ML20217Q843
| ML20217Q843 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/27/1997 |
| From: | Donohew J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217Q845 | List: |
| References | |
| NUDOCS 9709030399 | |
| Download: ML20217Q843 (11) | |
Text
panseuqk UNITED STATES g'
g NUCLEAR REGULATORY COMMISSION WABHINGTON, D.C. seteHost D(IDGY OPERATIONS. INC.
SYSTEM ENERGY RESOURCES. INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION ENTERGY MISSISSIPPl. INC.
DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING l_ICENSE Amendment No.132 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Doerations, Inc. (the licensee) dated October 22, 1996, as supplemented by letter dated June 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;
\\
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9709030399 970827 4
PDR ADOCK 05000416 P
pop
' 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and parsgraph 2.C.(2)llows:of Facility Operating License No. NPF-29 is hereby amended to read as fo (2) Technical,Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.132, are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.a k N. Donolew, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation-
Attachment:
Changes to the Technical Specifications i
Date of Issuance: August 27, 1997 9
..*.s.-,....
.m.-
o -
e ATTACHMENT TO LICENSE AMENDMENT NO.112 FACILITY OPERATING LICENSE NO. NPF 29 DOCKET NO. 50-416 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3.4-27 3.4-27 3.4-28 3.4-28 3.4-31 3.4-31 3.4-32 3.4-33 3.4-34 3.4-35 3.4-32 3.4-36
RCS P/T LiDits 3.4.11 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TINE C.
N0TE---------
C.1 Initiate action to lamediately Required Action C.t restoreparameter(s) shall be completed if to within limits.
this Condition is entered.
Algt C.t Deterstne RCS is Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation, or 3 than MODES 1, 2, and 3.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 a.
RCS pressure and RCS temperature are within the limits of the a>plicable Figure 3.4.11-1 based on t1e current EffectiveFull-PowerYear(EFPY),and b.
RCS heatup and cooldown rates are s 100'F in any I hour period.
(continued)-
?
GRAND GULF 3.4-27 Amendment No. 440,132 e
.thme hg&$gg M $6& M 6,y-cygg pg mg 9
ya,
.r.-w.m W,,ee w- % =ar se.-4 m<,.sws.w.-g
.;-2
..,s,-4ws
.-.4
RCS P/T Lioits 3.4.11 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.11.2
.------.--NOTE--------------------
On1 required to be met during control rod wit drawal for the purpose of achieving criticality.
Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in 15 minutes the applicable Figure 3.4.11-1 based on the prior to current Effective Full Power Year (EFPY).
control rod withdrawal for 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 dome pressure 2 25 psig during recirculation pump start.
Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes pressure vessel (RPV) coolant temperature prior to each is 5 100*F.
startup of a recirculation pump SR 3.4.11.4
NOTE--------------------
Only required to be met in MODES 1, 2, 3, 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 s 50*F.
startup of a recirculation pump (continued)
GRAND GULF 3.4-28 Amendment No. +GG,132
___.____.__._.a
l A-INSERVICE LEAK & HYDROSTAllC TESilNG UMR RCS P/T Umits B-CORE NOT CRRICAL LIMR C-CORE CRRICAL LIMR A
B C
3.4,n I
I I
)
- f f
1500 I
}
}
(
l I
f 1200 j
j
/
/
/
/
f f
I
/
/
1100;--
- Curves are j
.-__. applicable for service f
[
[
j 22 Periods up to and I
/
f f
1000
~~~; including 16 EFPY I
/
/
/
}
}
i
/
/
/
900
/
/
/
Acceptable Region of j
[
[!
Operation is to the
/
f f
Right of the Appliceble soo
/
r CuNo
(
)
}
l l
100 l
l
.E
(
f l
l-1-
312 psigY 400 iu sn
/
/
/
/
200
/
)
,l
,,f' /
100 6ii 7 Bolt Up Umtt ~
!!illi!1 7
s0 ' so 100 120 140 1s0 1:0 200 220 240 too to 40 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.4M, 132
_=
l AclNSERVICE LEAK a. HYDROSTATIC TESilNG LIMIT RCS P/T Limits B-CORE NOT CRITICAL LIMii C-CORE CRlilCAl LIMli A
B C
3.4,33
(
l I
i f
f.____
1300
/
)
I
(
/
J j
(f 12M f
(
Acco table Region of
~~~
Curves are
/
Operation is to the f
f f
1100
~ : applicable for service 1
i~~~~
l
. Right of the Applicable I
I I
periods greater than
,i
,/
,/
Curve '
1000 ----
16 EFPY but less than j
f r
.22~-
or equal to 20 EFPY
--[
/
,/
900
-f f
f f
I
(
f
/
}
l 0%
/
f f
f
/
)
f
(
700 r
r
,5 f
f 1
}
000
(
(
l.00
- 0 312 psig N X ir 300
,V
/
/
/
/
/
i 200
/
j
/
(
j
- Yd'N iiillill 70 20 40 40 80 100 120 140 160 100 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure Figura 3.4.11-1 (page 2 of 5)
GRAND GULF 3.4-32 Amendment No.132
~
~
- ~~^~ :~
~ ' ^ ~ ~ ~ -
A lH$0RVICE LEAK & HYDR $$1ATIC TESTING LIMg RCS P/T Limits B-CORE NOT CRRICAL LIMIT C-CORE CRRICAL LIMN A
B C
3.4,3 i 1400 I
i I
J l
i I
l 1
I I
1300 f
j j
/
I I
I
(
f f
1
~~[}
18
/
I Acceptable Region of
/
1
/
[
__/__. Opersbon is to the 1100 <---- Curves are
/
Right of the Applicable
- appiiombie for servloe
/
[
[
curve
- _:: Perkd* 9***r than
/
/
/
,,g
20 EFPY butless then j
j g
or equelto 24 EFPY j
/
[
~~
900
)
l l
?
