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Proposed Tech Specs Reflecting Changes to Surveillance Test Frequency Requirements for Various RPS Instrumentation
	ML20086S613
Person / Time
Site:	Limerick
Issue date:	07/28/1995
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20086S600	List: ML20086S598; ML20086S613;
References
	NUDOCS 9508020064
	Download: ML20086S613 (4)
	v • d • e

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. TABLE 4.3.1.1-1 .

r-g REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

o y '

CHANNEL OPERATIONAL

, CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH c FUNCTIONAL UNIT -

CHECK TEST CALIBRATION (a) SURVEILLANCE REQUIRED 5

1. Intermediate Range Monitors: '

.-- a. Neutron Flux - liigh %S S(b) W R 2 W(j) R 3,4,5

b. Inoperative N.A. W(j) N.A. 2,3,4,5

2. Average Power Range Monitor (f): # ~

a. Heutron Flux -

Upscale, Setdown

@ S(b) U , SA 2-3, 5(k)

S -Q- SA

b. Neutron Flux - Upscale.

w 1) Flow Biased S,0(g) Q W(d)(e),SA 1

[ 2) liigh Flow Clampeh S Q W(d)(e),SA 1

c. Inoperative .o$ N.A. Q(j) N.A. 1, 2, 3, 5(k)

d. Downscale 3 S Q SA 1

3. Reactor Vessel Steam Dome .

Pressure - High S Q R 1,2(h) g o m 4@ 4. Reactor Vessel Water Level-g-

U Low, level 3 S Q R 1, 2

"* 5. Main Steam Line Isolation Valve - Closure N.A. Q R 1 f

y 6. DELETED DELETED DELETED DELETED DELETED l R 1, 2 0 7. Drywell Pressure - High S Q

$ 8. Scram Discharge Volume Water Level - High 1,2,5(i)

R

a. Level Transmitter S Q 1, 2, 5(i)

b. Float Switch N.A. Q R 9508020064 950728 PDR ADOCK 05000352 P PDR .

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TABLE 4.3.1,1-1 (Centinued) -

s REACTOR PROTECTION SYST m INSTRUMENTATION SURVEILLANCE REQUIREMENTS

. ' E' OPERATIONAli C CHANNEL JCONDITIONSJFOR WilICll~

FUNCT10NAL ' CllANNEL '

E 'CliANNEL CALIBRATION SURVEILLANCE REQUIRED ~

_CllECK TEST'

$'FUNCTIONALUNIT n

Turbino Stop Valve - Closure N.A. Q 'R' 1 i 9.

. c

$ '10. Turbine Control Valve Fast Closure, Trip 011 1 N.A. R Pressure - Low Q I-1.1. -Reactor Mode Switch - N . A .- .1, 2,-3, 4, 5:

Shutdown Position N.A. R N.A. W N.A. 1, 2,~3, 4, 5:

12.- Manual " Scram .

j (a) Neutron detectors t9y be excluded from CilANNEL CALIBRATION. ~

(b)

The IRM and SRM channels shall be determined to overlap for at-least 1/2 decades during each startup-after i

entering CPERATIONAL CONDITION 2 and the-IRM and APRM channels shall- be determined to 6verlap for a least 1/2 i w , decades during each controlled shutdown, if not performed within the_ previous day.sm E L E.'l'EQ

), -

1 (c) 4W44hia wtulDrs priocto star.tupr-if-not-Derformed-wlthin-the-prevtous 7.-da This calibration shall consist of the adjustment of the Anci channel to confordr to'the power values calculated by~

. w s,(d)^ ' a h' eat; balance 'during OPERATIONAL CONDITION 1 when THERMAL POWER 225% of RATED THERMAL P

.; channel if the absolute difference is greater than 2% of RATED THERNAL POWER.

This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated: flow 1 (e) signal.

i The LPRMs shall be calibrated at-least once per 1000 effective full power hours (EFPH) using the TIP. system.

~

(f) Verify measured core floA(total core flow) to be greater than or equal:to estabitshed core flow at the existing -

, g (g) loop flow (APRM % flow). During' the startup test program,: data shall be recorded for the parameters listed to ,

m'" s provide a basis- for establishing the specified relationships. Comparisons of the actual data in accordance with en g-

' .g. the criteria listed shall commence upon the conclusion of the startup . test program, This function-is not required to' be _0PERABLE- when'the reactor pressure vessel head is remoyed per Spectfication ~e o " (h).

