ML20199J908

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Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors
ML20199J908
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 01/21/1999
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20199J899 List:
References
NUDOCS 9901260285
Download: ML20199J908 (9)
v • d • e


Text

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Enclosure 3 Edwin I. Hatch Nuclear Plant  !

Revision to a Request to Revise Technical Specifications for an increase in Allowable Value for Reactor Building and Refueling Floor Ventilation Exhaust Radiation Monitors Pane Chanac Instructiom l!!!ill '

P_ ass Instruction i

3.3-55/-56 Replace 3.3-61/-62 Replace Unit 2 P_ase Instruction ,

3.3-57/-58 Replace 3.3-63/-64 Replace

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9901260205 990121 PDR ADOCK 05000321 P PDR _

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HL-5694 E3-1 l l

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l . Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 2 of 4)

Primary Contairmant Isolation Instrtmentation l

APPLICABLE CONDITIONS i NODES OR REQUIRED REFERENCED l

OTHER CHANNELS FROM I SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE i FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE j l

2. Primary Contairment I

Isolation (continued)

c. Drywell 1,2,3 1 F SR 3.3.6.1.1 s 138 R/hr Radiation - High SR 3.3.6.1.2

! SR 3.3.6.1.5 SR 3.3.6.1.6 l d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 s 80 aft /hr l Exhaust SR 3.3.6.1.3 I l Radiation - High SR 3.3.6.1.6

e. Refueling Floor 1,2,3 2 G SR 3.3.6.1.1 s 80 mR/hr l Exhaust SR 3.3.6.1.3 I Radiation - High SR 3.3.6.1.6 l 3. High Pressure Coolant

[

Injection (NPCI) System Isolation

a. HPCI Steam Line 1,2,3 1 F SR 3.3.6.1.1 s 303% rated Flow - High SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6
b. HPCI Steam Supply Line 1,2,3 2 F SR 3.3.6.1.1 t 100 psig Pressure - Low CR 3.3.6.1.2 SR 3.3.6.1.5 i SR 3.3.6.1.6 i 1
c. HPCI Turbine 1,2,3 2 F SR 3.3.6.1.1 s 20 psig Exhaust Diaphragm SR 3.3.6.1.2 Pressure - High SR 3.3.6.1.5 SR 3.3.6.1.6 l
d. Drywell Pressure-High 1,2,3 1 F SR 3.3.6.1.1 s 1.92 psig  ;

SR 3.3.6.1.2 i SR 3.3.6.1.5  !

SR 3.3.6.1.6

e. HPCI Pipe Penetration 1,2,3 1 F SR 3.3.6.1.1 s 169'F Room Temperature-High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 i f. Suppression Pool 1,2,3 1 7 SR 3.3.6.1.1 s 169'F i

Area Ambient SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 (continued)

HATCH UNIT 1 3.3-55 Proposed 98-084

i

. Secendary Containment Isolation Instrumentation 3.3.6.2 l

I Table 3.3.6.2 1 (page 1 of 1) secondary Contalrunent Isolation Instrtsmantation APPLICABLE MODES OR REQUIRED l CHAMELs OTNER sPECIFIED PER SURVEILLANCE ALLOW 4sLE l l FUNCTION COWITIONS TRIP sisTEM REQUIREMENTS VALUE <

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1. Reactor Vessel Water 1,2,3, 2 st 3.3.6.2.1 t 47 inches i Level-Low Low, Level 2 (a) st 3.3.6.2.2 l SR 3.3.6.2.4 SR 3.3.6.2.5
2. DryweLL Pressure-Nish 1,2,3 2 st 3.3.6.2.1 s 1.92 psig l SR 3.3.6.2.2 SR 3.3.6.2,4 at 3.3.6.2.5 l
3. Reactor Building Exhaust 1,2,3, 2 st 3.3.6.2.1 5 80 na/hr l l Radiation - Nigh (a) SR 3.3.6.2.3 i SR 3.3.6.2.5 .
4. Refueling Floor Exhaust 1,2,3, 2 sa 3.3.6.2.1 s 80 sa/tr l Radiation - Nigh 5("I (b) SR 3.3.6.2.3 l st 3.3.6.2.5 I

(a) During operations with a potentist for draining the reactor vesset.

