ML20134E126
| ML20134E126 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/22/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20134E122 | List: |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 NUDOCS 9610310297 | |
| Download: ML20134E126 (20) | |
Text
,- . . . .. ., ... . . . - - . -..-- . .....-.- .. . ._ .. ~ ..- ..- - ... . - , . --
Att0chment 3 t3 GNR3-96/00120 Pr.go 1 cf 10 ,
I i
Attachment 3 Mark-ups of Affected Technical Specifications Pages and Proposed Replacement Curves for the Request for Revision to the Pressure-Temperature Curves (PCOL 96/10) for Grand Gulf Nuclear Station l
l I
(
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I 4
l 9610310297 961022
~.
RCS P/T Limits 3.4.11 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. --.------NOTE--------- C.1 Initiate action to Immediately Required Action C.2 restore parameter (s) shall be completed if to within limits.
this Condition is entered. A_N,Q C.2 Determine RCS is Prior to l
Requirements of the acceptable for entering MODE 2 LCO not met in other operation. or 3 i than MODES 1, 2, !
and 3. l I
l SURVEILLANCE REQUIREMENTS
! SURVEILLANCE FREQUENCY l
SR 3.4.11.1 ----.---...----.---NOTE--------------------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
Verify: 30 minutes
l within the limits of igure 3.4.11 ,
and l h< 9[AD Ch) {
I b. RCS heatup and cooldown rates are s j 100'F in any I hour period.
l l . (continued) l .
pg o g tbt C.w/tS t M E N EC M b l!
Eoweg. VSAR. b GRAND GULF 3.4-27 Amendment No. 120 l
. i RCS P/T Limits 3.4.11 d
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY i
.SR 3.4.11.2 -------------------NOTE--------------------
Only required to be met during control rod withdrawal for the purpose of achieving '
i criticality, i
Verify RCS pressure and RCS temperature are Once within.
within the criticality limits specified in 15 minutes Figure 3.411-1A) be9'd [%e c.u.Ad prior to l EN'M'< fW b A (fFN)* $ raw for Ilt b-9 ['f C h b ki l the purpose of
, achieving
. criticality SR 3.4.11.3 -------------------NOTE--------------------
Only required to be met in MODES 1, 2, 3, and 4 with reactor steam done pressure a: 25 psig during recirculation pump start.
Verify the difference between the botton Once within
! head coolant temperature and the reactor 15 minutes pressure vessel (RPV) coolant temperature prior to each is as 100*F. startup of a recirculation pump SR 3.4.11.4 --.----------------NOTE--------------------
l Only required to be met in MODES 1, 2, 3, j and 4 during recirculation pump start. !
Verify the difference between the reactor Once within coolant temperature in the recirculation 15 minutes loop to be started and the RPV coolant prior to each temperature is as 50*F. startup of :
recirculation pump (c;.1tinued)
GRAND GULF 3.4-28 Amendment No. 120
! 3 )
& b ~
\
[ H 4/ tot 44/c Ttsh4 L'M'Y Rt2 P T LIMI, - - l; A - INSERvlCE LEAK E HYM0iing 50b6 8 - C ?f^* ""^' "" ". 000;",0^ LIMIT a.lhQ C -mn:e er :::T::=.=;.T s :. :::L ,;-. uMIT r -
1 1400 A B C CA' gg l
, a _ ;
. . . . . , ~ , , ,i
' y n5 >5 5$5.-[
e r i
's r 1200 -
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. a n - a-
==~ * ,
I r X X " " ' ' ' ' #' I'" L UW F F I
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J l
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? Q V A , ,,... - - - _ _O .
- 1000 ,' ' '
="?*'
V g ,
3, u ,r r%
r J a a a r
c'
, ,*,"", , . .'.*_/ ::
_0_-_ *g-
. ,m a u.
>- y _ _ _ _.. w,,
r 's. !
