U-601163, Proposed Tech Spec Tables 2.2.1-1, Reactor Protection Sys Instrumentation Setpoints & 3.3.2-2, Containment & Reactor Vessel Isolation Control Sys

Proposed Tech Spec Tables 2.2.1-1, Reactor Protection Sys Instrumentation Setpoints & 3.3.2-2, Containment & Reactor Vessel Isolation Control Sys

ML20154J013
Person / Time
Site:	Clinton
Issue date:	05/18/1988
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20154J009	List: ML20154J005 U-601163, Proposed Tech Spec Tables 2.2.1-1, Reactor Protection Sys Instrumentation Setpoints & 3.3.2-2, Containment & Reactor Vessel Isolation Control Sys
References
U-601163, NUDOCS 8805260147
Download: ML20154J013 (6)

Text

.

TABLE 2.2.1-1 ,

Ugg REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS "8

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE o~

Q$ 1. Intermediate Range Monitor O$ a. Neutron Flux-High < 120/125 divisions < 122/125 divisions 88 if full scale of full scale 00*

of b. Inoperative NA NA

2. Average Power Range Monitor:

a. Neutron Flux-High, Setdown < 15% of RATED < 20% of RATED THERMAL POWER THERMAL POWER

b. Flow Biased Simulated Thermal Power-High

1) Flow Biased 5 0.66 (W-AW)+48%,(a) 5 0.66 (W-oW)+51%,(a)

'? with a maximum of with a maximum of w 2) High Flow Clamped < 111.0% of RATED < 113.0% of RATED THERMAL POWER THERMAL POWER

c. Neutron Flux-High < 118% of RATED < 120% of RATED THERMAL POWER THERMAL POWER

d. Inoperative NA NA

3. Reactor Vessel Steam Dome Pressure - High 5 1065 psig i 1080 psig

4. Reactor Vessel Water Level - Low, Level 3 > 8.9 inches above > 8.3 inches Instrument zero* above instrument zero

5. Reactor Vessel Water Level-High, Level 8 < 52.0 inches above < 52.6 inches above Instrument zero* Instrument zero ygR

6. Main Steam Line Isolation Valve - Closure 1 8% closed i 12% closed $

7. Main Steam Line Radiation - High < 3.0 x full power < 3.6 x full E Eackground e t Background

• Eower l nu m

TABLE 2.2.1-1 (Continued) ..

b REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS

'i E

i FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE

8. Drywell Pressure - liigh 5 1.68 psig $ 1.88 psig w 9. Scram Discharge Volume Water Level - High

a. Level Transmitter IC11-N601A 5 30 in.1 5 40 1/4 in.

IC11-N601B 5 30 in.t 1 40 1/4 in.

IC11-N601C $ 30 in.tt i 35 3/16 in.

IC11-N6010 $ 30 in.tt i 39 3/16 in.

b. Float Switch IC11-N013A $ 762 ft. 1.375 in. ms1 1 763 ft. 3 1/4 in. ms1 7 1C11-N0138 5 762 ft. 1.125 in. ms1 5 763 ft. 3 1/4 in. ms1 s.

IC11-N013C 5 762 ft. 0.75 in ms1 5 763 ft. I 11/16 in. ms1  %

IC11-N013D 5 762 ft 1.125 in. ms1 5 763 ft. I 11/16 in. ms1

10. Turbine Stop Valve - Closure 5 5% closed 1 7% closed

11. Turbine Control Valve Fast Closure, Valve > 530 psig > 465 psig Trip System Oil Pressure - Low RA NA

12. Reactor Mode Switch Shutdown Position NA NA Manual Scram NA NA 13.

(a)The Average Pbwer Range Monitor Scram Function varies as a function of recirculation loop drive flow (W).

AW is the difference in indicated drive flow (in percent of drive flow which produces the same core flow) between two loop and single loop operation at the same core flow. AW = 0 for two loop operation. AW = 8% 28 R for single loop operation. E c: E

• See Bases Figure B 3/4 3-1. J E-o S P.

tInstrument zero is 759 ft. 11 in. ms1 r7 ?,

ftInstrument zero i: 759 ft. 10.5 in. ms1 t" ,,

ce Inse.ct A1tede.d

r-Attachmsnt 2 to U-60ll63 Page 9 of 12 '

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection >

test, with reactor power at greater than 20% of RATED THERMAL POWER, the ,

normal full power background radiation level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints any be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be verified and the associated trip setpoints shall be returned.to their normal value within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection test at greater than 20% of RATED THERMAL POWER or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% of RATED THERMAL POWER.

TABLE 3.3.2-2 (Continued)

O .

E CRVICS INSTRUMENTATION SETPOINTS 3

z TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE

$ 1. PRIMARY AND SECONDARY CONTAINMENT ISOLATION (Continued) g k. Containment Pressure - High s 2.62 psid i 3.00 psid

1. Main Steam Line Radiation - High 5 3.0 x full p wer background 5 3.6 x full power background

m. Fuel Building Exhaust Radiation -

High 5 10 mR/hr 5 17 mR/hr

n. Manual Initiation NA NA

2. MAIN STEAM LINE ISOLATION

, a. Reactor Vessel Water Level -

g Low Low Low, Level 1 1 -145.5 in.* 1 -147.7 in.

w

b. %in Steam Line Radiation - High 5 3.0 x full power background 4

5 3.6 x full power background 4 (

4 w

c. Main Steam Line Pressure - Low 1 849 psig 1 837 psig

d. Main Steam Line Flow - High 5 170 psid** 1 178 psid**

c. Condenser Vacuum - Low 1 8.5 in. Hg vacuum 1 7.6 in. Hg vacuum

f. Main Steam Line Tunnel Temp. - High 1 165 F $ 176*F

g. Main Steam Line Tunnel A Temp. - High $ 54.5"F s 60*F

h. Main Steam Line Turbine Bldg. , ,, >

Temp. - High 5 131.2*F 1 138 F g o ;;

• ?8

i. Manual Initiation NA NA gg[

~m

3. REACTOR WATER CLEANUP SYSTEM ISOLATION 9, ;;' %

a. A Flow - High 5 59 gpm 5 66.1 gpm C

b. A Flow Timer .. 1 45 sec. 1 47 sec.

. ~.

TABLE 3.3.2-2 (Continued) 9 y CRVICS INSTRUMENTATION SETPOINTS A

x TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE E

Q 5. RHR SYSTEM ISOLATION (Continued) w

c. Reactor Vessel Water Level -

Low, level 3 > 8.9 in.* > 8.3 in.

d. Reactor Vessel Water Level -

Low Low Low, Level 1 > -145.5 in.* -

> -147.7 in.

e. Reactor Vessel (RHR Cut-in Permissive) Pressure - High 5 135 psig** 5 150 psig**

w f. Drywell Pressure - High x

[ 1) Containment Spray 5 1.68 psig i 1.88 psig '

4 2) Fuel Pool Cooling 5 1.68 psig i 1.88 psig s

g. Manual Initiation NA NA

• See Bases Figure B 3/4 3-1.

C* Initial setpoint. Final setpoint to be determined during startup test program. Any required change to this setpoint shall be submitted to the Commission within 90 days of test completion.

sp Insec+ A w ched

% c" U "

a. : n gN

Attachment 2-

. . ;o U-60ll63

. Page 12 of 12 Within 24 houra prior to the planned start of the hydrogen injection test, with reactor power at greater than 20% of RATED THERMAL POWER, the normal full power background radiation level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be verified and the associated trip setpoints shall be returned to their normal value within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection test at greater than 20% of RATED THERMAL POWER or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% of RATED THERMAL POWER.

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