(b) During CORE ALTERATIONS and during movement of irradiated fuel assenbtles in secondary containment. l l

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[ HATCH UNIT 1 3.3-62 Proposed 98-084 l

- . - . - - , . . --. -- - - . - _ . ~ . - - - - - - _ -

l , .

. Prinary Containment Isolation Instrumentaticn 3.3.6.1 Table 3.3.6.1 1 (page 2 of 4) l Primary Contalrusent isolation Instruwntation APPLICABLE CONDITIONS M3Es OR REQUIRED REFERENCED OTHER CHANNELS FROM sPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

2. Primary Contalrusent Isolation (continued)
c. Drywell . 1,2,3 1 F st 3.3.6.1.1 s 138 R/hr Radiat f orMigh st 3.3.6.1.2 st 3.3.6.1.5 st I.3.6.1.6
d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 s to na/hr l Exhaust SR 3.3,6.1.3 i Redietion - HIsh st 3.3.6.1.6
e. Refueling Floor 1,2,3 2 G st 3.3.6.1.1 s 80 am/hr {

Exhaust sa 3.3.6.1.3 i Radiation - Nigh SR 3.3.6.1.6

3. High Pressure Coolant Injection (NPCI) system Isolation
a. NPCI steam Line 1,2,3 1 F SR 3.3.6.1.1 s 303% rated I Flow - Nigh SR 3.3.6.1.2 steam flow  !

SR 3.3.6.1.5 i st 3.3.6.1.6

b. NPCI steen supply Line 1,2,3 2 F SR 3.3.6.1.1 2 100 psig Pressure - Low sa 3.3.6.1.2 st 3.3.6.1.5 st 3.3.6.1.6
c. WPCI Turbine 1,2,3 2 F st 3.3.6.1.1 s 20 psis Exhaust Diaphragm sa 3.3.6.1.2 Pressure - High SR 3.3.6.1.5 st 3.3.6.1.6
d. Drywel1 Pressure-High 1,2,3 1 F st 3.3.6.1.1 s 1.92 psig SR 3.3.6.1.2 l SR 3.3.6.1.5 st 3.3.6.1.6
e. NPCI Pipe Penetration 1,2,3 1 F st 3.3.6.1.1 s 169'F Room Temperature-Nigh SR 3.3.6.1.2 sa 3.3.6.1.5 SR 3.3.6.1.6
f. Suppression Pool 1,2,3 1 F SR 3.3.6.1.1 s 169'F Area Ashlent SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 (continued) 4 HATCH UNIT 2 3.3-57 Proposed 98-084 i

l , . S;cendary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (pase 1 of 1)

Secondary Contairunent Isolation Instrumentation APPLICABLE i MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SfsTEM REQUIREMENTS VALUE I

1. Reactor vessel Water 1,2,3, 2 sa 3.3.6.2.1 t -47 inches I Level- Low Low, Level 2 (a) SR 3.3.6.2.2 '

st 3.3.6.2.4 st 3.3.6.2.5

2. DryweiL Pressure-High 1,2,3 2 SR 3.3.6.2.1 s 1.92 psie sa 3.3.6.2.2 sa 3.3.6.2.4  !

st 3.3.6.2.5 1

3. Reactor Building Exhaust 1,2,3, 2 sa 3.3.6.2.1 s 80 na/hr Radiation - High (a) sR 3.3.6.2.3 i SR 3.3.6.2.5 j
4. Refueling Floor Exhaust 1,2,3, 2 sa 3.3.6.2.1 s 80 mR/hr Radiation - Nigh 5(*)*(b) sa 3.3.6.2.3 l sa 3.3.6.2.5

)

(a) During operations with a potential for draining the reactor vesset.

(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in secondary containment.

