reference temperature, based upon the fluence, can be predicted using the proper revision of Regulatory Guide 1.99. The pressure / temperature limit curves Figures 3.4.6.1-1, 3.4.6.1- {

2, 3.4.6.1-3a, and 3.4.6.1-3b include predicted adjustments for this shift in 1 RTuor at the end of indicated EFPY, as well as adjustments to account for the location of the pressure-sensing instruments. I The actual shift in RT uor of the vessel material will be checked periodically during operation by removing and evaluating, in accordance with ASTM E185-82, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius vary little, the measured transition shift for a sample can be adjusted with confidence to the adjacent section of the reactor vessel.

The pressure / temperature limit lines shown in Figures 3.4.6.1-1, 3.4.6.1-2, 3.4.6.1-3a, and 3.4.6.1-3b have been provided to assure compliance with the I minimum temperature requirements of the 1983 revision to Appendix G of 10CFR50. The conservative method of the Standard Review Plan has been used for heatup and cooldown.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.

BRUNSWICK - UNIT 2 B 3/4 4-4 Amendment No. l

a. Am JJ - n -=J. 4a w.a .Q + v -- . .--

.u a,.- A-- -_ AJ,*---4-4 aus 4 m~a4- aamu. A ., m .%Au _A ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPEPATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS PRESSURE-TEMPERATURE LIMITS CURVES l

\

l I

l MARKED-UP TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 1 l

l l

l

-- m ,,-

. . . .- .-. . . . . . -. .-. . ~ . . - _ _ . . - .._ ~.-._ ..-.. . - _ - - . - . . . . _.-.

)

4 1

ENCLOSURE 7 l BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 i NRC DOCKETS 50-325 AND 50-324 4 OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS PRESSURE-TEMPERATURE LIMITS CURVES a

1 1

4 MARKED-UP TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 1 l

- -. - . - - _ _ . . - . . - ~ , . . -- - . - _- . . . .. - - . -

i i

l l

REACTOR COOLANT SYSTEM

[

3/4.4.6 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.6.1 The reactor coolant system temperature and pressure shall be limited in accordance with the limit lines shown on (1) Figure 3.4.6.1-1 for heatup by non-nuclear means, cooldown following a nuclear shutdown, and low power PHYSICS TESTS; (2) Figure 3.4.6.1-2 for operations with a critical core other than low power PHYSICS TESTS or when the reactor vessel is vented; and (3) Figures 3.4.6.1-3ay .4.6.1-3b ,(3r 4/4fe.p'3gh as applicable for inservice hydrostatic or leak testing, with:

w

a. A maximum heatup of 00*F in any one-hour period, except for inservice hydrostatic or leak testing at which time the maximum heatup shall not exceed 30*F in any one-hour period.

b. A maximum cooldown of 100*F in any one-hour period except for inservice hydrostatic or leak testing at which time maximum cooldown shall not exceed 30*F in any one-hour period.

c. A maximum temperature change limited to 10*F in any one-hour period 1 during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves, and I

d. The reactor vessel flange and head flange temperatures greater than l or equal to 70*F when reactor vessel head bolting studs are under tension.

APPLICABILITY: At all times.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an engineering evaluation to determine the ef fects of the out-of-limit condition on the f racture toughness l properties of the reactor coolant system; determine that the system remains acceptable for continued operations, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS s l 4.4.6.1.1 The reactor coolant system temperature and pressure shall be l determined to be within the limits at least once per 30 minutes during system heacup, cooldown, and inservice leak and hydrostatic testing operations.

BRUNSWICK - UNIT 1 3/4 4-13 Amendment No. (fjl(P

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.1.2 The reactor coolant system temperature and pressure shall be determined to be to the right of the criticality limit line of Figure 3.4.6.1-2 within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality.

4.4.6.1.3 The reactor material irradiation surveillance specimens shall be removed and examined to determine changes in material properties at the intervals shown in Table 4.4.6.1.3-1.- The'results-of these examinations shall be used to update Figures 3. 4. 6.1-1, 3.4.6.1-2, 3. 4. 6.1-3a ,# . 34. 6.1- 3b , @f2)

@ 4j6.y 3 Q as applicable. The cumulative effective full pIwer years shall be determined at least once per 18 months.

l l

i i

1 l

1 I

i BRUNSWICK - UNIT 1 3/4 4-14 Amendment No. (hI

1 l

FIGURE 3.4.6.1-1 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL *' ' I-I w

< / l

(; NORMAL OPERATION WITH CORE NOT CRITICAL.

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! V l , , . , , ! y . e i e e i i 0 100 l 200 300 400 500 60

70) (175)

TEMPERATURE (* F1 PASES-

1. FUEL IN RIACTCR 2.

$ 16 EFPb 3.

7.1 X =1081.4 NfCM 2 > 1 MEV 4 RT (1/4 T)

5. 15h,IINSTRUMENTLOCATIONCCFJ.ECTICNINCLUOED s

6. REG. GUI::E 1.99 REV. 2 NOTEE-

1. CPERATE TO RIGHT AND/OR bel.0W LIMITING LINES

'.

IND! CATES BCTH UIATUP AND COCLDOWN RATE Q PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARINTHESES BRUNSWICK - UNIT 1 3/4 4-15 Amendment No. @

REACTOR COOLANT SYSTEM BASES PRESSURE / TEMPERATURE LIMILi (Continued) start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

During heatup, the therma? gradients in the reactor vessel wall produce thermal stresses which vary free compressive at the inner wall to tensile at the outer wall. -Thermal-induced compressive-stresses -tend to-alleviate the l tensile stresses induced by the internal pressure. During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.

The reactor vessel materials have been tested to determine their' initial l

RTuor. The results of these tests are shown in GE NED0 24161, Revision 1. l l Reactor operation and resultant fast neutron, E>l Mev, fluence will cause an l increase in the RTuor. Therefore, an adjusted reference temperature, based upon the fluence, can be predicted using the proper revision of Regulatory Guide 1.99. The pressure-temperature limit curve Figures 3.4.6.1-1, 3.4.6.1-2, 3.4.6.1-3a, and 3.4.6.1-3b include predicted adjustments for this shift in RTwor at the end of indicated EFPY, as well as adjustments to account for the location of the pressure-sensing instruments.

l The actual shift in RTuor of the vessel material will be checked l periodically during operation by removing and evaluating, in accordanco with ASTM E185-82, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius vary l little, the measured transition shift for a sample can be adjusted with l confidence to the adjacent section of the reactor vessel.

