ML20044F166
| ML20044F166 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/20/1993 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20044F164 | List: |
| References | |
| GGNS-PCOL-93-09, GGNS-PCOL-93-9, GNRO-93-00049, GNRO-93-49, NUDOCS 9305270105 | |
| Download: ML20044F166 (25) | |
Text
_
- _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ to GPeRO-93,00043 c
Page 10116 I
GGNS PCOL 92/09 Mark-up of Affected Technical Specification Pages l
i 1
i 9305270205 930520 PDR ADOCK 05000416 ppa P
- - - - - - ~ ~
6*.
TA8tE 3.3.1-1 RfACIOR PR0i[CIION SYSTEM INSTRUIENTAi!ON g
APPLICABLE MINIpRM r-OPERATIONAL OPERABLE CHAISIELS T
FilNCi10NAL LRilT C008IIl0NS PER TRIP SYST[M (a)
ACTION 1.
Interimodlate Range Itsnitors:
a.
80eutron Flux - High 2
3 1
.co
- u 3
3 b.
Inoperative 2
3 1
2.
Average Power Range Monitor ICI:
a.
10eutron Flux - High, Setdown 2
3 1
5 Bbh
}
(;
b.
Flow stased Simulated Thermal Power - Nigh 1
3 4
c.
flewtron Flux - High 1
3 4
Ah d.
Insperative 1, 2 3
1 2_
a 3
5
't _.
S w
[
3.
IIeacter Vessel Steam Bone U
Pressure - High 1,2(d) h 2
1 7
4.
Reacter Wessel Water Level - Law, 9
)
Lnel 3 1, 2 2
1 7.F 5.
Reactor Wessel Water Level-High, Level 8 1g,)
2 4
g; o
6.
Main Steam Line Isolation Valve -
II 'I Closure 4
4 IdI 7.
Main Steam Line Radiation - High I, 2 2
5
~
III 8.
Drywell Pressure - High 1, 2 2
I
. ~. - -....
..~.
- to GNRO 93,00019 Pags 3 of 16 TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS (a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condi-tion provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
(b) The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn" per Specification 3.9.2 and shutdown margin demonstrations performed.per Specification 3.10.3.
(c) An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.
(d) This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.
(e) This function shall be automatically bypassed when the reactor mode switch is not in the Run position.
(f) This function is not required to be OPERABLE when ORYWELL INTEGRITY is not required.
(g) With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(h) This function shall be automatically bypassed when operating below the appropriate turbine first stage pressure setpoint of:
(1) < 26.9%** of the value of turbine first-stage pressure at valves wide open (WO) steam flow when operating with rated feedwater temperature of greater than or equal to 420'F, or (2) < 22.5%** of the value of turbine first-stage pressure at WO steam 710w when operating with rated feedwater temperature between 370*F and 420'F.
l:
m[t) d M om cdcol r*A Whle' ** 6 a ca" c 83I ca+.;a'it not or
- c a a.u.
- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
- Allowable setpoint values of turbine first-stage pressure equivalent to THERMAL POWER less than 40% of RATED THERMAL POWER.
i
)
GRAND GULF-UNIT 1 3/4 3-5 Amendment No. 67, _
ci g
TABLE 4.3.1.1-1 o
REACTOR PROTECTION SYSTEN INSTRUMENTATION SURVEILLANCE REQ 111RENENTS h
CHANNEL OPERATIONAL E
CHANNEL FUNCT10NAL CHANNEL CONDITIONS FOR WHICH
}
FUNCTIONAL UNIT CHECK TEST Call 8 RATION (a)
SURVEILLANCE REQUIRED 1.
a.
Neutron Flux - High S/U.S.(b)
S/U, W R
2 5
--- W R
" 3, 4 3
b.
Inoperative NA W
NA 2M II) 2.
Average Power Range Monitor:
a.
Neutron Flux - High, S/U.S.(b)
S/U, W SA 2
Setdown S
S ^.