' ~7 g800 a r u
, m r
r r
w ,, , __ _ .- .. .. .,. _j ;
Z
'"" s s ?^^ L C O , 1
,a a C ^ A si, -
.o , ,
m u m
' 600 l l n---- --.- a 7 7 p ,.ar:-_= : m--
, __. ,;; . : - _: ,% .__a-s ,
6 i P,,..,,,, vr G. _ ivwy M i m wa l, u i
u - ,
Ire'_r::; ; ; :-ev L k1 7 ---
-t ; i .
T I, Ih 400 ' -
--i ,
i .
. . --1 <
BOLT UP LIMIT r # 312 peng --- -
327 '~
' 'li /SY '
/
200 -- ,,,ty 2r w \#
i,c _ si' ACCEPTABLE REGION OF OPERATION IS TO THE 7 ,
/ g(L a y: g.3s ue , .. . >
R!cHT OF THE APPLICABLE CURVE.
av s ,_ ___ .. a P ., wi i . ww w a. w 'us 0
0 100 h 200 p
[ g.,,,,, 300 RPV METAL TEMPERATURE FF) su g jgggg A MM l ,
a$u.es cut veS.
MINIMUM REACTOR VESSEL METAL TEMPERATURE VS. REACTOR VESSEL PRESSURE FIGURE 3.4.11-1
' ~
GRAND Gul.F 3.4-31 Amendment No. 120
__ - - - .~ - - _ _ - -- - - .- -
A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT RCS P/T Limits B-CORE NOT CRITICAL LIMIT
, C-CORE CRITICAL LIMR 1400 A B C '
I
/ /
/ 11 1 1300
/
[ )
7
)
r
'I I I 1200
/
l /
[ /
[
/ .f f 1100 - '
Curves are t f f
applicable for service
[ [ [
1000 periods up to and I
~~~~ including 16 EFPY /
f
/
/
[ /
[
/ ) )
900 / / /
/ / / Acceptable Region of
/ / /
y f / / Operation is to the CL 800 f
l f j Right of the Applicable
/ 1 ! Curve r
$ ) / )
[700 f f E / /
.c { 'l
}600 f f a
h.500 I 400 312 psig\
l
- l 300 ij f
/ /
/ /
200
/ /
g /
/
/
100 ,/ [ 1
! 1l I
~ Bolt Up. Limit l 0 ilililll 60 70 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure
, Figure 3.4.11-1 (page 1 of 5)
GRAND GULF 3.4-31 Amendment No l
- . . - . _ , ._ . . . ~ . - ..
l A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT B-CORE NOT CRITICAL LIMIT RCS P/T Limits
'. C-CORE CRITICAL LIMIT 1400 A; B C 3.4.11 1 I I \
J f (
1300
}
[ l I
[
/
\
l I i \
1200 7
j I
j l g l Acceptable Region of l
1100 5~~2 Curves are 777_ applicable for service /
g
/
['
/
[ Operation is to the
/ Right of the Applicable
/ /
periods greater than
,I ,/ ,/ Curve 1000 ----- 16 EFPY but less than j
, ,/ ,/
or equal to 20 EFPY f f f f )
900 )
/ f f
/ / /
vn / / f
/ / )
$ S00 / f f CL
/ / ./
if f / /
I k700 j f l
It: /
,g
/
/ f
.'gi 600 1 )
g g E
! 500 m
A 312 psig 400 '
N 1%-
l 3 300 if jf
/ /
/ /
200 / 'f t /
/
/ '
100 [, !
l
/
/
--Bol( Up Lirni,t 0 ! !
70 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure Figure 3.4.11-1 (page 2 of 5)
GRAND GULF 3.4-32 Amendment No l
4 A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT RCS P/T Limits B-CORE NOT CRITICAL LIMIT C-CORE CRITICAL LIMIT A
1400 B C 3.4. i i ll I I I i / /
1300 / I f
/ / /
/ I I
/ f /
1200 / ) )
j f
, ( ,1 Acceptable Region of
/ / / Operation is to the 1100 Curves are
/ / /
/ / / Right of the Applicable applicable for service l I I f / / Curve 1000 periods greater than / )
,/
~
20 EFPY butless than / / /
or equal to 24 EFPY l #
. 900 ff f f !
