Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust MonitorsML20236U255 |
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Site: |
Hatch ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
07/22/1998 |
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From: |
SOUTHERN NUCLEAR OPERATING CO. |
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To: |
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Shared Package |
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ML20236U252 |
List: |
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References |
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NUDOCS 9807290412 |
Download: ML20236U255 (9) |
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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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[Table view] |
Text
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Enclosure 3 Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:
Increase in Allowable Value for Reactor Building and Refueling Floor Ventilation Exhaust Radiation Monitors Page Change Instructions
.U.KIL.1 PAst Instruction 3.3-55/-56 Replace 3.3-61/-62 Replace
.V. Rill East Instruction 3.3-57/-58 Replace 3.3-63/-64 Replace I
i HL-5658 E3-1 L- -- - - - . -
l
Pricary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 2 of 4)
- Primary Containment Isolation Instrumentation APPLICASLE COND1T10Ns MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE l FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUlaEMEhis VALUE
]
- 2. Primary Containment Isotation (continued)
- c. Drywet! 1,2,3 1 F SR 3.3.6.1.1 s 138 t/hr Radiation Nigh SR 3.3.6.1.2 sa 3.3.6.1.5 SR 3.3.6.t.6
- d. Reactor Building 1,2,3 2 G sa 3.3.6.1.1 s 100 aft /hr l !
Exhaust sa 3.3.6.1.3 I tediation - High {
sa 3.3.6.1.6
- e. F.efueling Floor 1,2,3 2 G sa 3.3.6.1.1 s 100 ma/hr l EFh&Jt sa 3.3.6.1.3 I andt ation - Nigh sa 3.3.6.1.6 {
1
- 3. High Pressure Coolant i Injection (NPCI) system j lsolation
- a. MPCI steam Line 1,2,3 1 F sa 3.3.6.1.1 s 303% rated Flow - Mich sa 3.3.6.1.2 steam flow SR 3.3.6.1.5 )
54 3.3.6.1.6
- b. NPCI steam s p ly Line 1,2,3 2 F Sa 3.3.6.1.1 t 100 psig Pressure - Low sa 3.3.6.1.2 sa 3.3.6.1.5 sa 3.3.6.1.6
- c. MPCI Turbine 1,2,.3 2 F sa 3.3.6.1.1 s 20 pelg Exhaust Diaphragm sa 3.3.6.1.2 Pressure - Migh sa 3.3.6.1.5 54 3.3.6.1.6
- d. Drywell Pressure-High 1,2,3 1 F sa 3.3.6.1.1 s 1.92 psig sa 3.3.6.1.2 sa 3.3.6.1.5 s# 3.3.6.1.6
- e. NPCI Pipe Penetration 1,2,3 1 F sa 3.3.6.1.1 5 169'F j aoom Temperature-High sa 3.3.6.1.2 -
SR 3.3.6.1.5 ,
SN 3.3.6.1.6
- f. Suppression Poot 1,2,3 1 F sa 3.3.6.1.1 5 169'F Area Anblent sa 3.3.6.1.2 Temperature - HIsh SR 3.3.6.1.5 sa 3.3.6.1.6 (continued) l l
l HATCH UNIT 1 3.3-56 Proposed 98-084
! l E-_-------_------_
Secendary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1) secondary Containment Isolation Instrumentation
! APPLICABLE r
MEDEs OR REQUIRED l OTNER CHANNELS l SPECIFIED PER SURVEILLANCE ALLOWASLE l FUNCTION CONDITIONS TRIP SYSTEM REGUIREf1ENTs VALUE
- 1. Reactor vessel Water 1,2,3, 2 st 3.3.6.2.1 t -47 inches l
L*v't -Low Low, Level 2 (a) sa 3.3.6.2.2 t
st 3.3.6.2.4 I sa 3.3.6.2.5 i
- 2. Drywel1 Pressure-Nish 1,2,3 2 sa 3.3.6.2.1 s 1.92 pois SR 3.3.6.2.2 sa 3.3.6.2.4 sa 3.3.6.2.5
- 3. Reactor sullding Enhaust 1,2,3, 2 sa 3.3.6.2.1 s 100 mm/hr l Radiation - Mish (a) st 3.3.6.2.3 I st 3.3.6.2.5
- 4. Refueling Floor Exhaust 1,2,3, 2 st 3.3.6.2.1 5 100 mm/hr l l Radiat f an - Nish $(s)* g3 st 3.3.6.2.3 I l
l sa 3.3.6.2.5 l
l (a) During operations with a potential for draining the reactor vesset.
(b) During CORE ALTERATIONS and during movement of irradiated fuel assembtles in secondary contalrunent.