3, 5 I
D" b.
Flow Blased Simulated Thermal Power - High 5
Q W(d)(e), 34, g(l) 1 Y
c.
Neutron Flux - High S
Q W(d), 34 g
d.
Inoperative NA Q
NA 1, 2, 3, 5 *
.7 g 2=
3.
Reactor Vessel Steam Dome
- 9 I9)
I3) 1, 2
-[
Pressure - High S
Q R
4.
I9) 1, 2
{
Low, Level 3 5
Q R
f z
S.
3 I9) g High, Level 8 5
Q R
1 E
6.
Main Steam Line Isolation g
Valve - Closure NA Q
R 1
2 m
O 7.
Main Steam Line Radiation -
III High S
Q R
1, 2
-w I9) 8.
Drywell Pressure - High 5
.Q R
1, 2
s, TABLE 4.3.1.1-1 (Centinued) 5 REACTOR PROTECTION SYSTEN INSTRUMENTATION SURVEILLANCE REQUI o
8 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH y FUNCTIONAL UNIT CHECK TEST CALIBRATION E
9.
-Scram Discharge Volume Water SURVEILLANCE REQUIRED Q
Level - High H
a.
Transmitter / Trip Unit S
Q RI9) 1, 2, SIII b.
Float Switch NA Q
R 1, 2, SIII 10.
Turbine Stop Valve - Closure S
Q RI9) 1 11.
Turbine Control Valve Fast Closure Valve Trip System 011 Pressure - Low S
Q R(9) 1 12.
Reactor Mode Switch Shutdown Position MA R
NA 1,2,3,4,5 g 13.
Manual Scram NA W
NA 1,2,3,4,5
- (a) Neutron detectors may be excluded from CNANNEL CALIBRATION.
(b)
The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be deter-mined to overlap for at least 1/2 decade during each controlled shutdown, if not performed within the p s 7 days.
2? $
(c) [9EEETEOP Lsut 2 M g
(d)
This calibration shall consist of the adjustment of the APRM channel to conform to the power values
- j calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED g g
THERMAL POWER.
THERMAL POWER.. Adjust the APRM channel if the absolute difference is greater tiian 2% of RATED
'&~T' 3
g (e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.
3 2
(f)
The LPfWs shall be calibrated at least once per 1000 fedD/T using the TIP system.
8 i
g '(g)
Calibrate trip unit at least once per 92 days.
6 i
(h) Deleted.
$1 L
Q (1)
This calibration shall consist of verifying the 6 i 1 second simulated thermal power _ time constant.
g-4 (J) Not applicable'when the reactor. pressure vessel head is unbolted or removed per Specification 3.10.1.
(
g.
k) Not applicable when DRYWELL INTEGRITY is not required.
(1)
Applicable with any control rod withdrawn.
tion 3.9.10.1 or 3.9.10.2.
Not applicable to control rods removed per Specifica-I I
-.~..
. ~
~
i Attachmsnt 3 to GNRO-93,00049 Pag 2 6 of 14 l
~
INSERT TS page 3/4 3-8 With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(c) 1 1
e i
9 i
)
5 L
i r
\\
f i
1 1
i i
)
e, JABLE 3.J.6-1 CONTROL R00 BLOCK INSTRUMENTATION MINIMUM APPLICABLE E
onnaE Cm. cts onun0.t
[
TRIP FUNCTION EER TRIP FUNCTIQl1 CONDITIONS ACTION
- c N
1.
ROD PATTERN CONTROL SYSTEM E:
a.
Low Power Setpoint 2
1, 2 60
- b. High Power Setpoint 2
If 60
~<
2.
4l5313 INI
~
n = J-t; w - u.v. n u -
UpscaTi -
6 1
6 l i.
Inoperative C
1, 2, 5 6
c.
Downscale 6
6 d.
~
- h. f t :
4; :le,-6 tert 2, ',
i 3.
SOURCE llANGE MONITORS Detector not full in,3 4
2ff 61 g
a.