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l HATCH UNIT 2 3.3-63 Proposed 98-084

. Pricary Containment Isolation Instrumentatien

. 3.3.6.1 Table 3.3.6.1-1 (page 2 of 4)

Primary contairusent Isolation Instrumentation .

APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FRON SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIRENENTS VALUE

2. Primary Contalrusent Isolation (continued)
c. Drywelt 1,2,3 1 F SR 3.3.6.1.1 5 138 R/hr Radiation - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 So
d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 sjNIaR/hr Exhaust SR 3.3.6.1.3 Radiatten- Nigh SR 3.3.6.1.6
e. Refuellre Floor 1,2,3 2 G SR 3.3.6.1.1 s p sk/hr Exhaust SR 3.3.6.1.3 ,

Radiation- Nigh SR 3.3.6.1.6 1

3. High Pressure Coolant l

Injection (NPCI) System  ;

Isolation I

a. NPCI Steen Line 1,2,3 1 F SR 3.3.6.1.1 s 303% rated l Flow - Nigh SR 3.3.6.1.2 steen flow l SR 3.3.6.1.5 i SR 3.3.6.1.6 \ i
b. NPCI Steam S g ty Line 1,2,3 2 F SR 3.3.6.1.1 2 100 psis Pressure-Low SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 i c. NPCI Turbine 1,2,3 2 F SR 3.3.6.1.1 5 20 pois Exhaust Diaphragm SR 3.3.6.1.2 l Pressure- Nigh SR 3.3.6.1.5 l SR 3.3.6.1.6 i d. Drywett Pressure-High 1,2,3 1 F SR 3.3.6.1.1 s 1.92 psis SR 3.3.6.1.2 SR 3.3.6.1.5 i SR 3.3.6.1.6
e. NPCI Pipe Penetration 1,2,3 1 F SR 3.3.6.1.1 s 169'F Room Temperature-High SR 3.3.6.1.2

, SR 3.3.6.1.5 l

SR 3.3.6.1.6

f. Suppression Poot 1,2,3 1 F SR 3.3.6.1.1 5 169'F Area Ambient SR 3.3.6.1.2 l Temperature - Nigh SR 3.3.6.1.5 l SR 3.3.6.1.6 t

(Continued)

I HATCH UNIT 1 3.3-56 Amendment No. 195

1 Secondary Containment Isolation Instrumentation I

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3.3.6.2 l Table 3.3.6.2 1 (page 1 of 1) l Secondary Containment Isolation Instrumentation APPLICABLE I MODES OR REQUIRED l OTHER CHANNELS SPECIFIED PER SURVE!LLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE l

1. Reactor vessel Water 1,2,3, 2 SR 3.3.6.2.1 t -47 inches Level - Low Low, Level 2 (a) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5
2. Drywell Pressure- High 1,2,3 2 SR 3.3.6.2.1 s 1.92 psig l SR 3.3.6.2.2 SR 3.3.6.2.4 j SR 3.3.6.2.5 gg l
3. Reactor Building Exhaust 1,2,3, 2 SR 3.3.6.2.1 Radiation - High s)#mR/hr (a) SR 3.3.6.2.3 SR 3.3.6.2.5 /0
4. Refueling Floor Exhaust 1,2,3, 2 SR 3.3.6.2.1 Radiation - High Sk 3.3.6.2.3 s[mR/hr

$(a)* (b)

SR 3.3.6.2.5

. _ . - . . _ _ . . _ , . _ . . . _ . _ _ _ _ _ _ . - _ _ _ . , . _ . . _ - _ . . . . . . _ _ _ _ - . - - . - - . - - - - _ _ . . . . _ ~ - - - - - . _ . . .

l (a) During operations with a potentist for draining the reactor vessel.

(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in secondary containment.

O HATCH UNIT 1 3.3-62 Amendment No. 195

l

, Primary Containment Isolation Instrumentation I 3.3.6.1 l l-o .

\ Table 3.3.6.1 1 (page 2 of 4) i k., . Priomry Containment Isolation Instrumentation l

t APPLICApLE CONDITIONS  !

MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM l SP8.CIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWApLE FUNCTION l

CONDITIows . SYSTEM ACTION C.1 REQUIREMENTS VALUE i

2. PhimaryContainment  :

Isolation (continued) -

c. Drywell 1,2,3 1 F st 3.3.6.1.1 s 138 R/hr I

i Radiation-Nish SR 3.3.6.1.2 st 3.3.6.1.5 st 3.3.6.1.6 fg l d. Reactor Building 1,2,3 2 C sa 3.3.6.1.1 Exhaust sfersa/hr l- .

SR 3.3.6.1.3 .

Radiation - Nigh SR 3.3.6.1.6 f

/C l

e. Refuelins Fioor 1,2,3 2 G SR 3.3.6.1.1 5Jg'am/hr  !

Exhaust SR 3.3.6.1.3  ;

Radiation - ulgh SR 3.3.6.1.6 l l .

3. High Pressure Coolant Injection (NPCI) system Isolation l e is . HPCI steam Line 1,2,3 1. F st 3.3.6.1.1 s 303% rated  !

Flow - High SR 3.3.6.1.2 steam flow l (f st 3.3.6.1.5 i

st 3.3.6.1.6 1 i

b. MPCI steam supply Line 1,2,3 2 F st 3.3.6.1.1 R 100 psig 1 Pressure - Low st 3.3.6.1.2 st 3.3.6.1.5 SR 3.3.6.1.6 ]
c. NPCI Turbine 1,2,3 2 F SR 3.3.6.1.1 s 20 psis Exhaust Diaphragm SR 3.3.6.1.2 Pressure - Nigh 54 3.3.6.1.5 i sR 3.3.6.1.6 I
d. Dryweli Pressure-Nigh 1,2,3 1 F st 3.3.6.1.1 5 1.92 psig l- SR 3.3.6.1.2 t

SR 3.3.6.1.5  ;

st 3.3.6.1.6

]

e. HPCI Pipe Penetration 1,2,3 1 F SR 3.3.6.1.1 s 169'F Room Temperature - High st 3.3.6.1.2 st 3.3.6.1.5 SR 3.3.6.1.6
f. s p ession Pool 1,2,3 1 F SR 3.3.6.1.1 s 169'T Aree Anblent SR 3.3.6.1.2 Temperature - High st 3.3.6.1.5 st 3.3.6.1.6 (continued) l l

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l L . HATCH UNIT 2 3.3-57 Amendment No. 135 l- . - .

.- . . . -- . - . . . - . .-.~ .=_ - .- .- ..- - . - - . - -

+'

Secondary Containment Isolation Instrumentation  !

3.3.6.2  !

) Table 3.3.6.21 (page 1 of 1) s Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVE1LLANCE ALLOWABLE l FUNCTION - CONDITIONS TRIP SYSTEM REQUIREMENTS- VALLE j i

i

1. Reactor vesset Water 1,2,3, 2 SR 3.3.6.2.1 t -47 inches Level - Low Low, Level 2 (a) Sr. 3.3.6.2.2 SR 3.3.6.2.4 >

SR 3.3.6.2.5  ;

2. DryweLL Pressure-High 1,2,3 2 SR 3.3.6.2.1 s 1.92 pois i' SR 3.3.6.2.2 SR 3.3.6.2.4 I SR 3.3.6.2.5 70 '
3. Reactor Building Exhaust 1,2,3, 2 SR 3.3.6.2.1 5 p mR/hr Radiation- Mich (a) SR 3.3.6.2.3  ;

SR 3.3.6.2.5  ;

p

4. Refueling Floor Exhaust 1,2,3, 2 SR 3.3.6.2.1 5)9'sR/hr .

Nadiat ion - High

$(a) (b) SR 3.3.6.2.3 SR 3.3.6.2.5 (a) During operations with a potential for draining the reactor vessel. l (b) During CORE ALTERATIONS and during movement of irradiated fuel assaelles in secondary containment.  !

)

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lr HATCH UNIT 2 3.3-63 Amendment No. 135

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