)~ / I l / /
y / / /
e /
l
/ /
,g800 f / /
0, o ,/ f
)
f
) ,
/ } }
k700 g / /
\
l
/ /
~
c / /
l /
j600 / /
e S
h500
- e 400 312 psig N 1 l\ !
' - ~~
300
'[ j
/ /
/ /
- /
200 / /
f s /
100 ,
/ /
Bolt. Up Limit ~
0 I'!!'
70
{ 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure Figure 3.4.11-1 (page 3 of 5) l GRAND GULF 3.4-33 Amendment No
A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT t
B-CORE NOT CRITICAL LIMIT RCS P/T Limits j ". C-CORE CRITICAL LIMIT 1400 A B C 3 4 ii i ; ;
/ / /
/ I I
/
1300
/ [
/ / /
.__ / I i Cuwes are 1200
- applicable for service f
/ g
/ f
/ Acceptable Region of l --- periods greater than
$222' 24 EFPY but less than /
[ /
j / Operation is to the ;
/ Right of the Applicable
/ / /
- (([. or equal to 28 EFPY / / I/ Curve
/
l' 1000
/ /
j
/
/ !
/
/ / \
900 ' I j , l
/ 'l f 1 m / / /
h800 6 f i
(
f <
f
$ l'( / l k700 p l l M f f
.5 / /
l }600 ,
w E, / /
I
! 500 m
b
' 400 --- 312 psig 300 h _
if f
/ / .
/ /
200 ---- j' j'
\
l
/ \
/ )
100 / / '
~
Bolt Up Lirnit 0 .I '
70 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
! Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure Figure 3.4.11-1 (page 4 of 5)
GRAND GULF 3.4-34 Amendment No l
\
1 A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT I B-CORE NOT CRITICAL LIMIT RCS P/T Limits C-CORE CRITICAL LIMIT A B C 3,4,i i I J ) l
/ I I (
( !
1300 1 (
/ j j
/ / / i
) I I 1200 / / / !
/ / /
/ ( (
Curves are / J '
1100 / /
7 Acceptable Region of applicable for service { / /
/ / Operation is to the
~--- periods greater than ( f j 1000 28 EFPY butless than / / / Rightof the Applicable f / /
or equal to 32 EFPY / / / Curve
/ / /
900 1 ( (
I J J
/ ( (
I J J i E / / /
800
/ / /
o / / r
> f / /
/ ) )
k700 g / / /
/ /
g
- / /
/ /
}600 e / /
S / /
!500 e
400 312 psig s
! N I RA
- ~~
300 ---
7
/ /
/ /
200 j j'
/
! . /
100 j
[
< l
' Bolt Up Limit 0 I!'!
70 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure Figure 3.4.11-1 (page 5 of 5)
GRAND GULF 3.4-35 Amendment No
I Reactor Steam Dome Pressure 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS)
< 3.4.12 Reactor Steam Dome Pressure LCO 3.4.12 The reactor steam done pressure shall be s 1045 psig.
APPLICABILITY: MODES 1 and 2. l l
ACTIONS CONDITION REQUIRED ACTION CONPLETION TINE A. Reactor steam done A.1 Restore reactor steam 15 minutes pressure not within done pressure to limit. within limit.
B. Required Action and B.1 Be in MODE 3. 12 heurs associated Completion Time not met.
l 1
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify reactor steam dome pressure is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s 1045 psig.
i l .
i 4
I GRAND GULF 3.4- Amendment No. 120 lh*
- . . . . _ . - . - . - -_ .-. . - . . . . . . ~ . . . . - ..
i Attechnent 4 to GN3tO-96/00120 Pega 1 Cf 6 i
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Attachment 4 Pressure-Temperature Curves with Additional Information Supporting (PCOL 96/10) for Grand Gulf Nuclear Station 1
s
'I
A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT RCS P/T Umits B-CORE NOT CRITICAL LIMIT C-CORE CRITICAL LIMIT 1400 I A B C i ! I I /
/ I I 1300 / / /
g r r
) ) )
1200 Bottomhead Controlled g g j f
j f
j f
N / / /
't i T I 1100 Curves are
/ /
l g
._ --- applicable for service 7
/
j j' Beltline Controlled 1000 - ---- periods up to and I including 16 EFPY /
j l
/
j - ((
/ /
/ ) )/
900 / / /
/ / /
) Acceptable Region of
/ /
, ,r f Operation is to the f
800
/
j# f I
if I
Right of the Applicable
) Cume ;
) )
(700 IE
/
l /
,r ~- -
i c (
~. f
.g 800 ) )t g
g
^s.w( N g t
?