The pressure-temperature limit lines shown in Figures 3.4.6.1-1, )

3.4.6.1-2, 3.4.6.1-h , and 3.4.6.1-3b have been provided to assure compliance l with the minimum temperature requirements of the 1983 revision to Appendix G

of 10CFR50. The conservative method of the Standard Review Plan has been used for heatup and cooldown.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.

l 1

l t

l l

BRUNSWICK - UNIT 1 B 3/4 4-4 Amendment No. l

r T.wo t 3. 4 ' .! -l 1200 1100 1000 Tp -

a S 900 I j 8 800 s

GI i m !

y 7@ ,

F b

s [ NORMAL OPERATION CORE NOT CRITICAL - UNIT 1

{g 600 55 MY r

/ HEATUP / COOLDOWN z ""'" """

E 500 3

us

' E OPERATETO RIGHT ANDOR BELOW 400 tiuirino ting

@ J BASES:

E 1. FUEL IN REACTOR f

I 2. s 16 EFPY 2M f 3,7,3 x n 3a uc ru ,3ugy j 4. RTNOT = 93'F (1/4 T)

5.15 PSI INSTRUMENT LOCATION 100 CORRECTION INCLUDED BOLTUP 6. REG. GUIDE 1.99 REV. 2 70*F 0 ' '

1'70 O 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

I FIGURE 3.4.6.1-2 L,,t 3,4. 0,t _ 2.

l PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL

- 7 i

NORMAL OPERATION WITH C0'E l CRITICAL 1200 , , , ,

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O 100 l200 300 400 500 GOO l (70) (181) l t

l (210) TEMPERATURE (* F) 1 BASES:

1 1. FUEL IN REACTOR

/ 2. i 16 ETPb 3.

7.1 X 10 NfCM2 > 1 MEV 4 RTp.,, = 81.4 (1/4 T) 5, 15 P$I INSTRLHENT LOCATION CCERECTION !NCL"ChQ

/ 6. REG GUIDE 1.99 REV. 2 \

NOTESf \\

1. f CPERATE TO RIGHT AND/CR EELOW LIMITING LINES 2./

INOICATES BCTH HEATUP AND CCCLOCWN RATE *

3. FRESSURE AND TEMPERATURE INTEREECTIONS NCTED BY PARENTHESES

/4 CPERATICH IN CRCSS-HATCHED AREA PERMITTED CNLY WHEN WATER LEVEL 13 WITHIN NORMAL RANCE FCR PCWER CPERATICN.

l BRUNSWICK - UNIT 1 3/4 4-16 Amendment No. g

In s, c t 3 C kI - 2_

1200 1100 1000 1

3m 8' 900 0

E ;

o 800 f

Ei J u> r y 700 [

F h / NORMAL OPERATION o 600 J CORE CRITICAL - UNIT 1 1 6 [ HEATUP / COOLDOWN E 560 ps'g 2 LIM; TING CURVE h 500 OPERATE TO RIGHT ANDOR BELOW i g LIMITING LINE '

N OPERATION IN CROSS-HATCHED AREA

@ 400 j PERMITTED ONLY WHEN WATER LEVEL IS WITHIN NORMAL RANGE FOR POWER

)

j u) f g fj OPERATION.

BASES, f/! 1. FUEL IN REACTOR V/:

EL/s 2. s 16 EFPY 200 j$j 3. 7.1 x 10" N/Cu2 > 1MEV Tf//n

[

""/'

j f 4. RTNOT = 93'F (1/4 T) 5.15 PSI INSTRUMENT LOCATION 100

[r[g[r[ff CORRECTION INCLUDED 1 //////A 6. REG GUIDE 1.99 REV. 2 f///////'

s//J//J/ r:

70 , 193 210' O 100 200 300 400 500 600 !

MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

FIGURE 3.4.6.1-3a PRESSURE-TEMPERATURE LIMITS g 5, 4 ,g. h REACTOR VESSEL

i. ' HYDROSTATIC AND LEAK TESTS '

1200 i > ,. i e i . e i . , i 4 , i . . , ,

/

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i 6 6 ., 6 i e ij , , ,

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i ! e i i e/s t i uf i i . i e e i i i .

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J ! e i e i e i i i ! / it i e i 6 ! i ! Ni e i 6 i 6 . . 4 i ie i i i e i i i .

' ' ' ' ' ' ' N ' ' ' '

200 3' ' ' ' ' ' ' ' ' ' ' ' '

' . . . i i . / i i , . . . . . e i . . . '. . si. . . . . . . .' ,' ,' .' . . .

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i e

i i i ei i i

e ee i e i

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Nt ig t i i 6 6

. 6 e i i e i i ,

t I

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i e i i i e i A' ! !

,/ i e i 6 i 6 6 , a 6 i l , i\ , 6 i i . , ei i ! . ii.

' ' ' ' ' ,'i 'N '

100 . i i *

i /i i .' . i

, 6 6 . , ,i 6

s. ,' ' ' , .

6 ' ' .' .'

. i . . .' ' .'

i 6 ! 4/ , i i i 6 , , ; ; 6 , e i;, i g, 6 i , i 6 , e i ,i.

t i i / i j i e i ) i ! 6 i ! it ( i AN , 6 e i*1 6 i i1 .

i s 6 /* i ! i i , i t . , ! 6e , i ii i i ,\ , e i i s t i e 6 i .

i i i e i/ . i e 6e i i i i i e ie . ! . 6 i6 i ; iNi i i .. i , , i i i +

70 80 90 100 110 120 130 140 150 60 170 190 TEMPERATURE (' F)

BASES:

1. FUEL IN REACTOR

2. REACTOR NOT CRITICAL J 3. REG. GUIDE 1,99 REV. 2 4 < 8 ETPY

5. 3.5 X 10 N/CM > 1 MEV

6. RT = 65 (1/4 T)

7. 15EIINSTRUMENTLOCATICHCCRRECTICNINCLUCED NOTES:

1. CPERATE TO RIGHT AND/CR EELOW LIMITING LINES

2.

INDICATES BOTH HEATUP AND COOLDOWN RATE 3 PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTHESIS

6. CPERATING LIMIT INDICATES TEMPERATURE REQUIRED IF TEST PRESSURE WAS EXCEEDED.

BRUNSUICK - UNIT 1 3/4 4-17 Amendment No. @

_Tn s,.t 3.d.(.t _g I

1200 ,. ,

d' I r l 2r 1100 '

2 r'

.F J

J 1000 4

/

V l

.* J 8 900 /

f x 1 I [

f 800 l l d

m ,

/ l y 700 p'

f i 8 7P '* "

{

E 600 i

E b 500 3 HYDROSTATIC y PRESSURE TEST - UNIT 1 400 LiumNG CURVE m

Q- OPERATE TO RIGHT AND/OR BELOW

-313 peig LIMITING LINE 300 BASES:

1. FUEL IN REACTOR 200 2. s 14 EFPY 8

3. 2.39 X 10" N/CM > iMEV (N16 Nozzle)

4. N16 NOZZLE RTNDT = 86.3*F (1/41)

5. BOTTOM HEAD REGION RTNDT = 10*F (1/4 T) 100 6. BELTLINE REGION RTNOT = 85 4*F (1/4 T) 7.15 PSI INSTRUMENT LOCATION

~'BOLTUP CORRECTION INCLUDED

". , I, ,,, 8. REACTOR NOT CRmCAL 0 ,, ,

60 70 80 90 100'110 120 130 140 150 160 170 180 190 200 210 220 230 240 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

l

. FIGURE 3.4.6.1-3b y* " q' i

PRESSURE-TEMPERATURE LIMITS 2

'~f "

l -

I l

REACTOR VESSEL l

s-l l ; HYDROSTATIC AND LEAK TESTS I r l l

1200 ! i ! ! . i . i i , e . .# # 6 i i i i i , . ,iii , ,,,,,,,, g; I

i ii i , ,

)

,N i 6 i . i . . . e i 6 i i e i i e r i t i is. 6 . ., 4 , i. ,, i ! . i ,j , . i j l 4 i i . . , i i i 4 6

i ! i ! 6 i iii. . , e i e iii ,, , .j , . , , j

,x i

i i i ! ! i ! i i e i ! i i e i ii . e i i . .,, i, N y. i ,

1100 ! ! !\ 6 e i

f

,' '.i

! > i i e i

. i !