2**
5 62 b.
Upscale (b) 4 2ff 61 b
2**
5 62 Inoperatjve(b) 4 2ff 61; h
c.
2**
5 62 u>
d.
DownscaleICI 4
2if 61 5$
2**
5 62 "3
o3 Oc]. efh 3
4.
a.
- = =n e=
2, -
a l i. Upscale a
z, 5 6
Q k
perativ.a.
Ins 6
?. 5 6
E' C.
o a
c, a
g u
a 5.
SCR C 15 CHARGE VOLiflE 8
e a.
Water Level-High 2
1, 2, 5*
64
?
O to 6.
REACTOR.C00LMT SYSTEM RECIRCKATION FLOW a.
Upscale 3
1 64 7.
REACTOR MODE SWITCH $HUIDonM POSIIl0H 2
3, 4 63 5:
I to GNRO 93 C0049 j
M BTAT M Page 8 of 14 TABLE 3.3.6-1 (Continued)
CONTROL R00 BLOCK INSTRUMENTATION 1
l ACTION i
ACTION 60 Declare the RPCS inoperable and take the ACTION required by i
Specification 3.1.4.2.
'l ACTION 61 With the number of OPERABLE Channels:
a.
One less tnan required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable i
channel in the tripped condition within the next hour.
b.
Two or more less than required b'y the Minimum OPERA 8LE I
i Channels per Trip function requirement, place at least one inoperable channel in the tripped condition within one hour.
l l
With the number of OPERABLE channels less than required by the i
ACTION 62 Minimum OPERABLE Channels per irip Function requirement, place the inoperable channel in the tripped condition within one hour.
j With the number of OPERABLE channels less than required by ACTION 63 the Minimum OPERABLE Channels per Trip Function requirement, j
initiate a rod block.
ACTION 64 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place j
the inoperable channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
lEIES j
With more than one control rod withdrawn.
Not applicable to control rods l
removed per Specification 3.9.10.1 or 3.9.10.2.
i 9
OPERABLE channels must be associated with SRMs required OPERA 8LE per i
Specification 3.9.2.
4 With THERMAL POWER greater than the Low Power Setpoint.
I ff Whenever the related function is not bypassed as specified in notes (a) through (c).
(a)
This function shall be automatically bypassed if detector count rate is >
100 cps or the -IRM channels are on range 3 or higher.
(b)
This function shall be autcaatically bypassed when the associated IRM channels are on range 8 or higher.
(c)
This function shall be automatically bypassed when the IRM channels are on range 3 or higher.
(d)
Thi; '.n;ti;n ;h:ll M nt::: tic:lly by p ;;;d.A:n th: "* :h:.nn:h re^^ '
r:ng: !&
GRAND GULF-UNIT 1 3/4 3-54 Amendment No. 69, Mi, % -
AMachment 3 to GNRO-93<00049 s'
,,Pgage.9 of 14
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j Amentenant No. ifr,_.
GRAND GULF-UNIT 1 3/4 3-55
TA8tE 3.3.6-2 (Continued) m CONTROL R00 BLOCK INSTRWENTATION SETPOINTS h
_ RIP FUNCTION TRIP SETPOINT ALLOWA8LE VALUE T
m
.h
~ 4.
- "C; 3:ATC EflZ: L"TZ
- Del et<J,
~
7.vb = $5 vu Upscale f ina/125 of_fu11 -e ':
$ 110/125 of full scalo l '.
s Inoperative im MA
_..n....._,..... ___i.._
_.,a...
m e s s w 5.
SCRAM OISCHARGE VOLUME a.
Water Level-High 1 32 inches 1 33.5 inches 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW
_R a.
Upscale i 111% of rated flow 1 114% of rated flow a
57 7.
