ML20205H831

Proposed Tech Specs Revising Setpoints for Main Steam Line Radiation Monitor Instruments to Allow Performance of Hydrogen Injection Tests Into Primary Coolant

ML20205H831
Person / Time
Site:	Hatch
Issue date:	03/20/1987
From:	GEORGIA POWER CO.
To:
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ML20205H824	List: ML20205H818 ML20205H831
References
NUDOCS 8704010156
Download: ML20205H831 (9)

Text

1 TABLE 2.2.1-1 3: REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS

-A b FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

i. Intermediate Range Monitor, Neutron Flux-High 5 120/125 divisions 5 120/125 divisions g (2C51-K601 A,B,C,D,E,F,C,H) of full scale of full scale

--I 2. Average Power Range Monitor:

g (2C51-K605 A,B,C,D,E,F)

a. Neutron Flux-Upsca le, 15% 5 15/125 divisions 5 20/125 divisions of full scale of full scale

b. Flow Referenced Simulated Thermal 5 (0.58 W + 59%), s (0.58 W + 62%),

Powe r-Upsca le with a maximum with a maximum 5 113.5% of RATED $ 115.5% of RATED THERMAL POWER THERMAL POWER

c. Fixed Neutron Flux-Upscale, 118% 5 118% of RATED 5 120% of RATED THERMAL POWER THERMAL POWER

3. Reactor Vessel Steam Dome Pressure - High 5 1054 psig 5 1054 psig (2B21-N678 A,B,C,D) 7 en

4. Reactor Vessel Water Level - Low (Level 3)

(2B21-N680 A,B,C,D) 2: 10 inches above instrument Zero*

t 10 inches above instrument zero*

5. Main Steam Line Isolation Valve - Closure 5 10% closed 5 10% closed (NA)

6. Main Steam Line Radiation - High 5 3 x fu l l-powe r s 3 x full-power (2D11-K603A,B,C,D) ba c kg round ** ba c kg round **

7. Drywell Pressure - liigh 5 1.92 psig 5 1.92 psig (2C71-N650A,B,C,D) s o

E y 87040103gg  %

o. yDR 0320

-4 ADOCK o5000366 xo PDR C

j *See Bases Figure B 3/4 3-1.

co **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 the reactor power at 7

o greater than 20% rated power, the normal full-power radiation background 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 f rom hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set 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 af ter completion of hydrogen injection and prior to establishirg reactor power levels below 20% rated power.

TABLE 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION ,

APPLICABLE MINIMUM NUMBER

[2 OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT COND*TIONS PER TRIP SYSTEMial ACTION e

c- 1. Intermediate Range Monitors:

gg (2C51-K601, A, B, C, D, E, F, C, H)

~ ~

a. Neutron Flux - High 2'*8., S'*8 3 .1 DO 3, 4 2 2

b. Inope ra t ive 2,5'*8 3 1 3, 4 2 2

2. Average Power Range Monitor:

(2C51-K605 A, B, C, D, E, F)

a. Neutron Flux - Upscale, 15% 2, 5 2 1

b. Flow Referenced Simula ted Thermal Power - Upsca le 1- 2 3

c. Fixed Neutron Flux -

Upscale, 118% 1 2 3

d. I nope ra t ive 1, 2, 5 2 4

e. Downscale 1 2 3

$g f. LPRM 1,2,5 (d) NA

3. Reactor Vessel Steam Dome Pressure -

jJ High (2821-N678 A, B, C, D) 1, 2(*8 2 5 ru

4. Reactor Vessel Water Level -

Low ( Leve l 3 ) (2821-N680 A, B, C, D) 1,.2 2 5

5. Main Steam Line Isolation Valve -

Closure (NA) l8 4 3

6. Main Steam Line Radiation - High 1, 25*8, 8J8 2 6 l

,a (2D11-K603 A, B, C, D) n 43 7. D rywe l l Pressure - High 1, 2('8 - 2 5 o (2C71-N650 A, B, C, D) co Q.

s 8

El a

e

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION 9.'- In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

In OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shutdown position within one hour.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully' insert all insertable control rods within one hour.

TABLE NOTATIONS

a. A channel may be placed in an inoperable status 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 without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter,

b. The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accordance with Specification 3.10.3.

c. The IRM scrams are automatically bypassed when_the reactor vessel mode switch is in the Run position and all APRM channels are OPERABLE and on

. scale,

d. An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.

e. These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.

f. This function is automatically bypassed when the reactor mode switch is in other than the Run position.

g. This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

'l h. With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.11.1 or 3.9.11.2.

i. These functions are bypassed when turbine first stage pressure is s250*

psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.

I J. 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 the reactor power at greater than 20% rated power, the normal full-power radiation background 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 determined and associated trip setpoints shall be set 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 hydrogen injection and prior to establishing reactor power levels below 20% rated power.

• Initial setpoint. Final setpoint to be determined during startup testing.