' ', ' ' i i i i'

g, b,f g /'g , ' '

' + i

, f , , .

s'x i 6 i i i 6 i I ( 6 , i e a i . . 6 i i i.. ,y fi,, i i , ,

t ! i 6 K '

. , i e i ! e 4 e i i i i e i ,ii y. r , , , , , , . . )

l

! t i i i \ i ! , a e i e i i e i i e 6 . i 6 . y, g , ,$ , , , ,

('00 M A ',jW

' \

1000 ! ' ' ,'

! . , t A

. ! . . ! I e e !

i , . . t ,

* . i i i i i i i s . ! i si i e i i i i t i i e i ,

i i e i i , i a if, - 6 , . , i . . ,

! i i i ! 6 Ni ! i ! t i . i e i j . . i i .. w ye Ij i , i i , , , i i ! e i iT I 6 e 6 I i i i 6 e i e i , e , iirf. i i i . . , i . , i 900 a i !

', , . i e e is e i e i . . .' , i w . . , .' . . , i

' ' ' V

, , .jf ' ' , 'c; 'i ,' ' '

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ii i i i i i i x i i e i i i i i i i i i . ( , i ! i e y w . i g i . i , , , , ,

J l i .

i i i

I i ! i i i

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s. i 1

e i i 4

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6 i

e i

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, e i ! i vi

i e ,e i i e i e .' ' f' ', ' dw 'ie i ! ! 6 i 6 ! ! ! i i , ! i/! 6 i s 4 i i 6 , . , i I 800

, i i 6

. e i .

x i e e

i i i , ,

,! if

!' '80' i , , .

. , , ,' I l

! e i i ! i e si e i i 6 . i . . . , , y 6 i i _; ,ife e i e i , , ,

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i i i . , t i f/W-f

, ! . I e !\ i i e , e i i i i i ife i fi ! ,e i i i , , i 700 e

, , , e

. . . . . . . . . . . ! \ i ,i 6 . . e i i r

/.'! . , , .f i i , , , , e . , i .

i i i . . . i e i i i ex, 6 , i e i e i . . i , , i f , , 6 , i , !,,, , , ,

& i ii i i 6 i .

i ,,i l e i i

i i i ! 86 i i i i i y 4 . , s t isi , i i . ii.i i i i i , e 4 . 4 . !x e i l s i . v. i .e i iii ,,.. . . . .

600

' ' ' ' ' ' ' ' ' ' ' ' ' ' ' \ ' ' ' ' ' ' '. . ' ', ' ' i

', 'i .'

Lu i . . . . ! i i ! . , e i . , i i i s , . , , ,/ ./ i Q a i e i i i e i e i i e i . . y ei ei ff , i ! . I iiii i i , i i .

g ! ! i i . i i , e i i i i xi , 6 pie ii .

0,jd. ,! .... i e i i i i ,

e i i,i i ie i e i ! ! i 6 vv iii 3 i,6 . ,.. .6 i i , . . .

w ' ' ' ' ' ' ' ' ' ' ' # \ * ' ' ' ' ' ' ' ' ' ' '

C 500

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PA5ES:

1. FUEL IN REACTOR

2. -< 10 EF 7

3. 4.4 X 10 N/ > 1 MEV k 4 RT = 73 (1/4 T)

5. 15 b,,I INSTRUMENT LOCATION CORRECTICH INCLU& D

6. REG GUIDE 1.99 REV. 2

7. REACTCR NOT CRITICAL E2IE E -

1. CPERATE TO RIGHT AND/CR BELOW LIMITING LINIS

2.

INDICATES BOTH EEATUP AND COOLDOWN RATE

3. FRESSURE AND TDiPERATURE INTERSECTIONS NOTED BY PARENTEISES 4

CPERATING LIMIT INDICATES TDiPERATURE REQUIRED IF TEST FRESSURE WAS EXCEE0ED. /

BRUNSWICK - UNIT 1 3/4 4-18 Amendment No. @

1 set 3. 4. G. l - 3 b 1200 .r f

d' i

1100 f f

f f

d 1000 f f

.9 8' j 900 .f h

E /

800 /

h i e ,

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5 , r

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& 600 #

w SM yg a:

E b 500

! HYDROSTATIC g PRESSURE TEST - UNIT 1 3e 400 LIMITING CURVE kQ. OPERATE TO RIGHT ANDOR BELOW

-313 pelg UMITING LINE 300 i BASES.

1. FUEL IN REACTOR 2.s 16 EFPY 8

3. 2.73 X 10" N/CM > iMEV (N16 Nozzle)

4. Nif NOZZLE RTNDT = 89.7'F(1/4 T)

5. BOTTOM HEAD REGION RTNDT = 1D*F (1/4 T) 100 6. BELTLINE REGION RTNDT = 85.4*F (1/4 T)

_- ___ 7.15 PSI INSTRUMENT LOCATION

__ -.BOLTUP CORRECTION INCLUDED

, ,7,0*F, , 8. REACTOR NOT CRmCAL 0 ... .... ... ... ... ... ... ... . . ..

60 70 80 90 100 '110 120 130 140 150 160 170 180 190 200 210 220 230 240 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) 1 i

i I

Thi5 ye_ M4 bally MeIde d.

FIGURE 3.4.6.1-3c I PRESSUREeTEMPERATURE LIMITS a

REACTOR VESSEL i;

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~

70 90 100 110 120 130 140 150 160 170 180 f TEMPERATURE (' F1 PASES:

1. FUEL IN REACTOR 2.

$ 12 EFPb

3. 5.3 X 10 N/CM > 1 MEV 4 RT = 76' (1/4 T)

5. 1591 INSTRUMENT LOCATICN CCERECTION INC 'CED

6. REG. GUIOE 1.99 REV. 2

7. REACTOR NOT CRITICAL NO M

1. / OPERATE TO RIGHT AND/CR BELOW LIMITING LINES 2./

INDICATES BOTH EEATUP AND C00LDOWN RATE

/ PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTEESES OPERATING LIMIT INDICATES TEMPERATURE REQUIRED IF TEST PRESSURE WAS EXCEEDEDs ,

BRUNSWICK - UNIT 1 3/4 4-19 Amendrient No. Q

REACTOR COOLANT SYSTEM C

BASES i

PRESSURE / TEMPERATURE LIMITS (Continued) !

start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic ,

operation. t During heatua, the thermal gradients in the reactor vessel wall produce thermal stresses w11ch vary from compressive at the inner wall to tensile at the outer wall. Thermal-induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure. During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.

g RTm.

The reactor vessel materials have been tested to determine their initial The results of these tests are shown in GE NEDO 24161 .

Reactor operation and resultant fast neutron. E>l Mev, fluence will'bause an increase in the RT ,. Therefore, an adjusted reference temperature, based upon the fluence - can be predicted using the proper revision of Regulatory Guide 1.99.