~
E Feodwater Nozzle !
- s 500 Controlled
)
400 312 ps Curves B and C 1
300 i - - -
Are Based on an ART l/ ! I/
T/ \/ of 33.53 dog F of j if Beltline. Curve Ais 200
/ \ t' I f(T Not Beltline Controlled
/ N \
100 / -
/ lN\
f l iw i
/I- Faedwater Nozzle Controlled
__ Bolt Up Limit O' IiI!III! 'II!'I'!!!I!I
60 70 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Mirimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure I
l
A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT
- B-CORE NOT CRITICAL LIMIT RCS P/T Limits
, C-CORE CRITICAL LIMIT 1400 A, ; B C i I I I I (
1300
/
[ /
j
/
f I I i 1200 I I I j (
(
f j j Acceptable Region of I-~~
II Curves are applicable for service /
[ /
[ /
[ Operation is to the Rightof the Applicable periods greater than / / I Curve 1000 16 EFPY but less than
/
/
I%
[h _I' X
[ k
\
or equalto 20 EFPY
~~~ / / %d N \
900 / / / PW,,
y j .j a
- / / / Beltline Controlled a ~ Bottomhead Controlled / / /
o N / ) )
.$800 3 j f f O.
X / / /
$ l ! /
[700 '
f % f,y GC
.E I
/
"1CA I
Feedwater Nonle -
y600 / / Controlled S
h500
- g Curves A, B and C 400 312 psig Are Based on an ART N i g of 40.77 deg F of 300
/
i[ /
jf Beltline.
{-
A /
200 /% fi r sy jg K \
/ N %
100
/ / '
QX l l
- y - im I /I ~ Feedwater Nonle Controlled
--Bol} Up limit ,, ,,,
iiiiiiii ii iii -h,, s,ii i
iii 0
70 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure
- - . _ . . - . = _ . - . . _ _ . ._. - - . _. _ _ _ - - . _ _ - . _
A-INSERVICE LEAK & HYDROSTAllC TESTING LIMIT RCS P/T Limits l B-CORE NOT CRITICAL LIMIT l, C-CORE CRITICAL LIMIT 1400 A B C t J I l' I '
( l I 1300 / 1 I
( / j /
I I I l
I ( l
/ / /
(
/
[ /
f
/
.f Acceptable Region of Operation is to the 1100 --- Curves are / / /
l I
/ I / Right of the Applicable applicable for service periods greater than
/ /
(
I
[ Curve -
1000 20 EFPY but less than /
/
/ x
[
I \
I \
900 or equal to 24 EFPY j
g
/- ,
'N f
l
\ /s f q
\
.g
/ / s w / N 1 '
n / / !7N N \
y 800 ;
/ / / NM s~
j j D. / / / Beltline Controlled
$ / f I l [700 b E f f e / /
1 1 / ' / A y 600 - -
7 g
/ ~ ~
4 w E FeedwaterNozzle 5 s SM Controlled 1;
1 Curves A, B and C 400 312 psig N
~
Are Based on an ART N'
300 of 47.04 deg F of f/ \/.
/ A Beltiine. - ~~
/ . -
/L i 200 ' # A
/ -/t N 's
/ w N
/ / MA 1" / '
/ 4 N\
/ Feedwater Nozzle Controlled 1 I
~ Bolt Up Limit
! 0 !'!' ,
70 l 80 100 120 140 160 180 200 220 240 260 l
l RPV Metal Temperature (Degree F) l
, Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure i
~.