HATCH - UNIT 2 3/4 3-5 Proposed TS/0017q/87-09

TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION 5E

-j VALVE CROUPS- MINIMUM NUMBER APPLICABLE at OPERATED BY OPERABLE CHANNELS OPERATIONAL

, TRIP FUNCTION SIGNALfal PER TRIP SYSTEMfb)(c) CONDITION ACTION c: 1. PRIMARY CONTAINMENT ISOLATION 33 a. Reactor Vessel Water Level

-4 1. Low (Level 3) 2, 6, 10, 2 1,2,3 20 (2B21-N680 A, B, C, D) 11, 12 "O

2. Low-Low ( Level 2) 5,

• 2 1, 2, 3 20 (2B21-N682 A, B, C, D)

3. Low-Low-Low (Level 1) 1 2 1, 2, 3 20-(2821-N681 A, B, C, D)

b. D rywe l l Pressure - High 2, 6, 7, 10, 2 1,2,3 20 (2C71-N650 A, B, C, D) 12, *

! c. Main Steam Line

1. Radiation - High 1, 12, (d) 2 1, 2, 3,(J8 21 l (2D11-K603 A, B, C, D) l to 2. Pressure - Low 1 2 1 22

• % (2B21-N015 A, B, C, D)

• • 3. Flow - High 1, 2/line 1, 2, 3 21 ca (2B21-N686 A, B, C, D) 8 (2B21-N687 A, B, C, D)

[$ (2B21-N688 A, B, C, D)

(2B21-N689 A, B, C, D)

, d. Main Steam Line Tunnel Temperature - High 1 2/line(*8 1, 2, 3 21 (2B21-N623 A, B, C, D)

(2B21-N624 A, B, C, D)

(2B21-N625 A, B, C, D)

(2B21-N626 A, B, C, D)

I e. Condenser Vacuum - Low 1 2 1, 2,('8,3('8 23 j (2B21-N056 A, B, C, D) 4 ms

~5 f. Turbine Building Area 1 j$ Temperature - High 1 2(*) 1,2,3 21 4

o (2U61-R001, 2U61-R002, 2U61-R003, y 2U61-R004) a.

(n b

8 Ir D

7 O

j 4)

.; TABLE 3.3.2-1 (C ntinued)

ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 22 - Be in at least STARTUP within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

ACTION 23 - Be in at least STARTUP with the Group 1 isolation valves closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 24 - Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within one hour.

ACTION 25 - Isolate the reactor water cleanup system.

ACTION 26 - Close the affected system isolation valves and declare the affected system inoperable.

ACTION 27 - Verify power availability to the bus at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or close the affected system isolation valves and declare the affected system inoperable.

ACTION 28 - Close the shutdown cooling supply and reactor vessel head spray isolation valves unless reactor steam dome pressure s 145 psig.

NOTES

• Actuates the standby gas treatment system.

" When handling irradiated fuel in the secondary containment,

a. See Specification 3.6.3, Table 3.6.3-1 for valves in each valve group.

b. A channel may be placed in an inoperable status 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 without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

c. With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

d. Trips the mechanical vacuum pumps,

e. A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.

f. May be bypassed with all turbine stop valves closed.

g. Closes only RWCU outlet isolation valve 2G31-F004.

h. Alarm only.

1. Adjustable up to 60 minutes.

J. 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 the reactor power at greater than 20% rated power, the normal full-power radiation background 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 determined and associated trip setpoints shall be set 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 hydrogen injection and prior to establishing reactor power levels below 20% rated power.

HATCH - UNIT 2 3/4 3-15 Proposed TS/0091q/87-09

TACLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS . ,

r ALLOWABLE 3,5 r TRIP FUNCTION ~ TRIP SETPOINT VALUE ,

3: .

1. PRIMARY CONTAINMENT ISOLATION jE a. Reactor Vessel Water Level

-c

-4

1. Low (Level 3) 2 10 inches * . . 2 10 inches *

2. Low Low ( Leve l 2 ) 2 -47 inches *- 2 -47 inches

• ro 3. Low Low Low (Level 1) 2 -113 inches

• 2 -113 inches *

b. Drywel l Pressure -.High 5 1.92 psig 5 1.92 psig

c. Main Steam Line

1. Radiation - High 5 3 x ful l-power background ** 5 3 x ful l-power l.

backg round** l

2. Pressure - Low 2 825 psig - 2.825 psig

3. Flow - High 5 138% rated flow 5 138% rated flow

d. Main Steam Line Tunnel 4d Temperature - High s 194*F 5 194*F

, e. Condenser Vacuum - Low 2 7" Hg vacuum 2 7" Hg vacuum gg f. Turbine Building Area Temp.-High 5 200*F s 200*F

2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Exhaust Radiation - High 5 60 mr/hr 5 60 ar/hr

b. D rywel l Pressure - High 5 1.92 psig s 1.92 psig

c. Reactor Vessel Water Leve l - Low Low ( Leve l 2) 2 -47 inches

• 2 -47 inches *

d. Refueling Floor Exhaust Radiation - High 5 20 mr/hr 5 20 mr/hr 23 *See Bases Figure B 3/4 3-1 O

T3 **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 the reactor power at O greater than 20% rated power, the normal full power radiation background level and associated trip setpoints m may be changed based on a calculated value of the radiation level expected during the test. The background C' radiation level and associated trip setpoints may be adjusted during the test based on either calculations .