The pressure-te rature limit curve Figures 4.6.1-3a, 3.4.6.1- - include predicted adjustments for this s3.4.6.1-1, 3.4.6.1-l RT, at the en f indicated EFPY as well as adjustments to account for the location of the pressure-sens1 instruments.

,od The actual shift in RTuor o e vessel material will be checked periodically during operation by removing and evaluating, in accordance with ASTM E185-82. reactor vessel material irradiation surveillance specimens l installed near the inside wall of the reactor vessel in the core area. Since '

the neutron spectra at the irradiation samples and vessel inside radius vary little, the measured transition shift for a sample can be adjusted with l confidence to the adjacent section of the reactor vessel.

\ >

The ressure-temperature 1 ines s own in Figures 3.4.6.1-1, 3.4.6.1- 3.4.6.1-3a 3.4.6.1- have been provided to assure complian with the minimum temperature requirements of the 1983 revision to Appendix G of 10CFR50. The conservative method of the Standard Review Plan has been used for heatup and cooldown.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.

l l

N ,

l l

BRUNSWICK - UNIT 1 B 3/4 4-4 Amendment No. @ l

.. .-. .- - . ~ . .- - - - . .-.- - . -. .. .-.. - - - - . - -. - - . . - _ . . =

i I

4 l

ENCLOSURE 8 j BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 )

NRC DOCKETS 50-325 AND 50-324 l l OPERATING LICENSES DPR-71 AND DPR-62

REQUEST FOR LICENSE AMENDMENTS l PRESSURE-TEMPERATURE LIMITS CURVES L

l 4

i l

l l

1 MARKED-UP TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 2 l 1

l

1 1 l

l l

l REACTOR COOLANT SYSTEM l

3/4.4.6 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM l

LIMITING CONDITION FOR OPERATION j 1

i i 3.4.6.1 The reactor coolant system temperature and pressure shall be limited '

in accordance with the limit lines shown on (1) Figure 3.4.6.1-1 for heatup by (

non-nuclear means, cooldown following a nuclear shutdown, and low power PHYSICS TESTS; (2) Figure 3.4.6.1-2 for operations with a critical core other

~

than low power PHYSICS TESTS or when the reactor vessel is vented; and (3) Figures 3.4.6.1-3af g.6.1-3b, @4ff.Wr@ as applicable f or inservice l hydrostatic or leak testing, with*

0D

a. A maximum heatup of 100*F in any one-hour period, except for inservice hydrostatic or leak testing at which time the maximum heatup shall not exceed 30* F in any one-hour pe riod.

b. A maximum cooldown of 100*F in any one-hour period except for -

inservice hydrostatic or leak testing at which time maximum cooldown shall not exceed 30*F in any one-hour period.

c. A maximum temperature change limited to 10*F in any one-hour period .

during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves, and

d. The reactor vessel flange'and head flange temperatures greater than or equal to 70*F when reactor vessel head bolting studs are under tension.

APPLICABILITY: At all times.

ACTION: l With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of the reactor coolant system; determine that the sys' tem remains l l

acceptable for continued operations, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.6.1.1 The reactor coolant system temperature and pressure shall be l determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

BRUNSWICK - UNIT 2 3/4 4-13 Amendment No. @

l l . ,

[

REACTOR COOLANT SYSTEM t

SURVEILLANCE REQUIREMENTS (Continued) ,

, 4.4.6.1.2 The reactor coolant system temperature and pressure shall be l l determined to be to the right of the criticality limit line of Figure 3.4.6.1-2 within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality.

4.4.6.1.3 The reactor material irradiation surveillance specimens shall be removed and examined to determine changes in material properties at the l intervals shown in Table 4.4.6.1.3-1. The results of these examinations shall be used to update Figures 3.4.6.1-1,3.4.6.1-2,3.4.6.1-3a,,3.4.6.1-3b,Gggp QEM,V.1rScT) as applicable. The cumulative effective full power years shall be determined at least once per 18 months.

b BRUNSWICK - UNIT 2 3/4 4-14 Amendment No. d2) i

.m

i i

FIGURE 3.4.6.1-1 l PRESSURE-TEMPERATURE LIMITS bM I~

REACTOR VESSEL '

(. +

NORMAL OPERATION WITH CORE NOT CRITIC'AL

\

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i i i i 8 8

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, i , i i i4 . . . , i . 6 i + . - i i * '

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200

, , i , , , i ,

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I i * -

i , f i i i i i 100 , i ; f , , , , , , i , , , , , , , , . y i , , , i . , , 6 , . . . . i i .

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100 300 400 500 60 )

O l l 200 (70) (170)

TEMPERATURE (* F)

BASES:

1. FUEL IN REACTCR

2. 116 EFPb N/

3. 7.1 X 10 2 > 1 MEV 4 = 93 O (CM 1/4 T)

5. RT"3,$IINSTRUMENTLOCATICNCCRRECTICHINCLUC 15

6. REG. GUIOE 1.99 REV. 2 NCTES:f

1. OPERATE TO RIGHT MD/CR BELOW LIMITING LINES 2

INDICATES BOTH EEATUP AND COOLDCWN RATE PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTHESIS g

-/-

BRUNSWICK - UNIT 2 3/4 4-15 Amendment No. @

i Tnse et 3. 4. L. - l 1200 1100 1000 900 e 1 f

800 j h '

d e i 8

700 h ,

b NORMAL OPERATION b 600 600 pse I

CORE NOT CRITICAL - UNIT 2 h HEATUP / COOLDOWN Z

500 h

3 w

h 400 OPERATE TO RIGHT ANDOR BCt.OW g '

r uumNG UNE w

300 f J 1. FUEL IN REACTOR

/

f 2. s 16 EFPY l 200

[ 3,7,,x,on scu ,3,gy s

[ 4. RTNDT = 81.4T (114 T)

. 100 5.15 PSIINSTRUMENT LOCATION )

CORRECTION INCLUDED l

;BOLTUP 6. REG. GUIDE 1.99 REV. 2

- 70 1 0 .. .

, 3,3 0 100 200 300 400 500 600 MIMMUM REACTOR VESSEL METAL TEMPERATURE (*F) i

)

l l , , FIGURE 3.4.6.1-2 i PRESSURE-TEMPERATURE LIMITS %,d. 3. 'W 1 -

REACTOR VESSEL

, /f- #~ NORMEL OPERATION WITH CORE CRITICAL i < ,

l 1 00 ,

/

1100 s ,

/ ;

N .r i l N / 1

\ l / 6 1000

\

s l' x' r' '

h

\ l I h /

/

\ J $ '

/

900 \L i l

o

[ /

f

% F Q ;

j % J .f

~ '

f B00 g l ,

\T j w !

