ML20112E968

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Proposed Tech Specs,Revising Tables 3.3.3-1,3.3.3-2 & 4.3.3-1 to Reflect Mods to Automatic Depressurization Sys by Removing High Pressure Trip from Logic Sequence & Adding Manual Inhibit Switch
ML20112E968
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 03/18/1985
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20112E958 List:
References
NUDOCS 8503270283
Download: ML20112E968 (7)
v • d • e


Text

7 ---

ENCLOSURE 1-Proposed Change to Specification 3/4.3.3 Automatic Depressurization Systems (85TSB02) 8503270283 850318 PDR ADOCK 05000325 PDR (1038NLU/ccc )

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PAGE DESCRIPTION OF CHANGE 3/4 3-32 Item 4.a - Delete "Drywell Pressure - High" and Insert

" ADS Inhibit Switch" 3/4 3-33 Action 36 -Insert Action 36 to Table 3.3.3-1 3/4 3-35 Item 4.a - Delete "Drywell Pressure - High" and Insert

" ADS Inhibit Switch" 3/4 3-38a Item 4.a - Delete "Drywell Pressure - High" and Insert

" ADS Inhibit Switch" 3/4 3-38b Insert Footnote (c) "The ADS inhibit switches shall be maintained in the Automatic position."

(1038NLU/ccc)

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TABLE 3.3.3-1 '(Continued) ~

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' EMERGENCY CORE COOLING SYSTEM ACTUATION 1NSTRUMENTATION s:

.APPLICABI.E :

y M1NIHilM NUtlBER'

-OPERABLE CilANNELS.

OPERATIONAL:.

8 PER TRIP SYSTEM CONDITIONS.

' ACTION Q'

TRIP FUNCTION AND' INSTR 11 MENT NUMBER.

LOW' PRESSURE COOLANT INJECTION MODE OF RilR SYSTEM (Continued) 1-1,. 2, 3, 4*,. 5

  • 31 RilR Pump Start - Time Delay Relay e.

(STR-1A1,2 and STR-1B1,2) f.

Bus Power Monitor #

1/ bus 1, 2, ;3, 4*, 5* '

32

( El l-K10 6A, B) 3.

111C11 PRESSURE COOLANT INJECTION SYSTEM y

2 1,

2,-

3

-30 N

. Reactor Vessel Water Level - Low, Level 2 a.

y (B21-LT--NO31 A,B,C,D) g (B21-LTS-NO31A-2,B-2,C-2,D-2) 2 1, 2,- 3 30 b.

Drywel1 Pressure - liigh (El1-PS-N0llA,B,C,D)

(El1-PTS-N01IA-2,B-2,C-2,D-2) 2**

1, 2, 3 33 c.

Condensate Storage' Tank Level - Low (E41-LS-N002, E41-LS-N003) 2**

1, 2, 3 33 d.

Suppression Chamber Water Level - liigh

( E 41-LS!!-N015 A, B) e.

Bus Power Monitor #

1/ bus 1, 2, 3 32.

k (E41-K55 and E41-K56) 8.

g 4.

AUTOMATIC DEPRESSURIZATION SYSTEM

2 1

1,'2, 3

36 a.

ADS Inhibit Switch

. "p (B21-CS-SSA,B) b.

Reactor Vessel Water Level - Low,' Level. 3 2

't,.2, 3

30 (H21-LT-NO31A'B,C,n)

( B21-LTS-NO31 A-3, B--3, C-3,D-3) l.

(BSEP-1-46)

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a.

For one trip system, place at least one inoperable channel in the tripped condition within one hour or declare the associated ECCS inoperable.

b.

For both trip systems, declare the associated ECCS inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare the associated ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the tunimum OPERABLE Channels per Trip System requirement, verify bus power availability at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or declare the associated ECCS inoperable.

ACTION 33 - With the number of OPERABLE channels less than required by the tunimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within one hour or declare the HPCS system inoperable.

ACTION 34 - With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 35 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within I hour; operation may then continue until performance of the next required CilANNEL FUNCTIONAL TEST.

ACTION 36 - With the number of OPERABLE channels less than required by the tunimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ECCS inoperable.

BRUNSWICK - UNIT 1 3/4 3-33 Amendment No.

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( BSEP-1 -4 6)

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e-TABLE 3.3.3-2 (Continued)

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EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRlRIENTATION SETPOINTS

c 0

A1.LOWABLE P:

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE c:

LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Continued)

H e.

