ML17174A107
| ML17174A107 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 11/01/1979 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17174A103 | List: |
| References | |
| NUDOCS 7911060364 | |
| Download: ML17174A107 (6) | |
Text
ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION CHANGES FOR QUAD-CITIES 1 7911060
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QUAD-CITIES DPR-29 1.112.1 FUEL CLADDING INTEGRITY SAFETY LIMIT Appllcabilily:
The safety limits es1ablished to preserve 1he fuel cladding integri1y apply.10 !hose variables which monitor the fuel 1hermal behavior.
. ~bjeclive:
The objec1ive of the safely limils is 10 establish
- limits below which 1he in1egri1y of 1he fuel cladding is preserved.
LIMITING SAFETY SYSTEM SEITING Applicability:
The limi1ing safety system senings apply to trip settings of the instrumen1s and devices which are.
provided 10 prevent the fuel cladding in1egri1y safety limits from being exceeded.
Objecrh*e:
The objec1ive of 1he limiting safety system se1,tings is. 10 define 1he level of the process variables. at which automatic pro1ec1ive aclion is initiaied to prevent the fuel claclclirig integrity safety limits fro111 being exceeded.
SPECIFICATIONS
- A Reactor Pressure :> 800 psia and Core Flow
> 10% of Rated The existence of a minimum critical power ratio (MCPR) less lhan 1.06 shall constitute violation of the fuel cladding integrity safoty limiL
- 8.
Core Thermal Po"*er Limit (Reactor Pressure S 800 psig)
When the reactor pressure is s 800 psig or core flow is less 1han 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 seuing established in Specifica-tion 2.1.A for kmger than 1.5 seconds as indicated by the pr<X:ess computer.
- 2. When the process computer is out of service, this sarety limit shall be as-sumed to be exceeded. if the neutron flux exceeds the scram setting estab-lished by Specification 2.1.A and a con1rol rod scram does not occur.
1.112.1-1 A.
Neu.Iron Flux Trip Sl*ttings The limi1ing safely sys1em trip seuings shall be as specified below:
I I
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:
Ss (58Wn + 62)
(LTPF/TPF) with a maximum setpoint of 120% for core flow equal to 98 x 106 lb/hiand
- greater, where:
S.
a selling in percent of raled power w0 perc~nl of drive flow re-quued 10 produce a ra1cd core flow of 98 million I b/hr.
TPF.. LTPF unless the combina1ion of power and peak LHG R is above the
QUAD-CITIES DPR-29 D.
Reactor Waler Level (Shutdown Condition)
Whenever the reactor is in the shutdown condi-tion with irradiated fuel in the reactor vessel, the water level shall not be less than the corre-sponding to 12 inches above the top of the active fuel* when it is seated in the core.
- rop of active fuel is defmed to be 360 inches above vessel zero (see Bases 3.2).
I.I /2.1-2 curve in Figure 2.1-2, at which point the actual peaking factor value shall be used.
LTPF = 3.06 (7 x 7 fuel assemblies) 3.03 (8 x 8 fuel assemblies) 3.00 (8 x 8R fuel assemblies).
When the reactor mode switch is in the Refuel or Startup Hot Standby posi~
tion; the APRM scram shall he 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 ~aU not be operated in the natural circula-tion flow mode.*
- 8.
APRM Rod Block Setting The APRM rod block setting shall he as shown in Figure 2.1.-1 and shall be:
SS* (.58Wn + 50)
(LTPF/TPF)
The definitions used above for the APRM scram trip apply.
C. Reactor low water level scram setting shall be.
2': 143 inches ahove 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 top of the active fuel at normal operating conditions.
E. Turbine stop valve scram shall be s I 0% valve closure from full open.
F. Turbine control valve fast closure scram shall initiate upon actuation of the fast closure fole-noid valves which trip the turbine control valves.
G. Main steamline isolation valve closure scram shall be ~ 10% valve closure from full open.
H. *Main steam.line low-pressure initiation* of main steamline isolation valye: closure shall be.
2': 850 psig.
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0::::
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130 120
.* 110 100 90 80 70 60 50 40 30 20 10 0
0 DPR-29 APRM FLOW REFERENCE SCRAM \\
(ALL MODES)
\\
20 40 APRM ROD BLOCK 60 80 100 120.
REC IRCULA-T I-ON LOOP FLOW ( % of design)
FIGURE 2.1-1 APRM FLOW REFERENCE SCRAM AND APRM ROD BLOCK SETTINGS
0 w I-er er w
3 0 a.