/ /

h 700 \\ /

l

/

a T j r ~

\ / - /

y GOO \ f

,/

^ '

5 q I \ /

m II \ /

1 500 f

l' i

\ /

/ l j

/t

k I / N 400 g I

/ /

f

\h 300 t/

/L 1A

/ i, /

,f y f

fl #

16

/

i

\

s X

x

\

+

/ / \ i i / # / -

N I I

I I / // / \

200

,yf; ., ,

/// ) . >

/// / / \

)F J / .e 't 100 ,

// /

fp , ,;/ y,/,

h y s

! ff// / / / \

l #// / fl /if 8 ffl/ / / / /L \

/7 D V /r /if Vi 't j 0 100 00 300 400 500 GOO i

(2 0) TEMPERATURE (* F)

PASES:

1. FUEL IN RIACTCR

2. 115EFP}7

3. 7.1 X 10 N/CM2 > 1 ICV 4 RT ,, = 93 (1/4 T)

5. 15 P$I INSTRUMENT LOCATION CCRRECTION INCL- ED

6. REG. GUIDE 1.99 REV. 2 NOTE.

1. / CPEP. ATE TC RIGHT AND/CR BELOW LIMITING LIrrES 2

INDICATES BCTH HEATUP AND CCCLDOWN RATE f[. PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTHESES OPERATION IN CRCSS-HATCHED ARIA PERMITTED CNLY WHEN WATER LEVEL

" w1THINJCFM.JgGE FCR PCWER CPERAJCN BRUNSWICK - UNIT 2 3/4 4-16 Amendment No. @

(b w. . , .

s 1

1ns ef t 3.4. G, l - 2

, 1200 ,,

i6 ,

I i

1100 1000 'l ,

j i E f I

~g li i 2 900 ['

I l

6 f

x L

I o

F-800 .I I

e D

i ll D -

11 y 700 , i,,

4 ,,,,,,,,, ,,,,,,,,, ,,, ,,,,,

m 660 psig . r S NORMAL OPERATION U CORE CRITICAL - UNIT 2 600 h HEATUP / COOLDOWN Z LIMITING CURVE b 500 , _,

OPERATE TO RIGHT AND/OR BELOW

.E j ii LIMITING LINE W !

Z J

! CPERATION IN CROSS-HATCHED AREA 5

u) 400 i i ,,

PERMITTED ONLY WHEN WATER LEVEL IS WITHIN NORMAL RANGE FOR POWER i

i i W OPERATION. -

e i !

300 l fi BASES.

, f, ,

h ! 1. FUEL IN REACTOR

/A i i l j j 2. s 16 EFPY 200 ,, m,

[

,, ,,,, , ,,,,,, 3 7.1 x 10'7 N!CM2 > 1MEV ii i ! i/j ! i ! I i i!

f , #l l jl l'; 4. RTNDT = 81.4*F (1/4 T)

' ' 'i / V I' A ' i' '

100 5.15 PSI INSTRUMENT LOCATION l

[7 l llll iI CORRECTION INCLUDED

/ 4/ iA M / Q_

.i ! I

6. REG. GUIDE 1.99 REV. 2 lill i,ii ,

i / Vi /V 21 7 / i/ v n i 1

i 11 i4 i 70 181 210 O 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) 1

I l

l

* . ~ - -

l FIGURE 3.6.6.1-3a L d 3A.c.1 3q PRESSURE-TEMPERATURE LIMITS ,

REACTOR VESSEL l i

i HYDROSTATIC AND LEAK TESTS 1

i I

i 120 6 i . . . . . . 6 e i i , 6 i , , . . i i 6 . . . .iii .. i .,, . . . /

i . ,

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gg rs i

, A, i

i . .

i.i i .4 i ...

i 6 i

...i 6 . i .

...iv gyg !<noni

. .ki . I i 0 . I i . ,,I i l I i , 6 ..i h a h i I . . . . 8 . . . 1 l hI. . . . , .

. ! 6\ i i i e i e i . .6 i i i 6 , ii. . . i e i . . 6 i . I i , < . f.. . , i . .

. i 6 ,% i , 4 e i i . !6 .e i i e i i.! i e i i i i . ! i . i 6 i i . / 6 i . . . .

1000 i i i ,

N! .

,Xi i i ,

i i

e t

i . . .

i i i a

. i' .' '

6 e i i .

I

. i .

i , , I i i

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4

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e i

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. 6 i . . . .s i . . . . ! i , i i . . , , i i 6 i i i .. i/i .; . , i .. , 1 0

e i . .

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i i '.

. i i ,'

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, i , ,' '. .

6 .

/ i .

m' ', #' '

I

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^-

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! ! i e i . i

. i i i 4 . . . .is. . . . 6 . . . . . ... , eii . ! .f , 6 x . . , mon, 800

, , , , , , , ,,,3 , , , , , , , , , ,,, , , , , , ,/, , , , , 3 , ,/ , ,

. i , i i i i , , i . .x .! . . , . . . . . . . 6 ,i, ,f!, . . . . H . s.., . . . i i i , i . . i 6 . . . . (. . . . i i . i . i.. i i.i y... i i . , r y , ... . .

. . i 6 . . . . . i . 4 x.ii . . . . . . i i . .., f,i., . , .( w o ). f . . i . . . .

c

_' 7.00 , . . . i . ,

', , , , . .y . , , i . . . . . . .if ' '. ' '

l

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a. . i . , . . . . . . . i 6 ,x . . . . 6 . , y,i . . . i si ii, i . . . . . .

. .f M.

. . . . . , ,. . . . , , i is ,4 . i if, . 4 i i,i, i4 si . , . .

. t i i 4 . . . . i .6 . . i . i xi . i i i /6 s . .f . .4 . . . . .. . i . .

,. 0 0 e f , g; w , , , , , , , , , , , , , , g, , , , ,f , , , , , , , , , , ,, , .

g; i i + . . . i . , , a i . . . isti i f iv 30 It i . . i , i . ., . , '

8 . . .

s i

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i 4

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6 .

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4 . i . . i . . .

i , 6 . i . , i i.,i u! i . . if, i\ . . i . . . . . i ! . !

. . . . . . . . ..# , pq ,4 . ./ i 5 . i. . . i . i i . . i . . . . . . . . . . . i ,

400 , , . . . . . , i . , , m. ./i i , , . x. . . . . i . . . . . , , . . . . . . . f i

. . i . . . . . . ., i v.4 . i i is , ,,i . . . . i . . i , 6 . . . .i

, . . . . . . . . 4 , i _uai . /.ii. . i i.x ie 4 i . . . 4 i . . . i i e ! i. . . . i i ' '

. . . , , . . . 6 i . 4 9i / ...e i6 i i \i i ! 6 i . . . . i t i 4 . . . ii..

, . . . . . . . . . i i if , i . , , . .. x... . . . i . . , . . . . . . i.

.00 , ,, , , , , ,,f, , , , , . . , , 3 , , . , , , , , , , ,,,, ....

(2993 . , , i c mea , i i , . o, i i . . . i 4 . i ai i i i i 4 6 . . . . i . . .i'. ' ' . !

, i i 1 6 i i . . , . ! iiit ' ' ' ' I

. . . . , i s . . . . . if, i 6 . , i . i i i i i 6 \i

. i e , I i .

6 6 6 i . ! ' ' ' ' ' ' I i i i . . . . . . i i / i! . e . ! ! i e t \' ! . i .

i i i e i i i i . i . i . i . i i i i ' ' ' ' '

. i . i . . . i e, e i . . . e i e i i .s 200 y , , , , , , , , ,f , , , , . , , , , , , , , , ,,3 , , , , . , , , , , , , , i , . .

g i . . . . i , i vi , i , , . . , . . . . . 6 i 6 , x. . ! ! eii, . . . . . . . ' _;_ _.