I l
l l
1 l
HATCH UNIT 1 3.3-62 Proposed 98-084
l l
l Pricary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 4)
Primary Containment Isolation Instrumentation l -
APPLICABLE CONDIT10NS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE
- 2. Primary Contelnment Isolation (continued)
- c. Dryweti 1,2,3 1 F SR 3.3.6.1.1 5 138 R/hr Radlettordish SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 5100 aft /hr l Exhaust SR 3.3.6.1.3 I Radiatlon - Nigh SR 3.3.6.1.6
- e. Refueling Floor 1,2,3 2 G SR 3.3.6.1.1 5100 aft /hr l Exhaust SR 3.3.6.1.3 i Radiation - Nlgh 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 5 303% rated F1ow - Nish SR 3.3.6.1.2 steam f(ow
, SR 3.3.6.1.5 l SR 3.3.6.1.6
- b. HPCI Steam Supply Line 1,2,3 2 F SR 3.3.6.1.1 t 100 pois Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- c. MPCI Turbine 1,2,3 2 F SR 3.3.6.1.1 5 20 psig Exhaust Diaphragm SR 3.3.6.1.2 Pressure - Nigh SR 3.3.6.1.5 SR 3.3.6.1.6
- d. Dr;Mit Pressure - High 1,2,3 1 F SR 3.3.6.1.1 5 1.92 pois SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- e. NPCI Plpe Penetratim 1,2,3 1 F SR 3.3.6.1.1 5 169'F Room Temperature-Nigh SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- f. S w ession Poot 1,2,3 1 F SR 3.3.6.1.1 5 169'F Area Ashlent SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 (continued)
HATCH UNIT 2 3.3-57 Proposed 98-084 l
Secondary Containment Isolatien Instrumentation 3.3.6.2 I
(
Table 3.3.6.2 1 (page 1 of 1) secondary Contairument Isolation Instrumentation j
APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWASLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE
- 1. Reactor Vessel Water 1,2,3, 2 SA 3.3.6.2.1 2 47 inches Level -Low Low, Level 2 (a) sa 3.3.6.2.2 st 3.3.6.2.4 sa 3.3.6.2.5
- 2. Drywet t Pressure - Nigh 1,2,3 2 sa 3.3.6.2.1 s 1.92 psig sa 3.3.6.2.2 sa 3.3.6.2.4 sa 3.3.6.2.5
- 3. Reactor Building Exhaust 1,2,3, 2 SR 3.3.6.2.1 s 100 adt/hr l Radiation - Nigh (a) st 3.3.6.2.3 1 3R 3.3.6.2.5
- 4. Refueling Floor Exhaust 1,2,3, 2 SR 3.3.6.2.1 s 100 aft /hr Radiation - Nigh sa 3.3.6.2.3 5(a) (b) '
sa 3.3.6.2.5 (a) During operations with a potential for draining the reactor vessel.
(b) During CORE ALTERATIONS and during movement of 1. radiated fuel assembtles in secondary contaltunent.
HATCH UNIT 2 3.3-63 Proposed 98-084
Primary Containment Isolation Instrumentation 3.3.6.1
, , Table 3.3.6.1-1 (pege 2 of 4)
Primary Centelrunent Isolation Instrumentation 1
APPLICABLE CONDIT!0Ns 4
MODES OR REQUIRED REFERENCED OTNER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE FUNCTION. CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE i
- 2. Primary Centaltunent j Isetation (continued) '
- c. DryueLL 1,2,3 1 F st 3.3.6.1.1 s 138 R/hr Radletten - Nigh SR 3.3.6.1.2 SR 3.3.6.1.5 st 3.3.6.1.6 loo
- d. Reactor Sullding 1,2,3 2 G st 3.3.6.1.1 5 M eR/hr Exhaust st 3.3.6.1.3 Radiation- Nish SR 3.3.6.1.6 ,,,
- e. Refuelleg Floor 1,2,3 2 c st 3.3.6.1.1 s M mR/hr Exhaust sa 3.3.6.1.3 Radiatten- Nigh SR 3.3.6.1.6
- 3. Nish Pressure Coolant Injection (NPCI) system ,
Isoletten
- a. NPCI steen Line 1,2,3 1 F st 3.3.6.1.1 s 303% rated Fleu - Nish sa 3.3.6.1.2 steem flou st 3.3.6.1.5 SR 3.3.4.1.6
- b. NPCI steen s g ply Line 1,2,3 2 F st 3.3.6.1.1 2 100 psig Pressure - Lou SR 3.3.6.1.2 st 3.3.6.1.5 st 3.3.6.1.6
- c. NPCI Turbine 1,2,3 2 F st 3.3.6.1.1 s 20 psis Exhaust Diaphrope SR 3.3.6.1.2 Pressure - NIsh SR 3.3.6.1.5 st 3 J.6.1.6
- d. Dryue11 Pressure-Nish 1,2,3 1 F SR 3.3.6.1.1 5 1.92 psie st 3.3.6.1.2 st 3.3.6.1.5 SR 3.3.6.1.6
- e. NPCI Pipe Penetration 1,2,3 1 F st 3.3.6.1.1 5 169'F Room Temperature-Nigh st 3.3.6.1.2 st 3.3.6.1.5 st 3.3.6.1.6
- f. sgpression Poot 1,2,3 1 F sR 3.3.6.1.1 5 169'F Area Ambient st 3.3.6.1.2 !
