ML20084D024

Proposed Tech Specs,Providing Clear Surveillance Requirements & Setpoints for Demonstrating Operability of ATWS Recirculation Pump Trip Instruments

ML20084D024
Person / Time
Site:	Hatch
Issue date:	04/23/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20084D020	List: ML20084D017 ML20084D024
References
TAC-55543, NUDOCS 8405010141
Download: ML20084D024 (8)

Text

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m. TABLE 3.3.1-1 '

Y, E- REACTOR PROTECTION SYSTBf INSTRUMENTATION c

E APPLICABLE MINIbiN NUMBER OPERATIONAL OPERABLE GANNELS FlNCTIONAL UNIT CONDITIONS PER 'IRIP SYSTBf(a) ACTION

1. Intermediate Range Monitors:

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

a. Neutron Flux - High 2(c),5(b) 3 3 3, 4 2 2

b. Inoperative 2, 5(b) 3 1 3, 4 2 2

2. Average Pbwer Range Monitor (2C51-K605 A, B, C, D, E, F)

a. Neutron Flux - Upscale, 15% 2, 5 2 1 w b. Flow Referenced Simulated O Thermal Power - Upscale 1 2 3

c. Fixed Neutron Flux -

Upscale, 118% 1 2 3

d. Inoperative 1, 2, 5 2 4

e. Downscale 1 2 3

f. LFRM 1,2,5 (d) NA

3. Reactor Vessel Steam Dome Pressure -

High (2B21-N023 A, B, C, D) 1, 2(e) 2 5

4. Reactor Vessel Water Level - 1,2 2 5 Low (2B21-N017 A, B, C, D) 5.- Main Steam Line Isolation Valve -

Closure (NA) 1(f) 4 3

6. Main Steam Line Radiation - High 1, 2(e) 2 6 (2D11-K603 A, B, C, D)

, 7. 1, 2(E) 2 5

. Dryw(ell Pressure - High2C71-N002 A, B, C, D) 8405010141 840423 DR ADOCK 05000366 PDR

3: -

TABLE 3.3.1-1 (Continued) g REACTOR PROTECTION SYSTEM INSTRUMENTATION APPLICABLE MINIKIM NUMBER OPERATIONAL OPERABLE WANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTBi(a) ACTION

8. Scram Discharge Volume Water Level - High (2C11-N013 A, B, C, D) 1, 2, 5(h) 2 4 Level - High (2C11-N060 A, B, C, D) 1, 2, 5 2 4

9. Turbine Stop Valve - Closure (NA) 1(i) 4(j) 7

10. Turbine _ Control Valve Fast Closure, 1(i) 2(j) 7 Trip Oil Pressure - Low (2C71-N005 A, B, C, D) u 11. Reactor Mode Switch in Shutdown b Pbsition (NA) 1,2,3,4,5 1 8

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

l TABLE 3.3.1-1 (Continued)

REACTOR PRUTECTION SYSTIN INSTkUMENTATION ACTION 9 - In OPERATIONAL CONDITION 1 or 2, be in at least HUr 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 00RE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

TABLE NUTATIONS

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 magin demonstrations perfonned 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 CONTADMENT INTEGRITY is not required; this function may be bypassed when necessary for containment inerting or de-inerting (purging).

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 $250* psig, equivalent to 1HIRMAL POWER less than 30% of RATED THERMAL POWIR.

j. Also trips reactor coolant system recirculation ptmp motors.

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

HAT W - UNIT 2 3/4 3-5 Amendment No. 8, 29,

l INSTRINENTATION 3/4.3.9 ATHS RECIRCUIATION PLMP TRIP ACIUATION INSTREMENTATION LIMITING CDNDITION FOR OPERATION 3.3.9 The anticipated transient without scram recirculation pump trip (ATWS-RPT) systen instrmentation channels shown in Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint colmn of Table 3.3.9-2.

APPLICABILITY: CDNDITION 1 ACTION

a. With an ATWS recirculation pmp trip systen instrmentation channel trip setpoint less conservative than the value shown in the ALIIMABLE VAwE colmn of Table 3.3.9-2, declare the channel inoperable until the channel

> is restored to OPERABLE status with the channel trip set adjusted consistent with the Trip Setpoint value.

b. With the nmber of OPERABLE channels less than the MINIMLM NLMBER OPERABLE CHANNEM PER TRIP SYSTEM shown in Table 3.3.9-1 for one or both trip systens, place the inoperable channel (s) in the tripped condition within one hour.

c. With the nunber of OPERABLE channels two or more less than required by the MINIMIN NINBER OPERABLE CHANNEG PER TRIP SYSTEM shown in Table 3.3.9-1 for one trip systen and:

1. If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, place both inoperable channels in the tripped condition within one hour, or

2. If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip systen inoperable.

d. With one trip systen inoperable, restore the inoperable trip systen 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 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 />,

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

SURVEILIANCE REQUIREMENTS 4.3.9.1 Each A7WS racirculation puup trip systen instrmentation channel shall be denonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL EUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in TABLE 4.3.9-1.

4.3.9.2 IDGIC SYSTEM FUNCTIONAL TESTS and simulated autmatic operation of all 4 channels shall be performed at least once per 18 months.

HAICH UNIT 2 3/4 3-66

TABLE 3.3.9-1 RECIRCUIATION RMP 'IRIP ACIUATION INSTRLMENTATION APPLICABLE MINIMlM NLNBER OPERABLE OPERABLE CHANNEIS FUNCTIONAL UNIT CONDITIONS PER 'IRIP SYSTEM (a)

1. Reactor stem dme pressure -

(A' INS RPT) high (2B21-N045-A,B,C,D) 1 2

2. Reactor water level (Yarway Narrow Range)

(2B21-N024A,B, and 2B21-N025A,B) 1 2 (a)one 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 provided the other channel is OPERABLE. ,

~

Hatch _ Unit 2 3/4 3-67

_ _ _ . _ . . __ _ __ _ . . _.. = _._ _ _ . __. , _ .-

I TABLE 3.3.9-2

_ RECIRCULATION PLMP TRIP ACIUATION INSTRENENIS SEIPOINIS TRIP ALIOWABLE TRIP EUNCTION SETPOINT VALUE

1. Reactor Stem .61135 psig i 1150 psig Dme Pressure - High i

l 2. Reactor Vessel Water 2.- 38 inches  ?. - 45 inches 1

Level-Iow Low, Ievel 2 i

J i ,

i i

i i'

I i

I

! HA'IOf UNIT 2 3/4 3-68 l'

I L

P v y ,m-c - ,irm.. .wr .p ,

.-n- --, . - - . , ,- . r, --.cw' - -- --

TABLE 4.3.9-1 RECIRCUIATION PLMP TRIP AC'IUATION INS'IRINENTATION SURVEILLANCE RECUIREMENTS i

CHANNEL OPERATIONAL CONDITIONS CHANNEL FUNCTIONAL CHAhWEL IN WHICH SURVEILIANCE FUNCTIONAL UNIT CHECK TEST CALIBRATION REQUIRED

1. Reactor vessel l

steam dme pressure-high NA R R 1

2. Reactor water level (Yarway and narrow range D R R 1 i

HA'ICH UNIT 2 3/4 3-69

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ATTACl+ENT 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 f EIMIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

Remove Page Insert Page 3/4 3-2 3/4 3-2 3/4 3-3 3/43-3 3/4 3-5 3/4 3-5 3/4 3-66 3/4 3-67 3/4 3-68 3/4 3-69 l