& . . i . . 4 . i .i., i i . , . . t '

. . . 6 . . . io. . 6 . , , i . . \6 . .

j i . . . . i ,/. j i . . i . i e i e i e . . i , i i\. i , i,e 6 i i i i 100 . . . . . f, ,,

', . '. . . . . . ' '. s' '. . . ,',

i i , i . . i ' ' ' ' '

. . . . . . 6 .f i ,i ... . . . . ; . . . . . , . . iiN. 4 6 4 i j . 6 i i . 6/ . .. 6 i 6 . . i . i i e i , i . . . .i.\ e i i e i . i i e t '

, i i i i i ei . ' '

, . . , , , f. . .. , , , . . . i . . . . . . . . . i.a i i i i i . . . i v., , ,ii i . . . . . . . . . . . . . . , .. i ti . . i * . i '...

70 80 90 100 110 120 130 140 15 160 170 180 TEMPERATURE (' F1

$ASES:

1. FUIL IN REACTCR

2. REACTCR NOT CRITICAL

3. REG, GUIOE 1.99 REV. 2 I

4. -< 8 EFPY 17 l

5. 3.5 x 10 N/CM2 > 1 MEV

6. RT = 77 (1/4 T)

7. 153,,I$ INSTRUMENT LOCATICN CCRRECTICN IN 'UOED NOT!S-

1. CPERATE TO RICHT AND/CR BELOW LIMITING LINES

2.

INDICATES BOTH HEATUP AND CCCLDOWN RATE

3. PRESSURE AND TEMPERATURE INTERSECTICNS NOTED BY PARENTHESIS

/

CFERATING LIMIT INDICATES T &.PERATURE REOUIRED IP TEST PRISSURE WAS_$$ M DED-BRUNSMICK - UNIT 2 3/4 4-17 Amendment No. h i

M ,.a,- .

., , t .

Lut 3. 4. 6.1 - 3 a.

1200 f II I

....I I il 1100 Iil

\1

~

'l f'

1000 Ii/ -~-

_ i/

.9 /

g / !

E 900 g/ '

$ 'I

)

~C I

a. !

o F-800 1 [

w 1 M ! /1 h 700 , l- n, /'

8 l 7 '

u 600

! /l g , ,n, r

& +

2 541 psig j ; ; ,

~

y a

500 I

~,~,'

ii fi i

HYDROSTATIC g --

..._4. .4. _,. l PRESSURE TEST - UNIT 2 5 400 , ,' ,ll ', l ln n, , , ,

n l LIMITING CURVE

!O Ll_. !! !

' !! Hi i !! !

'!!!!! I! '

300 hk

,, n,, ,,,, n, 313 psig l!'!

l! i,l n,, ,,,,

OPERATE TO RIGHT AND/OR BELOW LIMITING LINE OASES-

~

I- i il i iij ti i i i i illi i i i

[" 'T t i l

~

r i i i i liii i i i F~ i j j i i li i illl i i i 1. FUEL IN REACTOR TTt , ii i ii iili ; i liii i T 2. s 14 EFPY IIII

%h ilii iiii l

i!!!

f-N ii!i M

i! I ll i4i lll f

!Ii i 17 2

3. 2.39 X 10 N/CM > 1MEV (N16 Nozzle)

4. N16 NOZZLE RTNDT = 78.6*F (1/4 T) ll llll 'l' 'I lll S. BOTTOM HEAD REGION RTNOT = 40*F (1/4 T) 100 ,,,, ,,,, ,,,, ,,,, ,,,, ,,,,

~m , 6. BELTLINE REGION RTNDT = 81.8'F (1/4 T)

IITI h,TITI !i!i tiii !i!! TiTii !!i I 7.15 PSI INSTRUMENT LOCATION h

iiT; BOLTUP 70*F -

IIiI IIII hh Ii6! jggi

.!'.',ll'

!! 'l l' f CORRECTION INCLUDED

8. REACTOR NOT CRITICAL 0 . . . , , , . , , ,

60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

FIGURE 3.4.6.1-3b PRESSURE-TEMPERATURE LIMITS % ,,A 1(1.E.1-3L REACTOR VESSEL HYDROSTATIC AND LEAK TESTS l

) <

1200 , , . ; , ,, ,, ,, , , . . ,,,, , , , i. . ,, , , . , . . , , ,,,i f.,

e ii, iiii i .6 l

. i ,i.. i i ! >! t i . t t6 i . ,! , ii i, ei.,,

, i i ii .i, . , , . .iii i i i i i. 6 ii i , . . i i i , i,iv .i.i i s . i i, i 6 a . 6 , ! e it s e i i t t ! 6 ! i . t i t i ! , .f 4 s i i .

l 1100 ii, i . . . 6 i

. i ,

. . ii.

i i,.

.. i .

4 .

. . i .

, , i i i i i i .

,, . i i

, ifp,f,,,,

s

, fi l l

xii 6 . . i i i 6 . . 6 ! ! ! $ i i i Le (ic901 l x! . i i , , 4 * , , , , i !e i . . i 6 . v4 i . , . . I N6 t ! i . t ! , t ! i ! , . !

, 6f i Uur# t /i i ! ....

.y i i , , i . , ii i i .. . . . . i i . . . i,f.e.. , , ,

1000 , s , , , ,, , , i , , , , , , , , , , , , , ,, i , , , , , ,f, , , ,,, , , ,

, x iii 6 i i i ei.6 i i i i i i i i + - . 4 .. . i , y, q .ia . , . .

\t i i ! t6 6 6 ! i 6 ! I v , 6 i . i . i ii. ! I i fi. A 6 : C3 i . .

. N6 i i . i i , , e i , , , i i . . i ! . , ,,. . . v i. - , ,m . . i .

}

900 .

e i . ", x ,'

i 6 i Ni6 e 6 .

i i

i

, i i .

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6 , i i exi i . . . 4, ,, e i 6 i i / i i e i . -- i . . .

800

. i . , ,,y . ..i . . ,6 i . . i i i f . , i , x . i ma,

, , , , , , i g, , , , , , , ,,

i ,i

, , , , , , , , , ,f, ,, , , , g , , ,f , , , ,

i i e i l\ i $ 6 i i i 6 e i 6 i 6 yi i i 6 i 6 i & i if i . . i !

a i i i i . si,ie ! i 6 6 i 6,. v. 4 ii i . i r- eii i i i 2 i6 i ! . x6 6 6 6 i i i i 6 i i i /! i. . . ! lir20) , r.6 .. . . . .

=

j 700 ! '

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e e

i i

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. i 6 9

. , l/

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. .' 8 i

! i.i -ie e e i . i

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'N

y 600 i

t , e 'i ,', ,' ' i Ni i e . / ' ' ' ,' ' i

,' L ' ,r' i i 6#,'s i i i e i . ' .'

. , i ,

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01 i i i ! i e i ! + . . .ii , ! is i ifi i # , ei . t i 1 . 4 i . i ,

m

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i . . . . i .