A-INSERVICE LEAK & HYDROSTATIC TESTING UMIT B-CORE NOT CRITICAL LIMIT RCS P/T Limits
". C-CORE CRITICAL UMIT 1400 A B C
, i
/ / /
/ I I 1300
/ [ [
/ / /
/ I j j
.I j
1200 ---- Curves are
.___. applicable for service f f g Acceptable Region of periods greater than / I I Operation is to the 1100 I / /
~__. 24 EFPY but less than I / / Rightof the Applicable
/ /\ /
.___, or equal to 28 EFPY / / \ 1 Curve 1000
/
f I
N
'i
/ (- [( 1/ 1
/ / 'N I/s (
900 I I _N \\
/ / / NM
/ / /
.a f j j Beltline Controlled I '
h800 L
f f j
I lf lf I
l f
k700 p ,I f
E
/ /
5 / /
3600 / /
$, / /
! 500
$ Curves A, B and C ~~ !
2 l
1 Are Based on an ART 400 l 312 psig N of 52.59 deg F of 300
- b. _
Beltline.
j ij< ij< , ,
i/ _' / I I
/ N / L l 200 / %.K f f -n
/ NN
/ M K 100 / '
/ ' '
/ Feedwater Nozzle Controlled
~
fI i l
. Bolt Up Limit i
0 'II!
70
( 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure I
A-INSERVICE LEAK & HYDROSTATIC TESTING LIMIT B-NON-NUCLEAR UMIT RCS P/T Limits C-CORE CRITICAL LIMIT 1400 A B C i
I ) / -
/ I I 1300 1 / /
/ I J
/ / / '
/ ,I I 1200 / / /
/ / /
I / / (
Curves are / l i 1100 / / / Acceptable Region of applicable for service / / /
/ Operation is to the '
periods greater than ( f j 1000 28 EFPY but less than / / / Right of the Applicable I / /t or equal to 32 EFPY / / ,r 3 Curve
/ /N / 1 900 / / \ / (
/ / h w / \ ,
/k i Nf \ ;
/\ % ) }\
& ~
^
J j 800 / / - - / N \
o, > / _7N N \
c / / r mg ,
>= .- f f l
/
Beltline Controlled 700 j
/ /
g / /
- / /
3 600 / /
1 / / i
/
S /
!500 ,
e -
L 400 312 psig m Curves A, B and C l g Are Based on an ART
' ~
300
' h7
/
]
/
of 57.57 deg F of j Beltline. '
p ___
200
/
/
jf N
kk
/ '% N 100 / / IIM
, - ; - ii im olt.U Limi . , ,
,'f ,
i 0
iiilIIIl III iiililll1IIIiii l , ,
( 70 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure I
j i Attechnent 5 t3 GNRO-96/00120 Pcgs 1 of 4 l !
i 1
1 2
a j
i !
- Attachment 5
)
- Technical Specifications Bases Mark-Ups for Revisibn to the Pressure-Temperature Curves (PCOL 96/10) 4 for 1
Grand Gulf Nuclear Station d
i Y N 1
i i
i a
RCS P/T Limits
. B 3.4.11 B 3.4 REACTOR COOLANT SYSTEM (RCS)
, B 3.4.11 RCS Pressure and Temperature (P/T) Limits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LC0 limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.
Figure c M 3.4 11-1 contains nd inservice P/T leak andlimit curvestesting.
hydrostatic fo k m w,,, E f r a
kam+un encum nrovidas 1imite far L* k L-'"a and >
NO @ i. gg g{+{h((go _ - ~ ~ ~ ~ ^
(,i rJ Ciud,a.)
j Each P/T limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and h@yg udC. compared to the applicable curve to determine that operation I is within the allowable region (i.e'., to the right of the dg applicable curve). l The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel is the component most subject to brittle failure. Therefore, the LCO limits apply mainly to the vessel.
10 CFR 50, Appendix G (Ref.1), requires the establishment of P/T limits for material fracture toughness requirements of the RCPB materials. Reference 1' requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests.' It mandates the use of the American Society of Mechanical Engineers (ASME) Code,Section III, Appendix G (Ref. 2).
The actual shift in the RT, of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with ASTM E 185 (Ref. 3) and 10 CFR 50, Appendix H (Ref. 4).
