ML20212J475

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Proposed Tech Specs,Incorporating License Change Application 6 to Implement Design Change to Lower Reactor Vessel Water Level of MSIVs & Steam Line Drain Valves from Level 2 to Level 1
ML20212J475
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 01/21/1987
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20212J427 List:
References
NUDOCS 8701280210
Download: ML20212J475 (5)
v • d • e


Text

m 5

TABLE 3.3.2-1 E

ISOLATION ACTUATION INSTRUMENTATION L.

I-

=

U VALVE CROUPS MINIMUM APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP PUNCTION SIGNAL PER TRIP SYSTEM (a)

CONDITION ACTION 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level 1)

Low Low Low Level 1 1,14 2

1,2,3 20

'l 2)

Low Low Level 2 10,11 (b)(c) 2 1,2,3 22 b.

Drywell Pressure - High 1,11 (b)(c)(d) 2 1,2,3 22 c.

Main Steam Line 1)

Radiation - High 1,10,14 2

1,2,3 21 2)

Pressure - Low 1,14 2

1 23 3)

Flow - High 1,14 2/11ne 1,2,3 21 w

D d.

Main Steam Line Tunnel 4

Temperature - High 1,14 2

1,2,3 21 w

1 1 e.

Main Steam Line Tunnel n

~

Temperature - High 1,14 2

1,2,3 21 y'

f.

Main Steam Line H

i Area Turbine Bldg.

Temperature - High 1,14 2

1,2,3 21 8

J g.

Main Steam Tunnel j

Penetration Area i

Temperature - High 14 1(h)(1) 1, 2, 3 22 h.

Condenser Vacuum - Low 1,14 2

1, 2*, 3*

21 i

1.

Manual Initiation 1

2/ group 1,2,3 24 10,11 1/ group 1, 2, 3 25 14 1/ group 1, 2, 3 26 2.

SECONDARY CONTAlletENT ISOLATION a.

Drywell Pressure - High 9(b)(c)(d) 2 1,2,3 27 b.

Reactor Vessel Water Level - Low Low, Level 2 9(b)(c)(d) 2 1, 2, 3, and i 27 c.

Refueling Floor Exhaust Radiation - High 9(b)(c)(d) 1(i) 1, 2, 3, and **

27 i

d.

Reactor Building Differ-ential Pressure - Low 9(b)(c)(d) 1(i) 1, 2, 3, and **

27 e.

Manual Initiation 9

1/ group 1, 2, 3, and **

27 1

8701280210 B70121 i

PDR ADOCK 05000322-l P

PDR i

o E

TABLE 3.3.2-2 g

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 4

ALLOWABLE

~

TRIP FUNCTION TRIP SETPOINT VALUE 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level 1)

Low Low Low, Level 1

> -132.5 inches *

> -139.5 inches l

2)

Low Low, Level 2 2 -38 inches

  • 1 -45 inches b.

Drywell Pressure - High A 1,69 psig 1 1.89 psig c.

Main Steam Line

~ 1)

Radiation - High 1 3.0 x full power background A 3.6 x full power background 2)

Pressure - Low 1 825 psig 1 805 psig 3)

Flow - High 1 106.0 psid 1 109.0 paid d.

Main Steam Line Tunnel Temperature - High 4 155 F**

4 161 F**

e.

Main Steam Line Tunnel to Temperature - High 4 50 F L 56 F i.

Main Steam Line l

')

Area Turbine Bldg.y y

w H

Temperature - High 4 155 F**

4 161 F**

d w

g.

Main Steam Tunnel t8 Penetration Area Temperature - High

< 175 F**

< 181 F**

h.

Condenser Vacuum - Low 1 8.5 inches Hg vacuum 2 7.6 inches Hg vacuum 1.

Manual Initiation N.A.

N.A.

2.

SECONDARY CONTAINMENT ISOLATION a.

Drywell Pressure - High i 1.69 psig 1 1.89 psig b.

Reactor Vessel Water Level - Low Low, Level 2 1 -38 inches

  • 1 -45 inches c.

Refueling Floor Exhaust Radiation - High 4 35 mR/ht**

4 45.5 mR/hr**

d.

