ML20126E437

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F023
ML20126E437
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 12/21/1992
From:
GEORGIA POWER CO.
To:
Shared Package
ML20126E428 List:
References
NUDOCS 9212290140
Download: ML20126E437 (9)


Text

_ ___.

Notes for Table 4.2-1 rCont'd)

- -a nr from other BWR's for wNeh the same des +gn instrument operates in en enwronment semder to that of 8-HNP-1. The faduce rete date must be reviewed and approved by the AEC pnor to any chenge in the

25 -

[

once-e-month frequency.

~ -

e.

TNs instrumentetson is exempted from the instrument functional test deferution. TNs instrument functenal test wdt consist of injectmg a simulated e8ectncel segnalinto the enessurement channels.

f.

Standard current source used which prowdes en instrument chonnet slignment. Celebretion usmo e radiation source shau be made once per operating cycle.

4,u Logic system functional tests and sunuteted autometH: ectuaten shed be g, ibm 4 once each operstmg cycle to 4y for the following:

1.

Mam Steam Une isolation Velves 8.

Reector Water Cleanup loolation 2.

Mem Steam Une Drain Velves.

9.

Drywen Isolation Velves 3.

Reactor Water Sempie Velves 10.

TIP Wtthdrawal 4

RHR - Isotation Velve Control 11.

Atmosphenc Control Velves S.

Shutdown Coolmg Valves 12 Sump Dram Verves 6.

Deleted 13.

Standby Gas Treatment l

I

'7.

Drywelt Equipment Sump Discherge to Radweste 14 Reacter Buddmg isoleten

?>

[

The logic system functionet tests shen include a ce16tetson of time delay relays and twners necessary 5

+

h for proper functeorwng of the tnp systems.

is M>C 9212290140.921221 PDR-ADOCK 05000321 P

pg

.1 e

+

L TABLE 3.7-1 (Cont'd)

--4b.

PRIMARY CONTAINMENT ISOLATION VALVES WM4CH f

j.

RECEIVE A PRIMARY CONTAfNMENT ISOLATIOr4 stGNAL t

c-i-

}

2' I

4

.. M -

Isolation Numtw of Power Maximum Normal Action en Group Opers'ed Valvas Operating Postxm trutsetin0 i

Valve klect ficenm (d1 '

teside Outs $e Tie-+e (sed fa)

Sic *st fel

[

l-Ibl "

i

{

6 RHR resetor sh_tdown coohng 1

1 24 C

SC suction (supply) f (E11-FOO8, E11-FOO9)

?

3

).

h 3

HPCI-turNne steem 1

1 50 0

GC (E418002. E41-FOO3) 4 4

~ RCIC-turtune steam-1 1

20 O

GC l'

(ESI-FOO7, E51-FOO8) f 5

Reactor water cleanup from 1

1 30 0

GC

.g

}-

y.

recirculation loop (G31-F001, G31-FOO4)

CD i

2-Post-sceident sampEng system supply 2

S C

SC i

(B21-F111, B21-F112) f l'

2 Post-accident sampEng system return 2

5' C

SC f

i.

(E41-F12.2 E41-F121) t h

2 Core sprey test line to suppression 1 each 57 C

SC I

. pool E"*

(E21-F015A.B.

3 4-L 1

t i

c+

v i

O I

i O

(

~

7 I

ta

. J D

L

/

t 1

,7 -

CD h

.. m J

s.

N.

M i -

CD

.C o

P

=

1

< Tv V

w -v T

  • W-

- " ' *W w

t'-t'7' v-

=1+

i ---

  • r-f w*w v'-+

m*=-:

+- =-'

Table 3.7-3 Testable Penetrations with T1111ble Bellsx1 Penetration Humber Penetration Descriction Malta X-7A Primary Steamline 'A' (1) (2) (4) (6)

X-78 Primary Steamline 'B' (1) (2) (4) (6)

X-7C Primary Steamline 'C' (1) (2) (4) (6)

~~

X-70 Primary Steamline 'D' (1) (2) (4) (6)

X-8 Steamline Condensate Drain (1) (2) (4) (6)

X-9A Feedwater Line 'A' (1) (2) (4) (6)

X-9B Feedwater Line 'B' (1) (2) (4) (6)

X-10 Steam to RCIC Turbine (1) (2) (4) (6)

X-Il Steam Line to HPCI Turbine (1) (2) (4) (6)

X-12 RHRS Shutdown Cooling Suction (1) (2) (4) (6)

X-13A RHR LPCI to Reactor (1) (2) (4) (6)

X-13B RHR LPCI to Reactor (1) (2) (4) (6)