The operating P/T limit curves will be adjusted, as (continued)
GRAND GULF B 3.4-52 Revision No. 1
o
- RCS P/T Limits B 3.4.11 BASES BACKGROUND necessary, based on the evaluation findings and the (continued) recommendations of Reference 5.
The P/T limit curves are composite curves established by superimposing limits derived from stress analyses of those portions of the reactor vessel and head that are the most restrictive. At any specific pressure, temperature, and temperature rate of change, one location within the reactor vessel will dictate the most restrictive limit. Across the span of the P/T limit curves, different locations are more restrictive, and, thus, the curves are composites of the most restrictive regions.
heatup curve represents a different set of restrictions than 1down curve because the directions of the thermal gradien u .:.. t +ha vessel wall are reversed. The thermal gradient reversal alters tne im..... . r' +he tensile stress between the outer and inner walls.
The criticality limits include the arence I requirement that they be at least 40*F above th-.;;tg c.,- :r tr.: "
{"g teeWoutcurve and not lower than the minimum permissible temperature for the inservice leak'and hydrostatic testing.
N0Y Tha consequence of violating the LCO limits is that the RCS g j,tg has been operated under conditions that can result in
, brittle failure of the RCPB, possibly leading to a L,h nonisolable leak or loss of coolant accident. In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components. The ASME Code,Section XI, Appendix E (Ref. 6), provides a recommended methodology for evaluating an operating event that causes an excursion outside the l imi ts..
APPLICABLE The P/T limits are not derived from Design Basis Accident l SAFETY ANALYSES (DBA) analyses. They are prescribed during normal operation l to avoid encountering pressure, temperature, and temperature
, rate of change conditions that might cause undetected flaws l to propagate and cause nonductile failure of the RCPB, a l condition that is unanalyzed. Reference 7 establishes the methodology for determining the P/T limits. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the P/T limits. Rather, the P/T limits (continued)
GRAND GULF B 3.4-53 Revision No. O
?
RCS P/T Limits B 3.4.11 t
BASES APPLICABLE are acceptance limits themselves since they preclude SAFETY ANALYSES operation in an unanalyzed condition. -
(continued)
- RCS P/T limits satisfy Criterion 2 of the NRC Policy Statement.
LCO The elements of this LCO are: i
- a. RCS pressure and temperature.are within the limits specified in Figure 3.4.11-1 and heatup or cooldown i rate is s 100*F in any one hour period during RCS '
heatup, cooldown, and inservice leak and hydrostatic testing.
- b. The temperature difference between the reactor vessel bottom head coolant and the reactor pressure vessel )
I (RPV) coolant is s 100*F during recirculation pump J startup and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow.
- c. The temperature difference between the reactor coolant in the respective recirculation loop and.in the reactor vessel is s 50*F during pump startup and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow.
j
- d. RCS pressure and temperature are within the '
' criticality limits specified in igure 3.4.11-1 prior to achieving criticality.
I l k 9 N iC4 k e. The reactor vessel flange and the head flange ,
temperatures is a: 70*F when tensioning the. reactor l vessel head bolting studs.
h These limits define allowable operating regions and permit a i ;
large number of operating cycles while also providing a wide i margin to nonductile failure. !
The rate of change of temperature limits control the thermal ;
gradient through the vessel wall and are used as inputs for l calculating the heatup, cooldown, and inservice leak and :
ww~~ n \
beced od %e cup.e4+ EGec+ lee Fu ll i
i Pe
- =-
W4 .
(EFPY) w' ~._
~ ~ (continued) a f
i GRAND GULF B 3.4-54 Revision No. 0
October 22, 1996 GNRO-96/00120 Page 2 of 4 facilitate NRC review. Upon approval of the proposed TS curves in Attachment 3, the curves included in Attachment 4 (containing detailed information used in development of the TS curves) will be retained in the Updated Final Safety Analysis Report for information. The Attachment 3 curves (containing operator information) will be included in the TS. In addition, a marked-up copy of the affected pages from the Technical Specification Bases is provided in Attachment 5. Upon approval of this request by the NRC, Entergy will revise the GGNS TS Bases in accordance with GGNS TS 5.5.11, ' Technical Specifications Bases Control Program, to reflect the changes provided in Attachment i
- 5. Attachment 1 is the affirmation as per 10CFR50.30 which supports i the facts set forth in this letter and its attachments.