~

3.10.1.

f 1

With:any control rod withdrawn. Not applicable:to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

g g- O((j))' -if the RPS shorting links are required to be removed per Specification 3.9.2, .they may be reinst

- - hours for required surveillance. During this time, CORE ALTERATIONS shall be suspended, and no control rod shall:

O. be moved.from its existing position.

- (k) .. Required to be' 0PERABLE only prior to and during shutdown margin demonstrations:as _ performed per Specification,- ~

.g 3.10.3. -

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TABLE 4.3.1.1-1 r- -

%:o REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL OPERATIONAL

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR -WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION (a) SURVEILLANCE REQUIRED E

p 1. Intermediate Range Monitors: & S-m a. Neutron Flux - High MS S(b) JN/U(m .W 1(j)

R R

2 3,4,5

b. Inoperative N.A. W(j) N.A. 2,3,4,5

2. Average Power Range Monitor (f): v

a. Neutron Flux - S(b) '""c S SA 2 Upscale, Setdown S r, g SA 3, 5(k)

b. Heutron Flux - Upscale 'T

, 1) Flow Biased S.D(g) (31ttfcT)Q W(d)(e),SA 1

2) liigh Flow Clamped S MQ W(d)(e),SA 1 0 .c. Inoperative N.A. Q(j) N.A. 1, 2, 3, 5(k)

d. Downscale S Q SA 1

3. Reactor Vessel Steam Dome .

Pressure - liigh S Q R 1,2(h) y.

iii 5 4. Reactor Vessel Water level-Low, level 3 S Q R 1, 2 jf * -

p ,

4 cn 5. Main Steam Line Isolation Valve - Closure N.A. Q R - 1

" DELETED DELETED DELETED DELETED l v, 6. DELETED w

R 1, 2

7. Drywell Pressure - liigh S Q

-~

8. Scram Discharge Volume Water Level - liigh R

1, i)

Level Transmitter 1, 2, 5(i)

a. S Q N.A. R 2, 5(

b. Float Switch Q

TAELE 4.3;1.1-1 (Continued) -

p REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS .

' El CHANNEL OPERATIONAL iS CllANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WillCll 9 FUNCTIONAL UNIT CllECK _. TEST CALIBRATION- SURVEILLANCE RE0UIRED

~

9. Turbine Stop Valve - Closure N.A. Q R 1

10. Turbine Control Valve Fast Closure, Trip 011 '

Pressure - Low N.A. Q R 1

11. Reactor Mode Switch Shutdown Position N.A. R N.A. 1,2 3,4,.5

12. Manual Scram H.A. W N.A. 1,?,3,'4,5 l W I'" (a) Neutron detectors may be excluded from CllANNEL CALIBRATION.

(b) ' The IRH and SRM channels shall be determined to overlap for at least 1/2 decades during each startup after-entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall.be determined to overlap for a least 1/2 decades during each controlled shutdown, if not performed within the previous 7 da s.

(c) GlGiliin3GhourT_pitorZohMtup.,_lf._noLperatu d w1.tn.tn=the, prev 4nus-4-cay bss.LETEb) .

(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by .

a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER lt 25% of RATED THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

li;; f (e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow 2 signal. .

wk (f) The LPRMs shall be calibrated at least once per 1000 effective full power hours-(EFPH) using the TIP system.-

Verify measured core flow (total core flow) to be greater than or equal to established core flow at the existing R (g)

._, ' loop flow (APRM % flow). During the'startup test program, data shall be recorded for the parameters listed to 18 E- provide a basis for establishing the specified relationships. Comparisons of the actual data in accordance with

the criteria listed shall commence upon-the conclusion of the'startup test program.

y (h) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification

.0 3.10.1.

(1) With any control rod withdrawn. Not ap'p.llcable to control rods removed per Specificat!on 3.9.10.1 or 3.9.10.2..

$; (j) If-the RPS shorting links- are required to be removed per Specification 3.9.2, they may be reinstalled for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance. During this time, CORE ALTERATIONS shall be sus) ended,.and no control rod shall

~be moved from its existing position. 1 (k) Required to be OPERABLE only prior to and during shutdown ~ margin demonstrations as performed per Specification 3.10.3.

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ML20086S613

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