Reactor Building Differ-1 0.30 inch H O 1 0.25 inch H O 2

2 ential Pressure - Low below ATM below ATM e.

Manual Initiation N.A.

N.A.

EXHIBIT C i,

TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#

1.

PRIMARY CONTAINMENT ISOLATION a.-

Reactor Vessel Water Level 11.g*A13(*}**

l

. Low Low Low, Level 1 Low Low, Level 2 L 13 1 13(*)

  • b.

Drywell Pressure - High c.

Main Steam Line

1) Rortistion - High ( }

1 1.0*/ A 13

2) Pressure - Low A 1.0*/ L139)**
3) Flow-High 4 -0.5*/ 4 13 d.

Main Steam Line Tunnel Temperature - High N.A.

e.

Main Steam Line Tunnel Temperature - High N.A.

f.

Main Steam Line Area Turbine Bldg.

Temperature - High N.A.

g.

Main Steam Tunnel Penetration Area N.A.

h.

Condenser Vacuum - Low N.A.

i.

Manual Initiation N.A.

2.

SECONDARY CONTAINMENT ISOLATION a.

Drywell Pressure - High A 13 b.

Reactor Vessel Water Level - Low Low, Level 2 g 13,)

c.

Refueling Floor Exhaust Radiation - High (b)

L 13 d.

Reactor Building Differential Pressure - Low N.A.

e.

Manual Initiation N.A.

3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

Flow - High N.A.

b.

Heat Exchanger / Pump Area Temperature - High N.A.

c.

SLCS Initiation N.A.

d.

Reactor Vessel Water Level - Low Low, Level 2-1 13(*)

7 e.

Main Steam Tunnel Penetration Area Temperature - High N.A.

f.

Manual Initiation N.A.

I 4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

RCIC Steam Line Flow - High i 13 b.

RCIC F*eam Supply Pressure - Low i 13 i

c.

RCIC Turbine Exhaust Diaphragm Pressure - High N.A.

d.

RCIC Equipment Area Temperature - High N.A.

[

e.

RCIC Elevation 63' Area Temperature - High N.A.

l f.

Drywell Pressure - High N.A.

g.

Manual Initiation N.A.

l

.I SHOREHAM - UNIT 1 3/4 3-20 L..

m

~

TABLE 4.3.2.1-1 ISOLATION ACTUATTON INSTRUMENTATION SURVEILLANCE REQUIREMENTS S*

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level 1)

Low Low Low Level 1 S

M R

1, 2, 3 l

2)

Low Low Level 2 S

M R

1, 2, 3 b.

Drywell Pressure - High S

M R

1, 2, 3 c.

Main Steam Line 1)

Radiation - High S

M R

1, 2, 3 2)

Pressure - Low N.A.

M Q

1 3)

Flow - High S

M R

1,2,3 d.

Main Steam Line Tunnel Temperature - High S

M R

1, 2, 3 e.

Main Steam Line Tunnel Temperature - High S

M R

1, 2, 3 m

f.

Main Steam Line 5

Area Turbine Bldg.

y Temperature - High S

M R

1, 2*, 3*

H.

g.

Main Steam Tunnel Penetration Area Temperature - High S

M R

1, 2, 3 0

h.

Condenser Vacuum - Low N.A.

M Q

1, 2*, 3*

i.

Manual Initiation N.A.

R N.A.

1, 2, 3 2.

SECONDARY CONTAINMENT ISOLATION a.

Drywell Pressure - High S

M R

1,2,3 b.

Reactor Vessel Water Level - Low Low, Level 2 S

M R

1, 2, 3 and i c-Refueling Floor Exhaust Radiation - High S

M R

1, 2, 3, and **

d.

Reactor Building Differ-ential Pressure - Low S

M R

1, 2, 3, and **

e.

Manual Initiation N.A.

R N.A.

1, 2, 3, and **

I.'

EXHIBIT E F

e T

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~

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BASES FIGURE B 3/4 3-1 REACTOR VESSEL VATER LEVEL SHOREHAM - UNIT 1 B 3/4 3-8 e

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