X-14 Reactor Water Cleanup line (1) (2) (4) (6)

X-16A Core Spray to Reactor (1) (2) (4) (6)

X-16B Cure Spray to Reactor (1) (2) (4) (6)

X-17 Spare (1) (2) (4) (6) l X-201A through Drywell Suppression Chamber (1) (2) (4) (6)

X-20lH to Vent Line HATCH - UNIT 1 3.7-22 techsp\\h\\85-22CUl-0

,m me

Table 3.7-4 Primary Containment Testable Isointion Valves 1

Penetration l

Number Yalve Desionation B.1111 X-7A B21-F022A & F028A Main Steam isolation Valves (1) (2) (3)'(5) (9)

X-7B B21-F022B & F0288 Main Steam Isolation Valves (1)(2)(3)(5)(9)

X-7C B21-FG22C & F028C Main Steam Isolation Valves (1)(2)(3)(5)(9)-

X-7D B21-F0220 & F028D Hain Steam Isolation Valves (1) (2) (3) (5) (9)

X-8 B21-F016 & F019 (1) (2) (4) (5) (9) e X-9A B21-F010B (1) (2) (3) (5) (10)

X-9A B21 F032B (1) (2)~(3) (5) (10)

X-9A E41-F006 (1) (2) (4) (5) (9)

X-9A G31-F203 (1) (2) (4) (5) (10)

X-98 B21-F010A (1) (2) (3)-(5) (10)

X-9B B21-F032A (1) (2) (3) (5) (10)

X-98 E51-F013 (1) (2) (4) (5) (9)

X-98 G31-F039 (1)(2)(4)(5)(10)

X-10 E51-F007 F008 (1) (2) (4) (5) (9)

X-Il E41-F002 & F003 (1) (2) (4)-(5) (9)

X-12 Ell-F008 & F009 (1) (2) (4) (5) (9)-

X-13A Ell-F015A (1)(2)(4)'(5)(9)

X-13B Ell-F015B (1) (2) (4) (5)-(9)

X-14 G31-F001 & F004

- (1).(2) (4) (5)~(9).

X-16A E21-F005A (1) (2) (4) (5) (9)

X-160 E21-F005B (1)~(2)=(4) (5) (9) l i

l l

HATCH - UNIT 1 3.7-23

'techsp\\h\\85-22Cul-129 l '.

l'r"*"r9-sy er ar r e y-

.cf

+.

y-w-

p-y q

-,ve,-g1 v-yyep-y y y gg ewg -y n --

~^-w-

~ w

--e'-en--yw=+p n'y*w,**h4-y"y~

y%-amiw>=

=Ev-ipy g

t 4

i i

)

l l

i UnitI

.. j Marked Pages h

l c

~...

il4-E I N" umerae um t '[

'Em E-

'E sp'gy l lg l

~'

l

e Notes for Table is.2-1 (Cont'd) h f rom other BWR's for which the same design instrtement operates in an environment similar to that of" 2

-4 Q

HMP-1 The faillere rate data must be revsewed and approved by the AEC prior to any change in the once-a-month f regteency.

i c

i 2

e.

This instrtementation is exempted f rom the instrtement ftenctional test definition. This instrument

-e functional test will consist of injecting a simulated electrical signal into the measurement channels.

I s

a

{

f.

Standard castrent source tesed which provides an instrument channel alignment.

Ca l i b ra tion tising a I

radiation stwrce sha ll be made once per opr ra ting cycle.

i.

Logic system ftmetional tests and siststated avstomatic activation shall be performed once each operating cycle for the foilowing:

1 Main Steam t.ine Isolation Valves 8.

Reactor Water Cleanttp Isolation 2.

Ma i s. S tea m l_ i ne Dra i n Va l ves 9.

Dryve l l isolation Valves i

3.

Reactor Water Sample Valves 10.

T I P Wi thd rawa l

.rok is. RHR - I so la tion Va lve Cont ro l 1T.

Atmospheric Control Valves em Shtetdown Cooling Valves 12.

Sump Dra in va lves i

atATcD 6.

' -- y 13.

Standby Cas Treatment 7.

