ML20207K329

Proposed Tech Spec Changes,Adding &/Or Clarifying Operability & Surveillance Requirements Re ATWS Recirculation Pump Trip Instrumentation

ML20207K329
Person / Time
Site:	Hatch
Issue date:	07/18/1986
From:	GEORGIA POWER CO.
To:
Shared Package
ML20207J957	List: ML20207J953 ML20207K329
References
TAC-55543, NUDOCS 8607290394
Download: ML20207K329 (17)

Text

r- ,

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUFREMENTS-SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-24 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-33 3/4.3.5 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION 3/4 3-37 3/4.3.6 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-43 Seismic Monitoring Instrumentation 3/4 3-47 Remote Shutdown Monitoring Instrumentation 3/4 3-50 Post-Accident Monitorir.g Instrumentation 3/4 3-53 Source Range Monitors 3/4 3-56 Traversing Incort Probe System 3/4 3-57 Chlorine Detectors 3/4 3-58 Fira Detection Instrumentation 3/4 3-59 Radioactive Liquid Effluent Instrumentation 3/4 3-60a Radioactive Gaseous Effluent Instrumentation 3/4 3-60f 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEh 3/4 3-61 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION 3/4 3-63 3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION 3/4 3-66 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops 3/4 4-1 HATCH-UNIT 2 V e607290394 e6071s PDR ADOCK0500g6 P

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)

Jet Pumps 3/4 4-2 Idle Recirculation Loop Startup 3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES 3/4 4-4 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems 3/4 4-5 Operational. Leakage 3/4 4-6 3/4.4.4 CHEMISTRY '3/4 4-7 3/4.4.5 SPECIFIC ACTIVITY 3/4 <-10 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System 3/4 4-13 Reactor Steam Dome 3/4 4-18 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 3/4 4-19 3/4.4.8 SThUCTURAL INTEGRITY 3/4 4-20 3/4.5 FMFRGENCY CORE COOLING SYSTEMS 3/4.5.1 HIGH PRESSURE COOLANT INJECTION SYSTEM 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM 3/4 5-3 3/4.5.3 LOW PRESSURE CORE COOLING SYSTEMS Core Spray System 3/4 5-4 Low Pressure Coolant Injection System 3/4 5-7 3/4.5.4 SUPPRESSION CHAMBER 3/4 5-9 HATCH-UNIT 2 VI

j1lJll l l

_ ~

N O .

I A

T 1212 1 3 3o3N t 5 5 3 6 5 C

A l

Sa L(

REM ENE BNT MAS UlY l NCS )

d MEP 3232 2 2 222( 2 2 84 2 2 ULI MBR IAT NR IER MPE OP N

O I

T A

T L N EAS '

E LNN '

M '

U BOOI AI S 5 5 ' 8 '

R CTT ' ' * '

T IAI , , ,

S N

LRD PEN

'4 4 '5 5 2 2 '2 2 '

8 2

8 2

1 I PPO ' ,,, , , , , , ' , ,

- AOC 2323 2 1 1111 1 1 I 1 1 1 M

. E 3 T S

3 Y S

E L N B O A I T T C

E T

O R )

P D R ) ,

O T

H e r

C C ,

u , h C  % s B e g U

B 5 s v i

, 1de e) , l H

F s

) el rD A a r ,

rF ,ta P V -

oE o, leac t l s eC

, l0 e8 n n t iE aup- m v6 o o) )

, h n cmU o, eN i iD hD inD ig o, si x DB L- t t g o, MD pS u 1 a a , ,

M C

H e ,

U drF%

l m, aA r2 eB l

o iC d

iiC l

e, g

- gC ee 8 e t2 s a , - ,

nB x n, a

cwn1 xnoo1 t8 S7 a(

W)

I RB e,

B a u e RB uePr e l6 e e, r R , l v r, l r t ,v N l3 n) nA uA A F i Fel ueie e- e iA s te, n a t eA w

fael tl nemNaaa s1 sl se LN iL3 s0 s2 ( 0 e5 T a1 o r o5 oRr crc e8 ev m m6 r6 I

N i0 r ep P0 r edses V2 Ve ae ak PN d6 t 6 twheppnM ( L er e- -

U ek u o ek uoTxUowR r r( tu t1 11 m- e n g- el i InoP oh o Ss S1 l7 A

L r1 N I a1 NF F DL tg tw o D eC N

e5 r5 ci co nl n2 v2y(

tC eC aH aL iC i(

O v2 ... e e a r I In2 ( a b A(

ab c deF R R M M a

D T

C N . . . . . . .