_a or measurements of actual radiation levels resulting from hydrogen injection. The background radiation .

La level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing 23 normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power cg levels below 20% rated power.

5$

s a

e

TABLE 3.3.6.7-1 (SHEET 1 OF 2)

MCRECS ACTUATION INSTRUMENTATION DC 3$ ' APPLICABLE r3 MINIMUM NUMBER DC OPERABLE CHANNELS OPERATIONAL e TRIP FUNCTION PER TRIP SYSTEM (alfbi CONDITION ACTION Ej 1. Reactor vessel Water Level - 2 1, 2, 3 52

>< Low Low Low (Level 1) (c)

-4 2821-N691 A, B,C,D i

r0

2. D rywe l l Pressure - High (c) 2 ' 1, 2, 3 52 2E11-N694 A, B, C, D

$ 3. Main Steam !.ine Radiation - High (c) 2 1, 2, 3,5*8 53 l 2 2D11-K603 A, B, C, D

, 4. Main Steam Line Flow - High (c) 2/line 1, 2, 3- 53 2821-N686 A, B, C, D

2B21-N687 A, B, C, D

! 2B21-N688 A, B, C, D 2B21-N689 A, B, C, D 00 5. Refueling Floor Area Radiation - High (c) 1 1, . 2, 3, 5,

• 54

1. • 2D21-K002 A, D w

• 6. Control Room Air inlet Radiation - High (C) 1 1, 2, 3,5,* 54. l 8

1Z41-R615 A, B o

7. Control Room Air inlet Chlorine Level - High (d) 1 1, 2, 3,4,5 55

1Z41-N022 A, B O

u, G

CL

(

,n.

O Z

N 00 Y

8 i

TABLE 3.3.6.7-1 (SHEET 2 0F 2)

MCRECS ACTUATION INSTRUMENTATION ACTION ACTION 52 -

Take the ACTION required by Specification 3.3.3.

ACTION 53 -

Take the ACTION required by Specification 3.3.2.

ACTION 54 -

a. With one of the required radiation monitors inoperable, restore the monitor to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the MCRECS in the pressurization mode of operation.

b. With no radiation monitors OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the MCRECS in the pressurization mode of operation,

c. The provisions of Specification 3.0.4 are not applicable.

ACTION 55 -

a. With one of the required chlorine detectors inoperable, restore the inoperable detector to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the MCRECS in the

-isolation mode of operation.

~

b. With no chlorine detectors OPERABLE, within I hour initiate and maintain operation of the MCRECSs in the isolation mode of operation.

c. The provisions of Specification 3.0.4 are not applicable.

NOTES When handling irradiated fuel in secondary containment.

a. A channel may be placed in an inoperable status 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 without placing the trip system in the tripped condition, provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

b. With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.6.7-1 for that Trip Function shall be taken,

c. Actuates the MCRECS in the control room pressurization mode.

d. Actuates the MCRECS in the control room isolation mode.

e. 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 the reactor power at greater than 20% rated power, the normal full power radiation background 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 determined and associated trip setpoints shall be set 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 hydrogen injection and prior to establishing reactor power levels below 20% rated power.

L i

HATCH - UNIT 2 3/4 3-58b Proposed TS/0091/87-09

TABLE 3.3.6.7-2 MCRECS ACTUATION INSTRUMENTATION SETPOINTS ",

x 3>

2N 1 RIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE

.r, 2:

e 1. Reactor Vessel Water Level - 2.-113 inches 2 - 113 inches c_ Low Low Low (Level 1)

~

!b 2. D rywe l l Pressure - High 5 1.92 psig 5 1.92 psig

-4 no 3. Main Steam Line Radiation - High - 5 3 x ful l-power backg round* 5 3 x full-power background

• i 4. Main Steam Line Flow - High 5 138% rated flow 5138% rated flow

. 5. Refueling Floor Area Radiation - High 5 20 mr/ hour 5 20 mr/ hour

6. Control Room Air inlet s 1 mr/ hour 5 1 mr/ hour j Radiation - High

7. Control Room Air inlet 5 5 ppe chlorine s 5 ppm chlorine Chlorine Level - High

)

w ln '

f?

Y 73 o

E i

cL u

1 o

i Osa *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 the reactor power at greater 20% rated

([ao power, the normal full power radiation background 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 j '4 setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels l E3 resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints us shall be set 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 af ter completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

5