Entergy has reviewed the proposed change against the criteria of 10CFR51.22 for categorical exclusion from environmental impact considerations. The proposed change does not involve a: significant hazards consideration; significant change or increase in the types or amounts of any effluents that ray be released offsite; significant increase in individual or cumulative occupational radiation exposure.
Entergy concludes that the proposed change meets the criteria given in 10CFR51.22 (c) (9) for a categorical exclusion from the requirement for j an Environmental Impact Statement. i Based on the guidelines presented in 10CFR50.92, Entergy Operations has concluded that this proposed amendment involves no significant j hazards considerations. Entergy Operations is requesting action on '
this submittal by November 1997 as we anticipate reaching 10 EFPY during this month.
If you have any questions, please contact Mike Larson at 601-437-6685.
Yours truly, JJH/
attachments: . Affirmation per 10CFR50.30
- 2. Evaluation of No Significant Hazards Consideration i for Request for Revision to the Pressure-Temperature Curves (PCOL 96/10) for Grand Gulf Nuclear Station
- 3. Mark-ups of Affected Technical Specifications Pages and Proposed Replacement Curves
- 4. Pressure-Temperature Curves with Additional Information
- 5. Technical Specifications Bases Mark-Ups
( cc: (See Next Page) l
r
. i l
-October 22, 1996 GNRO-96/00120 Page 3 of 4 l l
cc: Mr. J. E. Tedrow (w/a)
Mr..R. B. McGehee (w/a) ,
i Mr. N. S. Reynolds (w/a)
Mr. H.~L. Thomas (w/o) i l
Mr. J. W. Yelverton (w/a) I l Mr. L. J. Callan (w/a)
- Regional Administrator i j U.S. Nuclear Regulatory Commission ,
- Region IV
[' 611 Ryan Plaza Drive, Suite 400 .
, Arlington, TX 76011
'Mr. J. N. Donohew, Project Manager (w/2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop.13H3' '
Washington, D.C. 20555 .
Dr. E. F. Thompson (w/a) '
State Health Officer State Board of Health ,
P. O. Box 1700 l Jackson, Mississippi 39205 I
! l l
i c
. . . . . . . . . . _ - . . . - - . - . - _ . . ~ . _ _ _ .
. ~ _ _ . - - - . . - ~ . . . . ~ - . . . . . . _ .
. j Attechment 1 ts GNRS-96/00120 f L
i BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 1
DOCKET NO. 50-416 IN THE MATTER OF ENTERGY MISSISSIPPI, INC ,
and l SYSTEM ENERGY RESOURCES, INC. I and l
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION and j ENTERGY OPERATIONS, INC. l
, AFFIRMATION l
I, J. J. Hagan, being duly sworn, state that I am Vice President, Operations GGNS of Entergy Operations, Inc.; that on behalf of Entergy Operations, Inc., 3 System Energy Resources, Inc., and South Mississippi Electric Power l Association I am authorized by Entergy Operations, Inc. to sign and file with I the Nuclear Regulatory Commission, this application for amendment of the I l
Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President, Operations GGNS of Entergy Operations, Inc.;
and that the statements made and the matters set forth therein are true and 1
[ correct to the best of my knowledge, information and belief. !
l t
i J.' ga I
STATE OF MISSISSIPPI COUNTY OF CLAIBORNE SUBSCRIBED AND SWORN To beforege, a Notary Pp lic, in and for the County and State above named, this 22 day of UCYo bet- , 1996.
(SEAM l fg bl -
s \ Notary Public l My comrrission expires: ,
' e
' 38tSSPPI STATEWIDE NOTARY PUDUC I rEl t0MMISS10N EXI'!RES JUNE 5,1993 l
moNnm TH2U STrr.All NOTARY EERVICS