REACTOR IWDE SWITCH SHUTOOWN g
POSITION NA NA U>
$M aMr 03 1
2.*3 Eo s
O 7
2 9
I E,
g ta u#
I
TABLE 4.3.6-1 n
Cg CONTROL R00 BLOCK INSTRtM NTATION SURVEILLANCE REQJIRENENTS op CHANNEL OPERATIONAL T
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH I
g TRIP FUNCTION CHECK TEST CAllBRATION "I SURVEILLANCE REQUIRED "4
1.
R00 PATTERN CONTROL SYSTEN g
a.
Low Power Setpoint NA S/U(b),Q Q
1, 2 b.
High P Se int NA S/U(b),q q
3, 2.
G "=
Ocjd_t "Qu Thu-g
-n Inoperative h
M 1, 2, 5 li.
Q (b) Q NA I
a Downscale S/"
Q 27 S " u-3-:+ H e
" x de, St: W ;
"^
g
[
3.
SOURCE RANGE NONITORS tn a.
Detector not full in NA S/U,W NA 2ff, 5 b.
Upscale NA S/U,W Q
2##, 5 c.
Inoperative NA S/U,W NA 2##, 5 2 lx{
J d.
Downscale
_NA_
S/U,W Q
2ff, 5
- =c;;::ATc r= ::::::=v Cd 2i 4.
,3 rr-w.= ni: u
=
-S/ w
=
2, P 2
M Wu Q
2, !i h.
Upscale i :.
Inoperative im wu,w 2, b al.
_ _ _5eT e S/","
Q
- 1., a z
"^
2 y
3 5.
SCRAM 01SCHARGE Voll#E 9
w.
f a.
Water Level-Nigh NA Q
R 1, 2, 5*
6.
REACTOR COOLANT SYSTEN RECIRCULATION FLOW g
a.
Upscale NA Q
Q 1
y 7.
REACTOR N00E SWITCH SHUTOOWN POSITION NA R
NA 3, 4 o.
l
Attachm:nt 3 to GNPO-93,00049 Page 12 of 14
~
INSTRUMENTATION j
TABLE 4.3.6-1 (Continued)
CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIRE!
NOTES:
Neutron detectors may be excluded from CHANNEL CALIBRATION.
a.
b.
Within 7 days prior to startup.
c.
[ Deleted]
d.
[ Deleted) 1 e.
[ Deleted) i gd i
PL 1_
__9*L__A 1__
.L_99
____f_A
_E AL-
>1.
_A-A
_E AL_
Anhu
_L____1 h
no D
"'be h r$Aiues' caleulated by a $ at bAiaEe
@ g'hs OPERATIONAL N 1 when THERMAL POWER is greate or equal to
"/ 35% of RATED THERMAL Adjust the APRM if the absolute diffeence is greater than L POWER.
g.
+This calibration shall st of the adjus the APRM flow tiiased channel nform to a calibrated flow signa.
h.
- TM, ;eli,, etie.,..'.; ;...;i;t e'.e. i' jing t.% t, !;, ee'@ist er.ly.
With any control rod withdrawn.
per Specification 3.9.10.1 or 3.9.10.2.Not applicable to control rods removed l
With THERMAL POWER greater than the Low Power Setpoint.
Whenever the related function is not bypassed as specified in Table 3.4.6-1 notes (a) through (c).
l l
i i
i GRAND GULF-UNIT 1 3/4 3-57 Amendment No. IK, #,-iGij _._.__ i
Anachment 3 to GNRO-93.C0049 Page 13 of 14 2
.SPECIAL TEST EXCEPTIONS 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS t
+
LIMITING CONDITION FOR OPERATION 3.10.3 The provisions of Specification 3.9.1, Specification 3.9.3 and Table 1.2 may be suspended to permit the reactor mode switch to be in the Startup position and to allow more than one control rod to be withdrawn for shutdown margin demonstration, provided that at least the following requirements are satisfied.
The source range monitors are OPERABLE per Specification 3.9.2 with a.
the RPS circuitry " shorting links" removed.
b.