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. , , . . 6 . +

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(440) ., ; , , i i . '. . i i i i . 'g' ' G' @ i , , , . , i,i, , ,i ', , . .' .'

l 400 i i i ,

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' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' N' ' ' ' ' ' ' ' ' ' ' ' ' '

300 '

< (298) i i i 'i s ' m' c, ' '. '

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200 t. . . . . . . v, 4 . . . , ,, , ;, , i , , y + i i , , , i . . . . . .. .

m ,,- ,,,, , , f, , , , , , , , ,, , , , , , , , , gi, , , , , , , , , , ,, . . . ,

i . ..! I i/ i. i i i 4 . I it I i ! 6

. . I ! .Ni I ! , . 8 . . l . ii ' ' ' ! !

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i 6

i l

. i , ! n6 . i 6 . i , i . i ! , i , i i i . . .it , i i ! , . 6 ! > i i 100 4'ii' ' ' * ' ' ' ' ' ' ' ' ' ' ' '

' ' ' ' ' ' ' ' ' " ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' l I

. . 'i , , ./ . , i i , i , , , , , , , ! . . . , e ,, N . i . , , . . . , ! . i ' ' ' .

i ., i i vi i i i ,,i , i , . i ! ! i i . . i , , . i .3 , 6 i . 6i i i . i ' ' i i

. , i . . ' '

. i i ,

if . i i i ii . . , i . . i i . i i i i e i . ! x, i . i i i i !

, i , , i , t i i , . . i i . '

! . . if i, , ,. . ... . . . i . . , . , , ,i , \ . .

, i . . . . . i . i e i . e i * ' . '

t . s f. i. i , a 6 i , , , e i . ! \e i .

70 0 90 100 110 120 130 140 150 160 170 180 19C l

TEMPERATURE (* F1 BASES-

1. FUEL IN REACTCR

2. -< 10 EFPY17

3. 4.4 X 10 N/CM2 > 1 MEV 4 RT ,. = 82 (1/4 T)

5. 15 P$! INSTRLHENT LCCATION CORRECTICH I: LUCED

6. REG GUIDE 1.99 REV. 2

7. REACTCR NOT CRITICAL NOTE

1. CPERATE TO R!GHT AND/CR BELCW LIMITING LINES #

. 2.

INDICATES BOTH HEATUP AND CCCLDOWN RATE 3 PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTEISES .

l. CPERATING LIMIT INDICATES TEMPERATURE REQUIRED IF TEST PRESSURE WAS EXCEE0ED.

BRUNS'JICK - UNIT 2 3/4 4-18 Amendment No. (CD

u u t 3. 4 fo.) - 36 1200 , n , ,

i, ,

/

4 . . I I 6 I II l 1100 ,

i h

r.ui 1000 , , n ,j ,

I l f' i

^ I c) I i a t i i /I !

S 900 F TT -~~~~~T i j il i i o ,

,,f i 6 l

/ [i 3 --

ct , i di o

s 800 j

p--_ ll</4{ l 4 a t.L1 ! .

/ \

4 m I i /t 11 J

g 700

> i uv ,

i n i

,7

! ! 'l i l r ! j 'i i ii i O I i ift it i li 4 a

g 600 g , ,, on un ni / ii in in e li ! un HH i !q n!

! Z ll l 541 psig fu'-----

h ! ,lll ; , , lll h ' ' ' ' " ' ' "" ' ' ' '

s 500 i i o i i ! ii ! ! i 1 a i i u i i ! ! ! i i HYDROSTATIC g

iii, ll iii i

ii i i

F TI~ T-l ii t -----

i T PRESSURE TEST - UNIT 2 q

w 400 ,,,,

',,,, i LIMITING CURVE l,, iii

@ ii l ! ll till I e !Ii li i l ii '!'I I

,.---l OPERATE TO RIGHT AND/OR BELOW CL lill,ii Ii r '

Ul I

313 psig li ___

l TT-- y LIMITING LINE fThi ! ifj l% ll l l BASES.

i [!! ! illl

'~---

1. FUEL IN REACTOR O iiii i ii iiii ; ii iill it i ? 2. s; 16 EFPY

3. 2.73 X 10'7 N/CM2 > iMEV (N16 Nozzle) j li!! !ill ITN ! N'-~~ Nf" iiei MT 'ini 'itiT 77T TT TTT~ 'Ti T 4. N15 NOZZLE RTNDT = 82.0*F (1/4 T) 2it. 3,,,i TIIi

,i

$ i,i, I

WTT II ii i . T.

IIi T- .14 1liii i

5. BOTTOM HEAD REGION RTNDT = 40*F (1/4 T) 100 .

6. BELTLINE REGION RTNDT = 81.8'F (1/4 T) hf l bh UN. !l6 f 7.15 PSI INSTRUMENT LOCATION h

11 L BOLTUP -

70"F -

khh Im yt t !!!! ! ,l lll 1

1 8. REACTOR NOT CRITICAL 0 . . . . . . . . . . .

60 70 80 90 100 110 120 130 140 150 150 170 180 190 200 210 220 230 240 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

%s Pm e ihOWH-- 1 de teh d .

FICURE 3.4.6.1-3c %

N PRESSURE TEMPERATURE LIMITS REACTOR VESSEL N

HYDROSTATIC AND LEAK TESTS 1200 y i ! # . . . . , i i . . ., , , ,, i . . . i ii , , , , , . , , ,

, . i , i , y, i Ni ! . i , i i . . ! 6 i i i i ! ! i e i i i . e . . , i , i , . , i , , i f, 6 ., , .

isii ! i ! , i e i , ! , i i i ,i,, 6 i . . . , i , i , . , ,, ,f6 . .,,6 i ,Ni , ! i e i i eii . . . ! ii i i i , i i i , e i e , i.... fe , , . . , ,

1100 ' ' '\1n '

' ' ' f[*Tf='

. i . , , , . . . . . . . . .

. . . i , , , , . ,f . , , i

! i .! ! i . 3 i e i 1 e i e i i , i i i ii,i , , Ne l e i /

i N i i i i e i i , a 6

)

i( vj os! f4 gy

! 6 . e , e i i 4 i e i i f, i . , ,

i ! is i i i , e i ii i i . i ,i ! . i . , , , 1 4 ,

' '\' ' ' ' '

1000 ' '

i , i. . N .

e i i i'

f, I

t i i l 6 \ i ! s i i t a i ! . i i rt i i i i ! i i i i f. ) s i 1 . s i ; . .

i ! i t ! i i i e i i i e i i . , i e i . 1 I i i e ij i i i , N . i .

I i t i ! \ i ' i i ! ! ! i I i 6 , ! , i l i , , e i i / . e i e i e , l , .

' ' ' ' ' ' ' ' ' ' ' ' ' ' ' a 900 ' ' '

~

\' ' ' ' ' ' ' '

. . ,' .' if' ' , '

! 6 i

. i i !

Ni

. \

. i i i i i i . .

i , .

. i e i

.i i e !

i ifii i . .

i i e .

v,'e. .

, i i ! i i i .N, ... 6 i i , i e i i i v.,i i . i , -

6 , +. ,

i ! 4! i ,N ! ,. 4#! i e i i i i i f. ! i i ! e i i . i . . i

' ' ' ' ' ' ' ' ' ' ' ' ' ' I ,,',

800 . . . , , , .'