RilR Pump Start - Time Delay Relay 9<t< 1I seconds 9<t< 1I seconds

~

(STR-1Al,2 and STR-1B1,2) f.

Bus Power Monitor NA NA

( E l l-K10 6A, B) 3.

IIICil PRESSURE COOLANT INJECTION SYSTEM a.

Reactor Vessel Water Level - Low, Level 2

~> + 112 inches *

--> + 112 inches *

(B21-LTS-NO31A-2,B-2,C-2,D-2) u b.

Drywell Pressure - liigh

< 2 psig

< 2 psig (Ell-PTS-N0llA-2,B-2,C-2,D-2) c.

Condensate Storage Tank Level - Low

> 23 feet 4 inches

> 23 feet 4 inches-(E41-LS-N002; E41-LS-N003) d.

Suppression Chamber Water Level - liigh

< -2 feet **

< -2 f ec t* *

( E 41 -I.Sil-N015 A, B) c.

Bus Power Monitor NA NA (E 41-K55 and E41-K5 6) 4.

AUTOMATIC DEPRESSURIZATION S(STEM a.

ADS Inhibit Switch NA NA y

(B21-CS-S5A,B) h.

b.

Reactor Vessel Water Level - Low, Level 3

> + 2.5 inches *

> + 2.5 inches *

(B21-LTS-NO31A-3,B-3,C-3,D-3) c.

Reactor Vessel Water Level - Low, Level I

> + 1o2.5 inches *

> + 162.5 inches

  • g

( H 21 -LTM-N0 42 A-1, B-1 )

d.

ADS Timor (B21-TDPU-K5A,B)

< 120 seconds

< 120 seconds i

h b

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(!!SEP 4 fi)

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TABLE 4.3.3-I (Continued) w E

M EMERGENCY CORE C00LIAG SYSTEM ACTUATION INSTRlNENTATION SURVEILI.ANCE REQUIRE!!ENTS s:

h CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIllRATION SURVEILLANCE REQUIRED e

d H

4. AUTOMATIC DEPRESSbRIZATION SYSTEM a.

ADS Inhibit Switch D(c)

R NA 1, 2, 3 (B21-CS-S5A,B) b.

Reactor Vessel Water Level -

Low, Level 3 (B21-LT-NO31A,B,C,D)

NA(a)

NA R(b) 1, 2, 3

( il21 -LTS-NO31 A-3, B-3, C-3,D-3)

D M

1, 2, 3 c.

Reactor Vessel Water Level -

Low, Level 1 u

I)

)

( B21-LT-N042 A, B)

NA(^)

NA R

1, 2, 3

( B21 -LT!!-N0 42 A-1, B-1 )

D M

M 1, 2, 3 w

d.

ADS Timer NA R

R 1, 2, 3 S'

(!!21-TDPU-KS A, B) e.

Core Spray Pump Discharge Pressur.3 - liigh NA M

Q 1, 2, 3

( E21-PS--N008A,li and E21-PS -N009 A,II) f.

RilR (LPCI !! ODE) Pump Discharge Pressuria - liigh NA M

Q 1, 2, 3 (Ell-PS -N016A,B,C,D and E l 1 -PS -N0 20 A, B, C, D) g g.

Bus Power Monitor NA R

NA 1, 2, 3 (ll21-KI A,0) 8n

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TABLE 4.3.3-1'(Cont 1nued)

' N M

s EMERGENCY CORE COOLING SYSTEff ACTUATION INSTRUMENTATION ' SURVEILLANCE REQUIREMENTSi w

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W 1

'n i

CllANNEL.

OPERATIONAL l.

"E e

CilANNEL

. FUNCTIONAL' CHANNEL l

' CONDITIONS IN WHICH '.

TRIP FUNCTION AND INSTRUMENT NUMBER:

CHECK.

TEST CALIBRATION.

' SURVEILLANCE REQUIRED H-

~

5.

.LOS4 OF POWER a.

4.16 kv Emergency Bus NA NA R..

1,.2, 3,.4*, 5*

Undervoltage (Loss of'-

Voltaje) b.

4.16 kv Emergency Bus S

M R

1, 2, 3,f4*,.5* -

Undervoltage (Degraded Voltage)

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  • Required when ESF equipment is required to be OPERABLE.

(a) The transmitter channel check is satisfied by:.the trip unit channel check.

A separate transmitter check is not required.

(b) Transmitters are exempted f rom the monthly channel calibration.

(c)

The ADS Inhibit Switches shall be maintained in.the Automatic position.~.

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4.

W" T'
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