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< :r c::
w I I-w c::
0 u ea -
E.O
~o.
- -a -
0 0
APRM BACKUP SCRAM Quad Cities DPR-29 ROD BLOCK INTERCEPT LINE
/
tSi'<I*~ SC R l*M LIN[ (O.':J8'.*.'iJG2)
J c:;,c1JL..:, j ION LINE
- o I
Af'R M ROD BLOCK LINE ( 0. '.)81.:ut )0 ROD RLOCK 1"-HiiClPT
/
I
/
/
/
r~: '!*'.1 N~1,. (<'~..*,I: Nl x t pON 100/lOOPO'*"*l.l'l/FlO\\'V LINE.
Oi'll~A"JING RlGION
~,ur*;()Rl D UY N.f.D 0. -
?4167
- 40.
~-o~~ r*u::.1*.'.:.;': ~o t 1NE t.O
- () !'"
- t *; j ~ *i n / ~ n n ::: i u !-~ 1 e Ln.:> p nr ~;,~tun1.l C:i rr11l.nt ion j s Limiter. per 'l'~c-h. Specs.
3.G.H.3 Rnd 2.1.A.~
Rt.HD CON'.:111 IONS f'O'..JE:R.
( ORL 1.L O\\..'
l~O 100
\\.J l,
<. ! llH I I 01.' I> fl 1 [
( ;l"* 01" I< r. I I 0) r ' cull r ?.. 1.. 3
('..>Uil 1*'.r,1 IC)
- ."'""' rt(),.* UI r.s
~.(R:-'*'. R[t.t.l 1():;'.:,.lil p 10 r:cnr-1t.!.. o;,ti:::.111:::. co:;DrltON5 1 ::'()
c*~
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Minimum !lumber at Operable or Tripped lastnament Cllannels per Trip System111 2
2 2
1 3
3 2'51 3
2'5l (6) 2'5l llotes QUAD-CITIES DPR-29
. TABLE 3.2.J INSTRUMENTATION THAT INITIATES ROD BLOCK Instrument APRM upscale (flow b1as)m APRM upscale (Refuel and Startup/Hot Standby model APRM downscala171 Rod b!Ock monitor upscale (How bias~
71 Rod block monitor downscalem IRM downscale <31 '81 IRM ups ca 1e<8l SRM detector not in Startup position<41 IRM detector not in Startup position1s1 SRM upscale SRM downscale'91 High water level in scram discharge voluri1e
- 9 Trip level Settfn11
. * ~ ~
~
1 (2)
It-
.58Wn + 50.
- . LTPF TP~
- 512/125 full scale
~3/ 125 full scale
,tt:,.
0.65WD + 42< 2>
2:3/ 125 full scale
?:3/125 full scale
~108/125 full sea.le 2:2 feet below core center -
line 2:2 feet below core center -
line SW* counts/sec 2: 102 counts/ sec
- 52~ gallons
- I.
Foi the Startup/Hot Standby and Run pos1t1ons of the *reactor mode selector switch. there shall be two operabla or.tri~ped trip systems tor each function except the SRM rod blocks. IRM upscale and IRM downscale need not be operable in the Run position. APRM downscale, APRM upscale !tlow biased), RBM *upscale, and RBM downsule need not be operable in the Startup/Hal Standby mode. If lhe first column cannot be met for one of the two trip systems. this condition may exist IOI up lo 7 days provided that durine that lime the operable system is functionally tested immediately and daily thereafter; 1f this cond;tion lasts long~r than 7 dip tho system shall be tripped. If the first column cannot be met for both trip systems. the systems shall be tripped.
I
- 2. \\i) is tllt ructar recirculation loop ftow in percent. Trip level settine is in percent of rated power (2511 MWI).
- 3.
IRM dowllse1le may be bypassed when ii is on its lowest range.
4
- Thrs function is bypassed when the count rate is.2:100 CPS.
One of the four SRM mpuls may be bypassed.
- 6.
- This SRM function may be bypassed in the higher IRM ranges (ranges 8. 9. and 101 when the IRM upscale rod block is operable.
- 1.
Not requ11ed to be operable while performing low power physics tests at atmospheric pressure durine or after relueling al powe1 levels not lo e1ceed 5 MWt.
- 8.
This IRM function occurs when the reactor mode switch is in the Refuel 01 Startup/Hot Standby position.
- 9.
This t11p is bypassed whtn lhe SRM is fully inserted.
3.214.2-14 I