Text

Proposed Tech Specs Re Protective Instrumentation
	ML20059M120
Person / Time
Site:	Hatch
Issue date:	09/21/1990
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20059M119	List: HL-1122, Application for Amends to Licenses DPR-57 & NPF-5,changing Tech Specs Re Protective Instrumentation; ML20059M120; ML20059M123;
References
	NUDOCS 9010030168
	Download: ML20059M120 (6)
	v • d • e

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1 Table 3.1-1 (Cont'd) z 2$ Stram

. Scram Trip Signal Channels Scram Trip setting Source of Scram Signal is Operable r4 Number Source of (a)

Required Per Required to be Operable C

Trip System

.Except as Indicated Below e

ibl 12 Turbine Stop Valve 4

110% valve closure Automatically bypassed when hjC[:]

Closure from full open turbine steam flow is below c;

Tech Spec 2.1.A.3.

that corresponding to 301 of C) *"

rated thermal power as 2> 6) measured by turbine first

[j[3 stage pressure.

cy g, 7A)

Notes for Table 3.1-1 ON)

$$h[

The column entitled " Scram Number" is for convenience 50 that a one-to-one relationship (en be established a.

C)w) between items in Table 3.1-1 and items in Table 4.1-1.

"U O h) b.

Ihere shall be teo operable or tripped trip systems f or each potential scram signal._ 18 the number of ffkj"'

operable channels cannot be met f or one of the trip systems, the inoperable channel (s) or the associated l

trip system shall be tripped. tiowever,one trip signal channel of a trip system may be inoperable for up to l

t o (2) hours during periods of required surveillance testing without tripping the channel or associated trip system, provided that the other remaining channel (s) monitoring that parameter within that trip system is (are) operable.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test with the reactor power at greater than-c.

ya 20% rated power. the normal full power radiation background level and associated trip setpoints -

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 Ch 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation levels'after completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

o "1

OcO tn CD Q.

H tn

%s C3 LJ

'J O

O N

c4 N

i w

N (D

6 9

o

s 9

Table 3.2-1 (Cent.)

Oc Required 3$ Res.

Trip Operable Action to be taken if c3 ho.

Instrument Condition Channels Trip Setting number of channels is CC (a)

Nomenclature per Trip

-not met for both trip Remarks (d)

System (b) systems (cl s

c-

-z

-4 4

Hain Steam Line High 2

13 times normal Initiate an orderly load Initiates Group I Radiation full power back-reduction and close HSIVs. isolation.

9round'**

within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

5 Main Steam Line Low 2

1825 psig Initiate an orderly lo.d initiates Group 1-Pressure reduction and close isolation. Only MSIVs within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

_ required in RUN mode, therefore' activated when Mode Switch is in

.RUN position.

b

sin Steam Line High 2

1138% rated flow

_ Initiate an orderly luad Initiates Group I flow (15 psid) reduction and close MSIvs-isolation.

within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

7 Main Steam line High 2

il94*F Initiate an orderly load-Initiates Group i Tunnel Temperature reduction anj close NSIVs isolation.

within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

l 8

Reactor Water High 1

20-80 gpm Isolate reactor water (t) to Cleanup System cleanup system.

S3 Differential Flow w

9 Reactor Water High 2

IIS0*f Isolate reactor water Cleanup Area cleanup system.

Temperature o

3 10 Reactor Water High 2

167'r Isolate-reactor water t3 Cleanup Area cleanup system.

O Ventilation m

Differential t

C' Temperature

--4 12 11 Conaenser vacuum tow 2

i7-Hg. vacuum Initiate an orderly load Initiate Group 1 c3 reduction and close HSIVs Isolation within 8 hrs.

C3 El 12 Drywell Radiation High I

1138 R/HR.-

Close the affected

-tsolates ha isolation valves within

. containment purge Ed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in Hot.

and went valves.

Shutdown within the 3"

next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in Cold Shutdown within

~

the next~30 hours.

b

.y

- ~.,,

.-n.

.y s-.

y

~

y; Notes for able 3.2-1 r

-4 lhe column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established (7

4.

UC between lines in Table 3.2-1 and items in lable 4.2-1.

a b.

Primary containment integrity shall be maintained at all times prior to withdrawing control rods for the c:

==

purpose of going critical, when the reactor is critical, or when the reactor water temperature is above 212*F and fuel is in the reactor vessel except while performing low-power physics tests at atmospheric pressure at power levels not to exceed 5 MWt. or performing an inservice vessel hydrostatic or leakage test.

When primary containment integrity is required, there shall be two operable or tripped trip systems for each function.