The rod pattern control system is OPERABLE per Specification 3.1.4.2, or conformance with the shutdown margin demonstration procedure is verified by a second licensed operator or other technically qualified member of the unit technical staff.
The " continuous withdrawal" control shall not be used during out-of-c.
sequence movement of the control rods.
- d. __ Ma other CORE ALTERATIONS are in progress.
(Lse.eD
\\;
APPLICABILITY:
OPERATIONAL CONDITION 5, during shutdown margin demonstrations.
ACTION:
With the requirements of the above specification not satisfied, immediately place the reactor mode switch in the Shutdown or Refuel position.
SURVEILLANCE REQUIREMENTS p
4.10.3 Within 30 minutes prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the performance of a shutdown margin demonstration, verify that; The source range monitors are OPERABLE per Specification 3.9.2 with a.
the RPS circuitry " shorting links" removed.
i b.
The rod pattern control system OPERABLE, or a second licensed operator or other technically qualified member of the unit technical staff is present and verifies compliance with the shutdown demonstration procedures, and c.
No other CORE ALTERATIONS are in progress.
GRAND GULF-UNIT 1 3/4 10-3 men
~
i to GNRO 93 OC4019 Pace 14 of 14 INSERT TS page 3/410-3 i
The Average Power Range Monitors are OPERABLE per the requirements of Specification e.
3.3.1 for OPERATIONAL CONDITION 2.
i P
r i
i t
E 9
I t
r I
i e
i h
.=
i to GNFO-93 00043 Page1 of11 s
t t
?
i i
I i
t E
t 5
I I
I t
b V
i i
f 6
Ii GGNS PCOL 92/09 Sample Proposed Technical Specification Pages J
l f
l i
l J
i 4
I l
i 1
t
}
TABLE 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION APPLICABLE MINIMUM OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS-PER TRIP SYSTEM (al ACTION 1.
a.
Neutron Flux - High (b)(i) l l
3 2;I 3
l' b.
Inoperative I
S 3
3 l
2.
Average Power Range Monitor (b)(c),
a.
Neutron Flux - High, Setdown 2
3
'l b.
Flow Blased Simulated Thermal Power - High 1
3 4
c.
Neutron Flux - High 1
3 4
d.
Inoperative 1, 2 3
1 g
3.
Reactor Vessel Steam Dome Pressure High 1, 2(d) 2 1
4.
Reactor Vessel Water Level - Low, m>
Level 3 1, 2 2
1 jj, 5.
Reactor Vessel Water Level-High, 75 Level 8 1g,3 2
4 21 "u
6.
Main Steam Line Isolation Valve -
g g
1,y 4
4 a
Closure z
7.
Main Steam Line Radiation - High 1, 2(d) 2 5
w 0I 8.
Drywell Pressure - High 1, 2 2
1 8"
<o f
i GRAND GULF-UNIT 1 3/4 3-2 Amendment No.
Attachm nt 4 to GNRO-93:00049 TABLE 3.3.1-1 (Contin'uYdf#
REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS 4
(a)
A channel may be placed in an inoberable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without pla ing the trip system in the tripped cond-ition provided at least one OPERABLE channel in the same trip system is l
monitoring that parameter.
(b)
The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn
- per Specification 3.9.2 and shutdown margin demonstrations performed per Specification 3.10.3.
(c)
An APRM channel is inoserable if there are less than 2 LPRM inputs per I
level or less than 14
_PRM inputs to an APRM channel.
l t
(d)
This function is not required to be OPERABLE-when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.
(e)
This function shall be automatically bypassed when the reactor mode switch is not in the Run position.
i (f)
This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required.
(g)
With any control rod withdrawn.
Not applicable to control rods removed i
per Specification 3.9.10.1 or 3.9.10.2.
(h)
This function shall be automatically bypassed when operating below the appropriate turbine first stage pressure setpoint of:
(1) s 26.9%** of the value of turbine first-stage pressure at valves wide open (VWO) steam flow when operating with rated feedwater temperature of greater than or equal to 420'F, or (2) s 22.5%** of the value of turbine first-stage pressure at VWO steam flow when operating with rated feedwater temperature between 370*F and 420*F.
