ML20214M073

Proposed Tech Specs,Permitting Recirculation Flow Transmitters for Three Functions to Be Calibr on 18 Month Basis

ML20214M073
Person / Time
Site:	River Bend
Issue date:	08/29/1986
From:	GULF STATES UTILITIES CO.
To:
Shared Package
ML20214M056	List: ML20214M073 RBG-24286, Application for Amend to License NPF-47,permitting Recirculation Flow Transmitters for Listed Three Functions to Be Calibr on 18 Month Basis.Fee Paid
References
NUDOCS 8609100528
Download: ML20214M073 (5)

Text

3 b

e ENCLOSURE 2 PROPOSED REVISED RIVER BEND TECHNICAL SPECIFICATIONS 8609100528 860929 PDR ADOCK 05000458 P

PDR

TABLE 4.3.1.1-1 5

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g

i CHANNEL OPERATIONAL 5

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION (,)

SURVEILLANCE REQUIRED i

b 1.

Intermediate Range Monitors:

a.

Neutron Flux - High S/U,S,(b)

S/U(c),W R

2 S

W R

3,4,5 b.

Inoperative NA W

NA 2,3,4,5 Average Power Range Monitor:(I) 2.

a.

Neutron Flux - High, S/U,S,(b)

S/U(c),W SA 2

Setdown S

W SA 3,4,5 1

Thermal Power - High S,D(h)

S/U(c),y y(d)(e), SA(,)R(I) b.

Flow Biased Simulated o

w 1

c.

Neutron Flux - High S

S/U(c),y g(d), SA 1

d.

Inoperative NA W

NA 1,2,3,4,5 3.

Reactor Vessel Steam Dome Pressure - High S

M R(9) 1,2(3) 4.

Reactor Vessel Water Level -

Low, Level 3 S

M R(9) 1, 2 5.

Reactor Vessel Water Level -

High, Level 8 S

M R(9) 1 6.

Main Steam Line Isolation Valve - Closure NA M

R 1

7.

Main Steam Line Radiation -

High S

M R

1,2(d)

R(9) 1, 2(I) 8.

Drywell Pressure - High S

M

~

)

TABLE 4.3.1.1-1 (Continued) l f

h REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS co h

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

j (g) Calibrate Rosemount trip unit setpoint at least once per 31 days.

e l

j5 (h) Verify measured drive flow to be less than or equal to established drive flow at the existing flow H

control valve position.

H (i) This calibration shall consist of verifying the simulated thermal power time constant to be less than 6.6 seconds.

(j) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(k) With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

i (1) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not j

required per Specification 3.10.1 (m) Verify the Turbine Bypass Valves are closed when THERMAL POWER is greater than w

l

}

or equal to 40% RATED THERMAL POWER.

(n) The CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION shall include the turbine 4

first stage pressure instruments.

M The CHANNEL CAtl8 RATION shall exdude.

ihe llow reference 4rans,n Her.3 4hese.

S'O *n

• Ne rs.s hall be calibrafed q) feaf once p,, g g __x,

i

9 TABLE 4.3.6-1 5

g CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL OPERATIONAL 5

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION (,)

SURVEILLANCE REQUIRED E

1.

ROD PATTERN CONTROL SYSTEM i

a.

Low Power Setpoint S(I)

S/

d)(e)

SA 1, 2 CI) b.

High Power Setpoint S

S/

d)(e)

SA 1

2.

APRM I

l a.

Flow Biased Neutron Flux -

SA M 1

S/U(b)

Upscale NA S/U(b),M b.

Inoperative NA

,M NA 1, 2, 5 m

)

c.

Downscale NA S/U

,M SA 1

d.

Neutron Flux - Upscale, Startup NA S/U

,M SA 2, 5 w

h 3.

SOURCE RANGE MONITORS S/U((b) W NA 2, 5 a.

Detector not full in NA S/U(b),W SA 2, 5 b.

Upscale NA S/U(b),W NA 2, 5 c.

Inoperative NA d.

Downscale NA S/U b),W SA 2, 5 4.

INTERMEDIATE RANGE MONITORS a.

Detector not full in NA S/U(b) W NA 2, 5 b.

Upscale NA S/U

,W SA 2, 5 S/U NA 2, 5 S/U(b),W c.

Inoperative NA

,W SA 2, 5 d.

Downscale NA 5.

SCRAM DISCHARGE VOLUME a.

Water Level-High NA M

R 1, 2, 5*

6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.

Upscale NA S/UID) M SA 1

l

TABLE 4.3.6-1 (Continued)

)

CONTROL R0D BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:

a.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

b.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.

c.

Within one hour prior to control rod movement, unless performed within the preyious 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and as each power range above the RPCS low power setpoint is entered for the first time during any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period during power increase or decrease.

d.

At least once per 31 days while operation continues within a given power range above the RPCS low power setpoint.

e.

Includes reactor manual control multiplexing system input.

f.

Verify the Turbine Bypass valves are closed when THERHAL POWER is greater than 20% RATED THERMAL POWER.

l With any control rod withdrawn.

Not applicable to control rods renoved per Specification 3.9.10.1 or 3.9.10.2.

I Calibrate trip unit setpoint once per 31 days.

3 The CHANNEL cal 8 EAT 10 AJ sha.Il excltade 4be +1ow reference.

harsmiHers, thest fransm Mers shall be calibrufel at lead once 'per I6 mon +h s.

)

RIVER BEND - UNIT 1 3/4 3-64