' ' ' \

. , ,s , .' ,' , ' ', ' ' ' ' ' ' '

, i , i , i , , , . , , , f , , , , ,

a , , ,

i . . . i 6 ii ! . . i Ni i , i . . . i i i i e i , i vi i , ! . . . . a i. ve,i, 6 i i e i 6 e i , ii.i i e i ! ) i i ,

i\i ! t e i if i i . e i e i i i . i i / i i i.-- J

. i , , e t i 6 i ! i ts i , , . i e i 4 , a 6 ifi 6 i 4 , , i i ( / O -- ) i f1 , i , .

700

' ' ' ' ' ' ' ' ' ' i ' A' ' ' ' '

. i

', i , . , e i . , ,i ,' i . i i,i.

, # ,' f.'.' ' ' .. '. ' ,' ' ' ' '

' I ' '. .' '

,A . .' ' ' '.

! e i 6 i 6 $ i i i ! ! .,e iN t , i i iie i 6 eisj i ! e i i ! i e i . ./ i ,

i i_ .i. i 3 . i . . . i , i

, i . i

. ... . ! i i N. , i , i i i i i of ., . . . . .f, , i , , ....

, , e i i i i . . i . i Aii. , . , , i vi .i i i . i r. . . i , . . .,, ,

W G

GOO ' ' ' '

! , i i

6

'\

.,y ,

./ , .' ,i

, , .' f,,

.e'# i.6 i i e i , i i ! , ! , i ! /i6 6 ,6 i i i\i i '. ',. i 8

i . . ! ! I i y ! , , , 4 . . t . i i e . , , ,x 6 i i ri , i i i i i

e . e i i i ,

m W

500 i i . ,

i i , i i !

i i i , i 4 .x ,

' ' N e if i i ! i f i6

', ' ' /gii,,

p' , , .

, , , i e . . '. , , , , , i , , , .. . , , , . , ,

', ' .' .' g'

- . , i , , i i i , i i i i e i , , 6 . . Nfi sy f,i. 30, t . . . , ii !

. . ; . 6 i , i i ismf, \ 4 4

. , , i . , i gt i , i , . , , i . . . i . . .., .

(At0) ' ' ' ' ' ' ' ' ' ' ' ' ' ' W! 'd' ' ' ' ' ' ' ' ' ' ' ' ' ' ' '

400 ,' ', ' '

e i

C' mi,

. ,i C W i 1

, i , i i , , i 6 e , mi, , s . .! ,i x6 . . . 6 4 i . . . 4 i , i i e i i i .

i . 4 i ! i , * , . . . < ,i . ./ , ,,., iN . . . . i 6 e ii, ,,i. i... ....

f a . . i i . i e i s i H i . . fi i i.,i i A6 . i . , e ! ... ,,i! i . ' .. .

' ' ' ' ' ' ' ' ' ' * ' ' V ' ' ' \' ' ' ' ' ' ' ' ' ' ' ' '

~00 1

. j /4 . . , '. . . . ,\ + . . '.

(299) . . i .

, , i. . i . .

. i , i r, aNga , , , , . . ifi. .. iii; i i i i\ . . . , i . . . i . . > > . ... .

i

, , , , i i 6 . . , , , ..e y , , i. , i e ! .i . . (i . ! . . . . , .. . . i . t . . .

, , . . , i , , i . . , ,, v, . ,i6 . . . 4 . . .. s,,, ! , . . . . . . . . i . .' ' .' '

200 ~hs . . . , i . . i e i . ./ 4 . . . . . i . . , 6 .. .N. . i . . i i i i . . i i . ' .

y ,, , , , , , , , , ,f, , , , , , , , , , , ,, , N_, , , , , , , , , , , , ,

y .. , , . . . i , i f i , , i . i .4 . , i e , . . Ni i 6 . i i , , . . . . . ., ' '

, , , . . , , . . i , f, , i , , . . . .i. . . . . . . .s , , i i i , . . i , . i. ,

p ,, , , , , . . i ij , , , , , . . . , i , . . .. . . i !T t , , i . , i i . .- i i.'

100 * ' ' i

. . , i i e i ,

i i /t i i j!

. . . . i ,i, e i .' . .i As , .

. i . . '

. i. '

, i 6 . 4 i , ! 4 if . . , , i i .. . .! i i ii ix.i , , i . i 'ie

, i e i e i i j i/ ! l i .6 i .! i ! e ! .i , i i i . , i i i *N i , i I 8 ' ' i ' ' ' '

, , i , . , , i f, i , , i , , . . . , i ii . i . . i i i iiN i i i , . . . . ' . '

. , , , , , , , f.. . . , , , . . . , , , . .. , , , . . i i. . , ,

A i i , , ' . ' ' '

70 140 150 1 170 180 19C GO O 100 110 120 130 TEMPERATURE (' F)

PASES:

1. FUEL IN RIACTCR

2. < 12 EFF 7 2

3. -5.3 X 10 N/CM > 1 MEV 4 RT , = 66 (1/4 T)

N

5. 15 E$I !NSTRUMENT LOCATICN CCRRICTION INCLUCED

6. RIG. GU!:I 1.93 RIV. 2 7 REACTOR NOT CRIT! CAL NCT!S-

1. CPERATE TO RIGHT AC/CR BELOW LIMITING LINES

2.

ICICATES BOTH HEATUP AND COCLDOWN RATE

3. FRESSURE AC TEMPERATURE INTERSECTICNS NOTED BY PARENTHESIS 4

CPERA!!NG LIMIT IC ICATES TEMPERATURE REQUIRED IF TEST FRESSURI WAS EXCEE0ED. '

BIIDNSWICK - UNIT 2 3/4 4 19 Amendment No. (@

I REACTOR COOLANT SYSTEM SASES PRESSURE / TEMPERATURE LIMITS (Continued) start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic I operation.

During heatu). the thermal gradients in the reactor vessel wall produce thermal stresses w1ich vary from compressive at the inner wall to tensile at the outer wall. Thermally induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure. During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compress _ive at the outer wall.

g g,7 g _ g '

The reactor vessel materials have been tested to determine their initial RTuor. The results of these tests are shown in GE NEDOOl6 Reactor operation and resultant fast neutron. E>l Mev, fluence will cause an increase in the RTuo7 Therefore, an adjusted reference temperature, based upon the fluence, can be predicted using the proper revision of Regulatory Guide 1.99.

The pressure / temperature limit curves Figures 3.4. 6.1-1. 3.4. 6.1-2. @

3.4.6.1-3a, 6a 3.4.6.1-30 include predicted adjustments for this shift in

" ' RTuo7 at the end of indicatedLEFPY, as well as adjustments to account for the location of the pressure-sensing ' struments.

L The actual shift in RTuor o the vessel material will be checked periodically during operation by removing and evaluating in accordance with ASTM E185-82, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius vary little, the measured transition shift for a sample can be adjusted with 3 confidence to the adjacent section of the reactor vessel,

' an The pressure /temperatur limi lines own in Figures 3.4.6.1-1. 3.4.6.1-2.

(@b 3.4.6.1-3a grga .4.6.1- ave been provided to assure compliance with l

the minimum temperature requirements of the 1983 revision to A)pendix G of 10CFR50. The conservative method of the Standard Review Plan las been used for heatup and cooldown.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.

BRUNSWICK - UNIT 2 B 3/4 4-4 AmendmentNo.(hI

ML20133F431

Text

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