(i)
With any control rod withdrawn from a core cell containing one or more l
fuel assemblies.
- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
- Allowable setpoint values of turbine first-sta E{ essure equivalent to THERMAL POWER less than 40% of RATED THERMAL P GRAND GULF-UNIT 1 3/4 3-5 Amendment No. 67, _
TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CilANNEL CONDITIONS FOR WillCil FUNCTIONAL UNIT CilECK TEST CAllBRATION SURVEILLANCE REQUIRED 1.
a.
Neutron Flux - liigh S/U.S,(b)
S/U,W R
2(c)
S W
R 5
b.
Inoperative NA W
NA 2, 5(c)
III 2.
Average Power Range Monitor:
a.
Neutron Flux - liigh, S/U.S,(b)
S/U,W SA 2
I Setdown b.
Flow Blased Simulated III Thermal Power - liigh S, D(h) q g(d)(c), SA, R 1
c.
Neutron Flux - High S
Q W(d), 34 3
d.
Inoperative NA Q
NA 1, 2 l
3.
Reactor Vessel Steam Dome IO) 1, 2 III Pressure - liigh S
Q R
4.
IO)
I, 2
[$
Low, level 3 S
Q R
.g
}l "i
5.
liigh, level 8 S
Q R(0)
}
I I
6.
Main Steam Line Isolation Valve - Closure NA Q
R 1
l y
l
- 7. Main Steam Line Radiation -
III
[$
liigh S
Q R
1, 2 SI IdI 1, 2 8.
Drywell Pressure - High S
Q R
5?
I GRAND GULF UNIT 1 3/4 3-7 Amendment No.
67, 91, _
TABLE 4.3.1.1-1 (Ccntinued)
REACTOR PROTECTION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIRENENTS CHANNEL OPERATIONAL i
CilANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 9.
Scram Discharge Volume Water Level - High N
a.
Trant :tter/ Trip Unit S
Q RIGI 1, 2, SN b.
Float Switch NA Q
R 1, 2, S
- 10. Turbine Stop Valve - Closure S
Q R(0) 1
- 11. Turbine Control Valve Fast Closure Valve Trip System 011 g9g 1
-Pressure - Low S
Q R
- 12. Reactor Mode Switch Shutdown Position NA R
NA 1,2,3,4,5
- 13. Manual Scram NA W
NA 1,2,3,4,5 (ai Neutron detectors may be excluded from' CHANNEL CAllBRATION.
(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 1 2 decade during each controlled shutdown, if not performed m>
within the previous 7 avs.
(ci With any control rod withdrawn from a core cell containing one or more fuel assemblies.
I Ei3 (dj This calibration shall consist of the adjustment of the APRM channel to coviform to the power values 19 calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED o9 THERMAL POWER. Adjust the APRM channel if the absolute difference is greater tiian 2% of RATED j
THERMAL POWER.
u (e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a
' m calibrated flow signal.
a
.(fl The LPRMs shall be calibrated at least once per 1000 MWD /T using the TIP system.
r g) Calibrate trip unit at least once per 92 days.
i fh) Deleted.
6 f i i This calibration shall consist of verifying the 6 i I second simulated thermal power time constant.
w ressure vessel head is unbolted or removed per Specification 3.10.1.
g' <
i))Notapplicablewhen.thereactorgRITYisnotrequired.
Not applicable when DRYWELL INTE f
Applicable with any control rod withdrawn..Not applicable to control rods removed per Specifica-e (1
tion 3.9.10.1 or 3.9.10.2.
t GRAND GULF-UNIT 1-3/4 3-8 Amendment Nor 47, 9I, _
= :
TAB.E 3.3.6-1 CONTROL ROD 10CK '.NSTRUMENTATION HINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTIOE PER TRIP FUNCTION CONDITIONS --
ACTION-1.