U 1 2 3 84 5 6 7 F

I>dQ

~ t CZ[ ro )

b] wen u

~

7 TABLE 3.3.1-1 (Continued) ,

3 REASTOR PROTECTION SYSTEM INSTRUMENTATION E) APPLICABLE MINIMtfM NUMBER ,

r7 OPERATIONAL OPERABLE CliANNELS

C FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a) ACTION

' 8. Scram Discharge Volume Water c: Level - Ifigh (2C11-N013A,B.C D) 1, 2, 5'"' 2 4

== Level - High (2C11-N060A,B,C,D) 1, 2, 5 2 4

9. Turbine Stop Valve - Closure (N4) l 4 7 l h3

10. Turbine Control Valve rest Closdre, Trip Oil Pressure - Low I 2 7 l (2C71-N005A,B,C,D) 11 Reactor Mode Switch in Shutdown Position (NA) 1, 2, 3,4,5 1 8

12. Manual Scram (NA) 1, 2, 3, 4, 5 1 9 W

N 4

W I

W e

f ll

~

-a

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 lin the Run position and all APRM channels are OPERABLE and on scale.

d. An APRM 3ch nnel 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.

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.

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

HATCH - UNIT 2 3/4 3-5

INSTRUMENTATION 3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMD TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.9.1 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3.3.9.1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.9.1-2.

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION:

a. With an ATWS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table .3.9.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value.

b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, declare the affected trip system's) inoperable.

c. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 14 days or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

d. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.3.9.1.1 Each ATWS recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.9.1-1.

4.3.9.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

HATCH - UNIT 2 3/4 3-66 I

c TABLE 3.3.9.1-1 -

2=

%r ATWS RECIRCULAT'*N PUMP TRIP SYSTEM INSTRUMENTATION s ,

MINIMUM OPERABLE CHANNELS PER g

^

TRIP FUNCTION TRIP SYSTEM

$ 1. Reactor Vessel Water Level - Low Lov, Level 2 1

2. Reactor Vessel Pressure - High 1 N.

e, N

(

l

s e ig h

E c sp L n BE i AU 0 WL 5 2 OA 5 1 LV - 1 L

A _ 2 5 S

T N

I C

P T

E S

N O

I T

A T

N E

M U

• R T s S T e ig 2 N N h

- I Pl c sp 1 Io n M RP i 9 E TT 0 T E 5 2 3 S S 5 1 Y - 1 3 S 2 5 E P L I B R A T T

P M

U P

N O

I 2

T l A e L v U e C L R

I ,

C w E o R L S w W

T L o

A h

- g i

l H

e v -

e

- L e r

1 r u -

e s 3 t s a e fs W rP /

3

, 8 l l e e e s s r s s u e e g N V V i O F

_ I r r T o ot s C t e N c c s U a a a F e e B

- R R P e I

e

. R . . S T 1 2 *

. h4Q - i cZ-Nb Yno co

N -

O LI ET NA NR R R AB ll lCl A

C N

I O

T L A A T LN N E0T

_ E NlS M NiE R R U LACT R N

. T lCU S F N

I S I

NN 0E l M 1 iE

- AR 1 UI

. TU 9 CQ AE 3 R P

4 IE RC E TN L A B PL A 4L i

T UI PE V

NR L _

OU EK I S NC T N( S A A Ai l N

L l lC U C C

R l

c E

R S

W

. 1, f

w o

L h g

- i i

l l

e -

v e e L r u

r s e s t e a r W P l l e e s2 s s s el e y Ve V 0 v t

re r i ol o C t t N c , c F

U nw eo e a

Rt R P

I R . .

T 1 2 0jx 3- t :54 #

c[ ~ D w V' 8

INSTRUMENTATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION

~

3.3.9.2 The end-cf-cycle recirculation pump trip (E0C-RPT) system instrumentation channels shown in Table 3.3.9.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Tabla 3.3.9.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.9.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.

ACTION:

a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9.2-2,. declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.

b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within one hour.

c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:

1. If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within one hour.

2. If the inoperable channels include two turbine control valve cnanners or two turoine stop varve cnanneis, ceclare tne trip system inoperable.

d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

HATCH - UNIT 2 3/4 3-70

INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.9.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.9.2.1-1.

4.3.9.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

4.3.9.2.3 The END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME of each trip function shown in Table 3.3.9.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least the logic of one type of channel input, turbine control valve fast closure or turbine stop valve closure, such that both types of channel inputs are tested at least once per 36 months.