?
(
I I
J S00
/
/
/
/
i i
/
i i
N 100 l
j E
F l
5
- 00 l
l 1000 400 312 pelg x
3 k_
/
/
/
/
/
/
200 l-
/
/
/
/
400
/
'--Bolt,Up l.imit filifi1i O
70 20 40 40 00 1
120 140 100 100 200 220 240 260 R
Metal Temperature (Degree F)
Minimum Reactor Vessel Metal Temperature vs Reactor Vessel Pressure F10ure 3.4.11-1 (poge 3 of 5)
GRAND GULF 3.4-33 Amendment No.12
A INSERVICE LEAK & HYDRd5TATIC TE$1 LNG LIMii RCS P/T Limlis B-CORE NOT CRlilCAL LIMii C-CORE CRITICAL LIMil A
B C
1#0 3'4,33 i
i i
I I
I f
I I
1300
)
f f
j j
,f
,/
,/----
1200 I
--} Acceptable Region of applicable for service j
[
r_
periods grooter than
/
J J_ Operation is to the 1100'::: 24 EFPY butless than
[
[
f Right of the Applicable l-- Curve
- -- or oquel to 28 EFPY ~
g f
1000
(
l l-l l
1 I
i 900
/
,I
,I
/
f f
I
}
}
800 j
j-
/
/
r
/
/
t 700
/
/
f 5
/
)
~g 600
,/
,/
}
(
l 500 400-:::
312 psig N \\
300 f
f3
~
/
/
200
/
j
[
100
,d-/
,80"Yh b,b iiiii!ir 70 to 40 to 30 100 120 140 160 180 200 220 240 260 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.132
.%a mu
- m ih-
A INSERVICE LEAK 8. HYDROSTATIC TESTlHG !!MR i.
l l
B CORE NOT CRillCAL UMIT RCS P/T Limits C-CORE CRillCAL LIMil A
B C
l.
1400 j
I.
I I
1
~
3.4.11 i
11
/
/
}
1300 I
I i
I I
IZ l
I i
~
1 1
L I
I
~~
}
[
l
~
1200 I
l'--
l' i
i I
,i
\\
t
(
Curves are 1
(----
1*
'(([~ applicable for service ^
Acceptable Region of r
r
- r
]
periods greater than --
l-Operation is to the g
~-f 1000 ---- 28 EFPY but less than
/
~~~~
- Right of the Applicable
~~
1
- or equalto 32 EFPY 1
[
Curve
/
r
(
/
I 900
/
I I
}
/
/
]
--/
f f
/
/
/
800 l
l
]
~~ '
il l
r F
,r
[ 700 I
/
/~
/
/
/
/p j
g f
l
~~
.y 400 J
/
/
/
}
}
I I
E
= 500 m
b 400 ] 312 psig N %^
x 300 f
j
/
V f
f 200
[
[
-a
/
p
--.y 100
,f[j
/
/III Bolt.Up Limit-1 }!!lii!
0 70 20 40 SO 80 100 120 140 160 180 200 220 240 260 RPV Metal Temperature (Degree F)
Minimum Reactor Vessel Meto1 Temperature vs Reactor Vessel Pressure Figure 3.4.11-1 (page 5 of 5)
GRAND GULF 3.4-35 Amendment No.132
-i..
Reactor Steam Dome Pressure 3.4.12 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.12 Reactor Steam Dome Pressure LC0 3.4.12 The reactor steam done pressure shall be s 1045 psig.
APPLICABILITY:
MODES 1 and 2.
$TIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within dome pressure to
- limit, within limit.
8.
Required Action and B.1 Be in MODE 3, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify reactor steam done pressure is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l 1045 psig.
GRAND GULF 3.4-36 AmendmentNo.430,(
132'-
==
8-6$F
^ ^ -
---iW..pagg.g 1.n
..49 9gg
,.9 g gg g,_