Drywell Enttipment Surip Discharge to Radwaste 14 Reactor Building Isolation t

The logic system functional tests shall incitade a calibration of time delay relays and timers necessary for proper ftmetioning of the trip systems.

o b

i i

m 4

--3r-m 1----m J

l l

l 1

TABLE 3.7-1 (Cont'd) g

' N PRIMt.RY CONIA1NMENT ISOLAT8CN VALVES WHICH RECEIVE A PRIMARY CONTAINMENT ISOLATION SICNAL r

B C*

Number of Power Maximum Normal Action on tsolation Ope ra ted Va lves Ope ra ting Position Ini t ia ting M

croup (b)

Valve Identification (di inside Outside T ime ( sec t tai Sioral fal_

-6 RHR reactor shutdown cooling 1

1 2 84 C

SC suction (supp8y) y (E11-FOOS, E11-FOO9)

,g-1 1

20/12 C

SC 6

RHR reactor head spray N'

^

e w

(Eti-ro22 1-F023) 3 HPCI - turbew steam 1

1 50

-O CC (E41-f002, E41-FOO3) 4 RCIC - turbine steam 1

1 20 0

CC (E51-FOO7, E51-FOO8) 5 Reactor water cleanup from 1

1 30 0

GC recirculation Ioop (c31-FOO1, c31-FOOti)

F 2

Post-accident samptIng system supply 2

5 O

SC N

(B21-F111, 821-F112) o>

2 Post-accident sampling system return 2

5

.C SC

([41-F122, F41-F121) l 2

Core spray test line to suppression 1 each 57 C

SC line pool (021-F015A,B)

.{

m i

CL ke

=

i e

2 O.

N G-W

'N N

e

/

( h r

f

?

Table 3.7-3 Testable Tenetrations with Testable Bellows Penetration Number

[enetration Description

' Notes X-1A Primary Steamline 'A' (1) (2) (4) (6) x-1B Primary Steamline 'B' (1) (2) (4) (6)

'g f X-7C Primary Steamline 'C' (1) (2) (4) (6)

T-10 Primary Steamline 'D' (1) (2) (4) (6) b b,'

X-8 Steamline Condensate Drain (1) (2) (4) (6)

(9.Wi g]

X-9A Feedwater Line 'A' (1) (2) (4) (6) x-$3 Feedwater Line 'B' (1) (2) (4) (6) 2 X-10 Steam to RCIC Turbine (1) (2) (4) (6) x-11 Steam Line to !!PCI Turbine (1) (2) (4) (6)

X-12 RMRS Shutdown Cooling Suction (1) (2) (4) (6'

(

x-13A RHR LPCI to Reactor (1) (2) (4) (<

X-133 RM;1 ' PCI to Reactor (1) (2) (4) (6)

,or Water Cleanup Line (1) (2) (4) (6)

X-16A Core Spray to Reactor (1) (2) (4) (6)

X-166 Core Spray to Reactor (1) (2) (4) (6)

X-11

-RP H a Sp ey (1) (2) (4) (6) x-201A through Drywell Suppression Chamber (1) (2) (4) (6)

X !J1H to Vent Line HATCH - UNIT 1 3.7-22

1

l Table 3.7-4 Primary Containment Testable Isolation Valves Penetration Number Valve Designation Notes X-7A B21-F022A & F02BA Main Steam Isolation Valves (1) (2) (3) (5) (9)

X-78 B21-F0228 & F02BB Main Steam Isolation Valves (1) (2) (3) (5) (9)

X-7C B21-F022C & F02BC Main Steam isolation Valves (1) (2) (3) (5) (9)

X-70 B21-F0220 & F028D Main Steam Isolation Valves (1) (2) (3) (5) (9)

X-8 821-F016 & F019 (1) (2) (4)-(5) (9)

X-9A B21-F010B (1) (2) (3) (5) (10)

X-9A B21-F032B (1) (2) (3) (5) (10)

X-9A E41-F006 (1) (2) (4) (5) (9)

X-9A 631-F203 (1) (2) (4) (5) (10)

X-9b B21-F010A (1) (2) (3) (5) (10)

X-98 B21-F032A (1) (2) (3) (5) (10)

X-9B E51 -F013 (1) (2) (4) (5) (9)

X-98 G31-F039 (1) (2) (4) (5) (10) x-10 E51-FOO7, F008 (1) (2) (4) (5) (9)

X-11 E41-F002 & F003 (1) (2) (4) (i) (9)

A-12 E11-F008 & F009 (1) (2) (4) (5) (9)

X-12 A E11-F015 A

' (1) (2) (4) (5)_(9)

X-138 E11-F015B (1) (2) (4) (5) (9)

X -14 G31-F001 & F004 (1) (2) (4) (5) (9)

X-16A E21-F005A (1) (2) (4) (5) (9) l X-16B E21-F005B

('1) (2) (4) (5) (9)

_ [

~

.y-

[ X-17 E11-F022 & F023 (1) (2) (4) (5)(9)[

p/,

~

.~a - #'-

/

w

~.. _..-

HATCH - UNIT 1 3.7-23 Am0ndment No. 51, 129