HATCH - UNIT 2 3/4 3-71 m

SE TABLE 3.3.9.2-1

--4

[2 [N[-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION i; ,

c: MINIMUM sc OPERABLE CalANNELS

[] TRIP FUNCTION PER TRIP SYST[M

8 DJ 1. Turbine Stop Valve - Closure *3 28

2. Turbine Control Valve - Fast Closure 28*8 N

4 Y

N N

• • 3A trip system 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 provided tha t the other trip system is OPERABLE.

8*8This function shall be automatically bypassed when turbine first stage p re s su re is less than or equal to 250 psig, equivalent to THERMAL POWER less than 30 % of RATED THERMAL IOWER.

s L

1 TABLE 3.3.9.2-2 M

n END-OF-CYCL E RECIRCULATION PUMP TRI P SETPolMlf 1 ,

IRIP FUNCTION TRIP SETPolMI At t oWABL E VAL UE C

z 1. Turbine Stop Valve - Closure s 10% closed 5 10% closed N

2. Turbine Control Valve - Fast Closure 2 600 psig 2 600 psig 1

4 b

Y

! O

l s

d n

o c

e s

i 1

i i

M 5 5

( 3 3 1 1 E

M 5 s I

T E

S N

O P

S E

E R M

I T

E S

N O

P S

E R

M E

T S

Y S

3 P

- I 2 R T

9 P

JMU 3 P E N L O B I A T T A t

u C

t i

l C

E R

E L

C Y

C F

O e

- r D

4 u

s

{J l o

C e t r s u

s aF o

l C

e

- v l e a l

v V a l V o r

p t o n t o N S C 0 -

1 e e T n n C i i N b b U r r F u u T T P

I R . .

T 1 2 5M:t ,

c2Q ro .YX

e i

_g TABLE 4.3.9.2.1-1 23 q END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENll x

' CHANNEL c- FUNCTIONAL CHANNEL

[E TRIP FUNCTION TEST CALIBRATION

~

1. Turbine Stop Valve - Closure M* R ro

2. Turbine Control Va lve - Fa s t Clo s u re M* R w

4 Y

Di

• The Recirculation Pump Breakers neeil not be tripped on part or'the Channel functional Test. All channel alarm functions and only that portion of the trip functions which can be tested trithout causing a trip of the Breakers (and Recirculation Pumps) need be tilsted during the Channel Functional Test.

{;. .-

INSTRUMENTATION BASES 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION The undervoltage relay's shall automatically initiate the disconnection of offsite power sources whenever the voltage setpoint and time delay limits have been exceeded. This action shall provide voltage protection for the emergency power systems by preventing sustained degraded voltage conditions due to the offsite power source and interaction between the offsite and onsite emergency power systems. The undervoltage relays have a time delay chcracteristic that provides protection against both a loss of voltage and degraded voltage condition and thus minimizes the effect of short duration disturbances without exceeding the maximum time delay, including margin, that is assumed in the FSAR accident analyses.

3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NED0-10349, dated March 1971, and NEDO-24222, dated December 1979.

The end-of-cycle recirculation pump trip (ECC-RPT) system is a part of the Reactor Protection System and is an essential safety supplement to the reactor trip. The purpose of the EOC-RPT is to recover the loss of thermal margin which occurs at the end-of-cycle. The physical phenomenon involved is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity. Each EOC-iti'T system trips corn recirculation pumps, reducing cooient flow in order to reduce the void collapse in the core during two of the most limiting pressurization events. The two events for which the EOC-RPT protective feature will function are closure of the turbine stop valves and fast closure of the turbine control valves.

A fast closure sensor from each of two turbine control valves provides input to the EOC-RPT system; a fast closure sensor from each of the other two turbine control valves provides input,to the second E0C-RPT system. Similarly, a limit switch for each of two turbine stop valves provides input to one l EOC-RPT system; a limit switch from each of the other two stop l

valves provides input to the other EOC-RPT system. For each EOC-RPT system, the sensor relay contacts are arranged to form a 1-out-of-2 twice logic for the fast closure of turbine control HATCH - UNIT 2 8 3/4 3-Sa

g

, s

h. b i.

INSTRUMENTATION

. BASES 3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION (Continued) valves and a 2-out-of-2 logic for the turbine stop valves. The operation of either logic will actuate the E0C-RPT system and trip both recirculation pumps.

Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled. The manual bypasses and the automatic Operating Bypass at less than 30% of RATED THERMAL POWER are annunciated in the control room.

HATCH - UNIT 2 B 3/4 3-5b L