Temperature - Nigh st 3.3.6.1.! l st 3.3.6.1.6 (continued)
I s
l HATCH UNIT 1 3.3-56 Amendment No. 195
l i
i Secondary Containment Isolation Instrumentation '
3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)
Secondary Contairunent Isolation Instrumentation
- APPLICABLE I
MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE l 1. Reactor vessel Water 1,2,3, 2 SR 3.3.6.2.1 R -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 i 2. Drywell Pressure-Nigh 1,2,3 2 SR 3.3.6.2.1 s 1.92 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 ,,
- 3. Reactor Building Exhaust 1,2,3, 2 SR 3.3.6.2.1 5 15 adt/hr Radiation - Nigh (a) SR 3.3.6.2.3 SR 3.3.6.2.5 eco
- 4. Refueling Floor Exhaust 1,2,3, 2 SR 3.3.6.2.1 5 M aft /hr l Radiation - High SR 3*3'0 2 3
$(a) (b)
SR 3.3.6.2.5 l
(a) During operations with a potential for draining the reactor vessel.
(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in secondary containment.
l j
i l
I l l
!1 i
HATCH UNIT 1 3.3-62 Amendment No. 195 i
~
, Primary Containment Isolation Instrumentation 3.3.6.1 i
. , Table 3.3.6.1 1 (page 2 of 4)
Primary Contalrunent Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM sPECIFIED PER TRIP REQUIRED suRVE!LLANCE ALLOWASLE FUNCTION CONDIYIONs SYSTEM ACTION C.1 REQUIREMENTS VALUE 1
- 2. Primary Containment asotation (continued)
- c. Drywelt 1,2,3 1 F sR 3.3.6.1.1 5 138 R/hr Radiation-Nigh sR 3.3.6.1.2 SR 3.3.6.1.5 st 3.3.6.1.6 geo
- d. Reactor Building 1,2,3 SR 3.3.6.1.1 Exhaust 2 C sgue/hr SR 3.3.6.1.3 Radiat ton - High SR 3.3.6.1.6 100
- 4. 9ehntIng floor 1,2,3 2 G SR 3.3.6.1.1 sgmR/hr Exhaust st 3.3.6.1.3 Radiation - High SR 3.3.6.1.6
- 3. High Pressure Coolant Injection (HPCI) system Isolation
- a. MPCI 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 st 3.3.6.1.5
- b. HPCI steam supply Line st 3.3.6.1.6 ,
gQ 1,2,3 2 F st 3.3.6.1.1 t 100 psig /
Pressure - Low st 3.3.6.1.2 -
sa 3.3.6.1.5 I SR 3.3.6.1.6 1
- c. NPCI Turbine 1,2,3 2 F sa 3.3.6.1.1 s 20 psig Exhaust Diaphragm SR 3.3.6.1.2 Pressure - High . st 3.3.6.1.5 SR 3.3.6.1.6
- d. Drywell Pressure-High 1,2,3 1 F sa 3.3.6.1.1 s 1.92 psig sa 3.3.6.1.2 st 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 5 169'F Room Temperature-High sR 3.3.6.1.2 3R 3.3.6.1.5 SR 3.3.6.1.6
- f. sta pression Poot 1,2,3 1 F st 3.3.6.1.1 s 169'F Area Ambient st 3.3.6.1.2 Temperature - HIsh st 3.3.6.1.5 SR 3.3.6.1.6 l i
(continued)
HATCH UNIT 2 3.3-57 Amendment No. 135
^ Secondary Containment Isolation Instrumentation ?"b 3.3.6.2 -
g ,
Table 3.3.6.21 (page 1 of 1) secondary Containment Isolation Instrumentation - aw i
(
APPLICA8LE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER suRVE!LLANCE ALLOWASLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE
- 1. Reactor Vessel Water 1,2,3, 2 st 3.3.6.2.1 . R 47 inches Level -Low Low, Level 2 ' (a) st 3.3.6.2.2 -
st 3.3.6.2.4 st 3.3.6.2.5
- 2. Drywel1 Pressure-Nigh 1,2,3 2 st 3.3.6.2.1 s 1.92 pelg ,
st 3.3.6.2.2 SR 3.3.6.2.4 -
e.s . a .
st 3.3.6.2.5
- 3. Reactor Building Exhaust 1,2,3, 2 st 3.3.6.2.1
,.,..n
. .a Radiation- Migh (a) st 3.3.6.2.3 s)(mR/hr -
SR 3.3.6.2.5 dw
- 4. Refueling Floor Exhaust 1,2,3, 2 st 3.3.6.2.1 Radiation - High s y aft /hr
.3.6.2.3
$(a)* (b) st ,,
SR 3.3.6.2.5 (a) During operations with a potential for draining the reactor vessel.
(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in secondary containment, w,. 3-9(
% - ;.n,, , ;.p _. ..w. -
..,g., m
' %4pp,yglh
- m. #
' .' . ;; ef ^f. 4 1
I 1
l I
I HATCH UNIT 2 3.3-63 Amendment No. 135