ML17174A107

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Proposed Tech Spec Changes 1.1-3.2.3.,for Quad-Cities Facility
ML17174A107
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 11/01/1979
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17174A103 List:
References
NUDOCS 7911060364
Download: ML17174A107 (6)
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Text

ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION CHANGES FOR QUAD-CITIES 1 7911060

QUAD-CITIES DPR-29 t ,

- '* ,....J 1.112.1 FUEL CLADDING INTEGRITY SAFETY LIMIT LIMITING SAFETY SYSTEM SEITING Appllcabilily: Applicability:

The safety limits es1ablished to preserve 1he fuel The limi1ing safety system senings apply to trip cladding integri1y apply .10 !hose variables which settings of the instrumen1s and devices which are.

monitor the fuel 1hermal behavior. provided 10 prevent the fuel cladding in1egri1y safety limits from being exceeded.

.~bjeclive: Objecrh*e:

The objec1ive of the safely limils is 10 establish

  • The objec1ive of 1he limiting safety system se1,tings limits below which 1he in1egri1y of 1he fuel cladding is. 10 define 1he level of the process variables. at which is preserved. automatic pro1ec1ive aclion is initiaied to prevent the fuel claclclirig integrity safety limits fro111 being exceeded.

SPECIFICATIONS

  • l A Reactor Pressure :> 800 psia and Core Flow A. Neu.Iron Flux Trip Sl*ttings

> 10% of Rated The existence of a minimum critical power The limi1ing safely sys1em trip seuings shall be ratio (MCPR) less lhan 1.06 shall constitute as specified below:

8. Core Thermal Po"*er Limit (Reactor Pressure When the reactor mode switch is' in the S 800 psig) Run position. the APRM flux scram setting shall be as shown in Figure When the reactor pressure is s 800 psig or 2.1-1 and shall be:

core flow is less 1han 10% of rated, the core

. thermal power shall not exceed 25% of rated thermal power.

  • I Ss (58Wn + 62) (LTPF/TPF) with a maximum setpoint of 120% for core flow equal to 98 x 106 lb/hiand C Power Transient greater, I. The neutron flux shall not exceed the where:

scram seuing established in Specifica-tion 2.1.A for kmger than 1.5 seconds S . a selling in percent of raled as indicated by the pr<X:ess computer. power

2. When the process computer is out of service, this sarety limit shall be as-I w0 ""' perc~nl of drive flow re-quued 10 produce a ra1cd core flow of sumed to be exceeded. if the neutron 98 million I b/hr.

flux exceeds the scram setting estab-TPF .. LTPF unless the combina1ion lished by Specification 2.1.A and a of power and peak LHG R is above the con1rol rod scram does not occur.

1.112.1-1

QUAD-CITIES DPR-29 D. Reactor Waler Level (Shutdown Condition) curve in Figure 2.1-2, at which point Whenever the reactor is in the shutdown condi- the actual peaking factor value shall be used.

  • tion with irradiated fuel in the reactor vessel, the water level shall not be less than the corre- LTPF = 3.06 (7 x 7 fuel assemblies) sponding to 12 inches above the top of the 3.03 (8 x 8 fuel assemblies) active fuel* when it is seated in the core. 3.00 (8 x 8R fuel assemblies) .
2. APRM Flux Scram Trip Setting (Re-fueling or Startup and Hot Standby Mode)

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 I0% 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.

  • rop of active fuel is defmed to be 360 inches H. *Main steam.line low-pressure initiation* of main above vessel zero (see Bases 3 .2).

steamline isolation valye: closure shall be.

2': 850 psig.

I.I /2.1-2

DPR-29

~

130 120

.* 110 APRM FLOW 100 REFERENCE SCRAM \

(ALL MODES) \

90 "O

<lJ

!... 80

<+-

0

-~

....J 70 APRM ROD BLOCK lJ... 60 z

0 0::::

I-

> 50 w

z 40 30 20 10 0

0 20 40 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

Quad Cities DPR-29 ROD BLOCK APRM BACKUP SCRAM INTERCEPT LINE ______ _,,,,_

/

Af'R M ROD BLOCK LINE ( 0. '.)81.:ut )0 ROD RLOCK 1"-HiiClPT

/

/

tSi'<I*~ SC R l*M LIN[ (O.':J8'.*.'iJG2) 0 w

I- /

< ea -

er /

I I

w 0

er 3

a.

_.)

c:;,c1JL..:,

LINE j

J ION r~: '!*'.1 N~1 ,. (<'~..*,I: Nl 100/lOOPO'*"*l.l'l/FlO\'V LINE.

x t pON

r E.O -

c::

w I

I-w c::

0 u

~o .

Oi'll~A"JING RlGION ~,ur*;()Rl D UY N.f.D 0. - ?4167

  • - ~-o~~ r*u::.1*.'.:.;': ~o t 1NE * () !'"
  • 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.~

-a -

Rt.HD CON'.:111 IONS f'O'..JE:R.

( ORL 1.L O\..'

0 100 1 ::'()

40. t.O l~O 0  :;o

\.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

. TABLE 3.2.J INSTRUMENTATION THAT INITIATES ROD BLOCK Minimum !lumber at Operable or Tripped lastnament Cllannels per Trip System111

.* ~ ~

Instrument Trip level Settfn11

~ 1 (2) 2 APRM upscale (flow b1as)m It- .58Wn + 50. *. LTPF

-- TP~

2 APRM upscale (Refuel and Startup/Hot * :512/125 full scale * *

  • Standby model 2 APRM downscala171 ~3/ 125 full scale 1

Rod b!Ock monitor upscale (How bias~

Rod block monitor downscalem 71

,tt:,.

0.65WD + 42< >

2:3/ 125 full scale 2

I 3 IRM downscale <31 '81  ?:3/125 full scale 3 IRM ups ca 1e< 8l ~108/125 full sea.le 2'51 SRM detector not in Startup position< 41 2:2 feet below core center -

line 3 IRM detector not in Startup position1s1 2:2 feet below core center -

line c*~__ ;

2'5l (6) SRM upscale SW* counts/sec 2'5l SRM downscale'91 2: 102 counts/ sec High water level in scram discharge voluri1e :52~ gallons llotes

  • 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

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