ML17174A108
| ML17174A108 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 11/01/1979 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17174A103 | List: |
| References | |
| NUDOCS 7911060368 | |
| Download: ML17174A108 (6) | |
Text
ATTACHMENT 4 PROPOSED TECHNICAL SPECIFICATION CHANGES FOR QUAD-CITIES 2.
7911080
( _ __,
c*
QUAD-CITIES DPR-30 1.112.1 FUEL CLADDING INTEGRITY
. SAFE:TY LIMIT Applicability:
The safety limits established to preserve the fuel cladding integrity apply to* those variallles which monitor the fuel thermal behavior.
Objective:
The objective of the safety limits is to establish limits below which the integrity of the fuel cladding is preserved.
LIMITING SAFETY SYSTEM SETTING Applicability:
. The limiting safety system settings appiy to trip settings of the instruments and devices which are.
provided to prevent the fuel cladding integrity safety limits from peing exceeded.
Ohjecth*e:
The objective of the limiting safety system settings is to define the level of the process variables at whi<:h automatic protective action is initiated to prevent the fuel cladding integrity safety limits from being exceeded.
SPECIFICATIONS A.. Reactor Pressure > 800 psia and Core Flow
> 10% of Rated The existence of a minimum critical power ratio ( MCPR) less than 1.06 shall constitute violation of the fuel cladding integrity safety limit.
B.
Core Thermal Power Limit (neactor Pressure s 800 psig)
When the reactor pressure is s 800 psig or core flow rs less.than 10% of rated, the core thermal power shall not exceed 25% of rated thermal power.
C.
Power Transient I. The neutron flux shall not exceed the scram setting established in Specifica-tion 2.1.A for longer than 1.5 seconds as indicated by the process computer.
- 2. When the process computer is out of service, this safety iimit shall be as-sumed to be exceeded if the neutron flux exceeds the scram Sl!tting estab-lished by Specilication 2.1.A and a coritrpl rod scram does not occur.
1.1I2. 1-t A.
Neutron Flux Trip Settings The limiting safety system trip settings shall be as specified below:.
I. APRM Flux Scram Trip.Setting (Run.
Mode)
When the reactor mode switch is in the*
Run position. the APRM flux scram setting shall be as shown in Figure
.2.1-1 and shall be:
(LTPF/TPF) '
with a maximum setpoint of 120% for.
Ss (0.58WD + 62) core flow equal to 98 x 10' lb/hr and greater.
where:
S
= setting in percent of rated power Wo
. = percent of drive flow r~
quircd to produce a rated core flow of 98 million I b/ hr.
TPF = L TPr unkss thl* rnmhination of power and peak LHG R is a hove the:
-~-*
l
/
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QUAD-CITIES DPR-30 D. Reactor Water Level (Shutdown Condition)
Whenever the reactor is in 1he shutdown condi-tion with irradiated fuel in the reactor vessel, the water level shall not be less than that corre-sponding to 12 inches ahove the top of the active fuel when it is seated in the core.
1.1 /2.1-2 curve in Figure 2.1-2, at which point the actual peaking factor value shall be used.
L TPF = 3. 06 ( 7 x 7 fuel assemblies)
- 3. 03 ( 8 x 8 fuel assemhlies)
When the reactor mode switch is in. the Refuel or Startup Hot Standby posi-tion, the APRM scram shall be set at less than or equal to
- 15% of rated neutron flux.
- 3.
- IRM Flux Scram Trip Setting The IRM flux scram setting shall be set at less than or-equal to. 120/ 125 of full scale.
- 4. When the reactor mode switch is in the startup or run position, the -reactor sh*a11 not be. operated in the natural circula-tion flow mode.
B.
APRM Rod Block Setting The APRM rod block setting shall be as shown in Figure 2.1-1 and shall be:
SS (0.58Wn + 50)
(LTPF/TPF)
The definitions* used above for the APRM scram trip apply.
C. Reactor low water level scram setting shall be C!: 143 inches above the top of the active fuel at normal operating conditions.
D. Reactor low water level ECCS initiation shall be 83 inches ( + 4 inches/-0 inch) above the fop of the active fuel at normal operating conditions.
E. Turbine stop valve scram shall be s 10% valve closure from full open.
F. Turbine control valve fast closure scram shail initiate upon actuation of the fast closure sole-noid valves which trip 1he lurhine control Valves.
G. Main steam line isolation valve closure scram shall be s 10% v.alve closure from full open.
H. Main steamline low-prl'SSUre initi;1tilln or main steamline isolation valve closure shall be
- ? 850 psig.
130 120 110 100 90 "Cl CJ
.µ
'O*.