R00 PATTERN CONTROL SYSTEM a.
Low Power Set 2
1 2
60
- b. liigh Power Se(oint point 2
II 60
-l 2.
Deleted l
3.
SOURCE RANGE MONITORS ta) 4 2##
61 a.
Detector not fulT in 2**
5 62 b.
Upscale (b) 4 2##
61 2**
5 62 IDI c.
Inoperative 4
2##
61 2**
5 62
- d. - Downscale(c) 4 2##
61 2**
5 62 l
4.
Deleted 5.
Water Leve'-High 2
1, 2, 5*
64 6.
REAC"0R COOLANT SYSTEM RECIRCULATION FLOW 3
1 64 m 3,
.a.
Lpscale En 7.
BEACT01 100E ShITCH SHUTDOWN POSITION 2
3, 4 63
- M Q
INSTRU lek TATIO4
-a "u
G
~9 5 8
i 8~
i?w GRAND GULF-UNIT 1 3/4 3-53 Amendment No. 69,--101, 105, _.
_ _ _ _. _ _. _ _ _. _ _ -. _... _.. _ _ _. - ~ _. _. _ _.. _. - _.. _. _ _ _ _.. _.. _ -.. _ _ _. _ _. _ _. ~.. _ _ _ _... _.. _. _., _.. _ _..., _ _..... _ _ _...
__ _ -. to GNRC-93 'OCC49 Page 7 of 11 TABLE 3.3.6-1 (Continued)
CONTROL R00 BLOCK INSTRUMENTATION ACTION ACTION 60 - Declare the RPCS inoperable and take the ACTION required by j
Specification 3.1.4.2.
ACTION 61
- With the number of OPERABLE Channels:
One less than required by the Minimum OPERABLE Channels per a.
Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
b.
Two or more less than required by the Minimum OPERABLE Channels per Trip Function requir.ement, place at least one inoperable channel in the tripped condition within one hour.
With the number of OPERABLE channels less than required by the ACTION 62 Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.
ACTION 63 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.
With the number of OPERABLE channels less than required by the ACTION 64 Minumim OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
NOTES With more than one control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
OPERABLE channels must be associated with SRMs required OPERABLE per Specification 3.9.2.
With THEPEAL POWER greater than the Low Power Setpoint.
Whenever the related function is not bypassed as specified in notes (a) though (c).
(a) This function shall be automatically bypassed if detector count rate is 100 cps or the IRM channels are on range 3 or higher.
(b) This function shall be automatically bypassed when the associated IPM channels are on range 8 or higher.
(c) This function shall be automatically bypassed when the IRM channels are on range 3 or higher.
l (d) Deleted GRAND GULF-UNIT 1 3/4 3-54 Amendment No. 69, A, 445, _
w TABLE 3.3.6-2 1
CONTROL R00 BLOCK INSTRUMENTATION SETPOINTS TRIP FUNCTIO _ff TRIP SETPOINI ALLOWABLE VALUE 1.
R00 PATTERN CONTROL SYSTEM a.
Low Power Setpoint 20 + 15,. -0% of RATED THERMAL 20 + 15 -0% of RATED THERMAL POWER POWER b.
High Power Setpoint s 70% of RATED THERMAL POWER s 70% of RATED THERMAL POWER l
2.
Deleted 3.
SOURCE RANGE MONITORS i
a.
Detector not full in NA NA 5
5 b.
Upscale s 1 x 10 cps s 1.5 x 10 cps c.
Inoperative NA
'NA d.
Downscale a 0.7 cps 2 0.5 cps 4.
Deleted I
5.
Water Level-High s 32 inches s 33.5 inches
.n 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW N l?
co a.
,f a.
Upscale s 111% of rated flow s 114% of rated flow 7.
MAC"0R MODE SWITCH SHUTDOWN
.G MSI" 10N NA NA
@L 83 6
.8e, i
GRAND GULF-UNIT 1 3/4 3-55 Amendment No..M,
~.