When performing inservice hydrostatic or leakage testing oa the reactor vessel with the reactor coolant temperature above 212*f. reactor vessel water level instrumentation associated with the low low (Level 2) trip requires two operable or tri.pped channels. The drywell pressure trip is not required because primary containment integrity is not required.

c.

li the nusiber of operable (hannels cannot be met f or one of the trip systems, the inoperable channel (s) or the associated trip system shall be tripped. However, one trip signal channel of a trip system may be inoperable f or up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during periods of required surveillance testing wiU + t tripping the channel or associated trip system, provided that the other remaining channel (s) mon " ring that same.

g parameter within that trip system is (are) operable.

d.

The valves associated with each Group isolation'ere given in Table 3.1-1.

n

$d e.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test with the reactor power no at greater than 20t rated power, the normal full-power radiation background level and associated j,

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ' of re-establishing normal radiation levels af ter completion

' 2f of hydrogen injection and prior to establishing reactor power levels below 20% rated po-er.

O

' {j f.

1he high 'dif f erential flow signal to.the RWCU isolatic valves may be bypassed for. up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months l.

during periods of system restoration or' testing.

=

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IABtf 3.3.2-l_(Continued 1

~

-L.,

i 150t ATION ACTUATION INSTRUMEHlal[Qtfit I.

APPtICABLE n

'I i/ALVE GROUPS

' MINIMUM nut 1Bf R OPERATED BY

-OPERABLE CHANNELS" OPERATIONAL ~

_SifM_Li4L EL4_1812._1Y11LHth)1t1

- likelllDN...

6(110H 181t_ites1108

,z

~ q 2.

_ SECONDARY CONIAIDHLtD$Dift[10H N

a.

Reactor Building Enhaust Radiation'- High.

6. 10, 12. -

7

'1.2.3.5'end--

24 (20t!-K609'A. B, C. D)-

b.

Drywell Pressure - High 2, 6, 7. 10 2-1, d 3

24 (2C71-N650 A; 8. C. D)

12. *

~

Neact' or Vessel Water

5. *

. 2 --

1, 2,.s '

~ 24 -

c.

level - tow tow.(tevel 2)'

(282l-N682'A, R.-C. D) d.

Refueling floor Enhaust Radlation - High-6, 10, 12. -

2 :.

l.2.3.5.*d**M24

'(2D11-K611 A, B, C. D) 5.

REACTOR WA1IR CtfAra#P syS11tLISQLallgg^

-w a.

3 Flow - High (2G3I-N603 A, B) 5..

1 I,' l 2, 3 '

' 25(1)'

N-

. 1, 2 73

25'

-V 5...

1.1

~. gs b.

Area'Temperatt,re - Hiijh'.

(2G31-N662'A, D' E. H. J, H)..-

c.

Area Ventilation a Temp..- High 5-

'l i

~ rl, 2, 3 o 25 -

(2631-N663 A' D, C.~ H Ji: M:

2G31-N661 A D, E. H J. H:.

2G31-N662-A, D,1E,.H,yJf H) _

j

-d.

SLCS Initiation'(NA)~

15'"*-

NA

1. 2, 3,

3 257 s

.21

. l. 2. 3 x (25-o 5.~*:

V'

,e.

Reactor vessel Water Level -' Low l Low 1

1(level 2)'.(2821-N682 A B,-C,'D).=

-4

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ow.

o

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.g.

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1 -~u i 4 V 222 -

c, TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATIOS ACTION t

ACTION-20 Be in at least HOT SHUTDOWN'within'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

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

ACTION 23 Be in at least STARTUP with the Group 1 isolation valves closed 1

-within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or in at least HOT SHUTOOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

]

ACTION 24 Establish SECONDARY CONTAINMENT ~ INTEGRITY with the standby I

gas treatment system operating within one hour.

4 ACTION 25 Isolate the reactor water cleanup system.

l 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 I 145 psig.

ACTION 29 - Either close the affected isolation valves within' 24 ho'urs or be in HOT SHUTOOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00HN-within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

NOTES Actuates the_ standby gas treatment system.

When handling irradiated fuel in the secondary containment.

When performing inservice hydrostatic or leak testing with the reactor coolant temperature above 212* F.

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

I

\\

HATCH - UNIT 2 3/4 3-15 Proposed TS/0378q/232-91 l

a

' c.

With a~ design'providing only one channel per trip system, an inoperable ~

i channel need-not be placed in the tripped condition where-this would cause the Trip Function to occur.

In'these cases, the inoperable channel shal}

.i

^be restored to 0PERABLE status within 2= hours 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 Lypassed with all turbine stop valves closed.

g.

Closes on'y RWCU outlet isolation valve 2G31-F004.

h.

Alarm oniy.

1.

Adjustable up to 60 minutes.

j.

Isolates containment purge and vent valves.

k.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 levei 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation. levels after.

l completion of hydrogen injection'and prior to establishing reactor power levels below 20% rated power.

1 1.

The high differential flow isolation signal to.ne RWCU isolation valves may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during periods of system restoration,.

maintenance, or testing.

t HATCH - UNIT 2 3/4 3-15a Proposed TS/0378q/12-91

ML20059M120

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