BO
~
4-0
~*
70 x
_J 60 L..!...
z:
0 C'.'.
r I-50 LLI z
40
' 30 20 10 0
0 QUAD-CIT I ES
REFERENCE SCRAM \\
(ALL MODES)
\\
20 40
~
APRM ROD.BLOCK 60 80 RECIRCULATION LOOP FLOW(% of-design)
FIGURE 2.1-1 100 APRM FLOW REFERENCE SCRAM 120
0 w I-a:
L...
0 a:
w 3
0 a.
c:
- w I
1-lJ c:
0 u 120 100 -
eo *-.
50 -
40
- '() -
APRM BACKUP SCRAM Quad Cities DPR-30 ROD BLOCK INTERCEPT LINE
~-
/
iPRM SCRAM l IN[ ( 0. ')8* *.'0 62)
I
'"AOU;UL J,'
I (iil(UL-"\\ 1 ION ur.iE
/
/
N(;:.*. 1.1~ Al.,
!. (l:~:;T 11!JT X IJJON
-- 1o'01100;-0-.-.*1,1;/J"l 0*:1 LJNE OPlRAl ING HIGION SUr'i\\")ln D UY N.[.0 0. -
2~167
- ll1.r*":!ti11;'. <*n ;.?n/',lc T.c*-op or fl;d.ura.l. t>ircullll.il.1!'1 js
- l i r:i:i i.,o:d 11c:y 'f'cc h.
~ l'L*c s.
3.6.H.3 and 2.. 1.A.~
I 'll'~'I: R COrt[ fl 0\\..'
OL-___
__...r_~__,~
!':O BO 100 40 1 :'O 0
- o
\\.J T. c (IR l I I. ow II Al [
(,: or Rt. 110) f1U11?[ 2.1-3
(:SCH(l*':.T IC)
- t. I 'i<M fl ()...' l3 I t. '...
'.,( IUJ*'. 1-H l I. T I (l: :'..ti I P
., 0
- '.J"'Hf,\\
(li'I I;/\\ 1 Ir:~. ( (HJiJ 11 I n1:s
i l
I
- ~......
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QUAD-CITIES DPR-30 TABLE 3.2-3.
INSTRUMENTATION THAT INITIATES ROD BLOCK Minimum Number of Operable or Tripped Instrument Channels per Trip System1 I) 2 2
Instrument APRM upscale (flow bias~n Trip Level Setting
~.sawn +
- -1 LTPF (.2).: '
SO_J TPF 2
3 3
2(5l 3
2'51 (6) 2'5)
Notes APRM upscale (Refuel and Startup/Hot Standby model APRM downscalem Rod block monitor upscale (flow biaslm Rod block monitor downscalem IRM downscale 13i 181 IRM upsc~lei 81 SRM detector not in Startup position141 IRM detector not in Startup positiqn18l SRM upscale SRM downscale191 High water level in scram discharge volume sl2/125 full scale
~3/125 full scale 0.65Wn + 42( 2)
~31125 full scale
~31125 full scale s 108/ 125 full scale
~2 feet below core center-line
~2 feet below core center-line sl05 counts/sec
~ 102 counts/sec s25 gallons
- I.
For the Startup/Hot Standby and Run positions of the reactor mode selector switch, there shall be two operable or tripped trip systems for each function exce*pt.
the SRM rod blocks. IRM upscale and IRM downscale need not be operable in the Run position, APRM downscale, APRM upscale (flow biased), RBM upscale. and RSM downscale need not be operable in the Startup/Hot Standby mode. II the lirst column cannot be met for one ol the 'two trip systems, this condition may exist for up to 7 days provided that during that time the operable system is functionally t.ested immediately and daily thereafter; if this condition lasts longer than 7 days the system shall be tripped. II the first column cannot be met for both trip systems. the systems shall be tripped.
- 2. WD is the react01 recirculation loop How in percent. Trip level setting is in percent of rated power (2511 MWtl.
- 3.
IRM downscale may be bypassed when it is on its lowest range.
- 4.
This function is bypassed when the count rate is ~100 CPS.
- 5.
One of the four SRM inputs may be bypassed.
- 6.
This SRM function may be bypassed in the higher IRM ranges (ranges 8. 9, and 10) when the IRM upscale rod block is operable.
7.*
Not.required to be operable while performing low power physics tests at atmospheric pressure during or alter refueling at powar levels not to exceed 5 MWt:
- 8.
This IRM function occurs when the reactor mode switch is in the Refuel or Startup/Hot Standby position.
- 9.
This trip is bypassed when the SRM is fully inserted.
3.2/4.2-14 I