TABLE 4.3.6-1 CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION (a) SURVEILLANCE REQUIRED,
1.
R00 PATTERN CONTROL SYSTEM a.
Low Power Setpoint NA S/U(b),Q Q
1, 2 b.
liigh Power Setpoint NA S/U(b),q q
j.,
l 2.
Deleted 3.
SOURCE RANGE MONITORS a.
Detector not full in NA S U,W NA 2##, 5 b.
Upscale NA 5 U,W Q
2##, 5 c.
Inoperative NA S U,W NA 2##, 5 d.
Downscale NA S/U,W Q
2##, S l
4.
Deleted S.
SCRAM DISCllARGE VOLUME a.
Water Level-High HA Q
R 1, 2, S*
6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW En m>
- E a.
Upscale NA Q
Q-1
,3 E
7.
REAC"0R MODE SWITCH Sil0TDOWN 30$110N NA R
NA 3, 4 5
0 8
8 8-O U
3/4 3-S6 Amendment No. 49, 101, _
.r. RAND GULF
- AIT 1
Anacnnvent a to GNRO-93.00049 Pags 10 of 11 INSTRUMrNTATION TABLE 4.3.6-1 see CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REOUIREMENTS NOTES:
Neutron detectors may be excluded from CHANNEL CALIBRATION.
a.
b.
Within 7 days prior to startup.
c.
[ Deleted]
d.
[ Deleted]
e.
[ Deleted]
f.
[ Deleted]
g.
[ Deleted]
h.
[ Deleted]
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
With THERMAL POWER greater than the Low Power Setpoint.
Whenever the related function is not bypassed as specified in Table 3.4.6-1 notes (a) through (c) i l
i e
F i
GRAND GULF-UNIT 13/4 3-57 Amendment No. 16, 49, +GE, __
Attachment a to GNRC-93i00049
~
^
Page 11 of 11 l'
j t
j SPECIAL TEST EXCEPTIONS i
3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS LIMITING CONDITION FOR OPERATION 1
The provisions of Specification 3.9.I, Specification 3.9.3 and Table 3.10.3 1.2 may be suspended to permit the reactor mode switch to be in the Startup i
position and to allow more than one control rod to be withdrawn for shutdown l
margin demonstration, provided that at least the following requirements are satisfied.
The source range monitors are OPERABLE per Specification 3.9.2 with the RPS circuitry " shorting links" removed.
l a.
t The rod pattern control system is OPERABLE per Specification 3.1.4.2, l
b.
or conformance with the shutdown margin demonstration procedure is verified by a second licensed operator or other technically qualified member of the unit technical staff.
The " continuous withdrawal" control shall not be used during out-of-e I
sequence movement of the control rods.
j c.
i j
d.
No other CORE ALTERATIONS are in progress.
i The Average Power Range Monitors are OPERABLE per the requirements of
)
Specification 3.3.1 for OPERATIONAL CONDITION 2.
l e.
t APPLICABILITY: OPERATIONAL CONDITION 5, during shutdown margin demonstrations.
)
2 4
ACTION:
I With tne requirements of the above specification not satisfied, immediately l
place the reactor mode switch in the Shutdown or Refuel position.
i j
l i
SURVEILLANCE REQUIREMENTS I
1 4.10.3 Within 30 minutes prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the performance of a shutdown margin demonstration, verify that; 3
I ThesourcerangemonitorsareOPERABLEperSpecification3.9.2withthe
~!
a.
RPS circuitry shorting link.s" removed.
The rod pattern control system OPERABLE, or a second licensed operator b.
or other technically qualified member of the unit technical staff is l
present and verifies compliance with the shutdown demonstration l
procedures, and j
c.
No other CORE ALTERATIONS are in progress.
5 i
l
{
4 Grand Gulf-Unit 1 3/4 10-3 Amendment No. __
r
_ -.