ML20091R191

Proposed Tech Specs,Incorporating New Instrumentation Trip Setpoints & Allowable Values

ML20091R191
Person / Time
Site:	Perry
Issue date:	08/29/1995
From:	CENTERIOR ENERGY
To:
Shared Package
ML20091R178	List: ML20091R191 PY-CEI-NRR-1969, Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)
References
NUDOCS 9509060254
Download: ML20091R191 (11)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. - _ _ ---__._- -___-__ _ _ _----- _ _

Nig TABLE 3.3.2-2 E

Fo ISOLATION ACTUA110N INSTRUMENTATION SETPOINTS 4-o ALLOWABLE x.}

TRIP FUNCTION..

TRIP SETPOINT VALUE 1.

PRIMARY CONTAINMENT ISOLATION

! o i Og a.

Reactor Vessel Water Level -

g=

!ib 'i Low, Level 2

> 129.8 inches *

> 127.6 inches o*4 H Te

'o b.

Drywell Pressure - High 1 1.68 psig 1 1.88 psig c.

Containment and Drywell Purge Exhaust Plenim Radiation - High 1 2 mR/hr above background-1 4 mR/hr above background d.

Reactor Vessel Water Level -

Low, Level 1

> 16.5 inches *

> 14.3 inches e.

Manual Initiation NA NA 2

MAIN STEAM LINE ISOLATION Y

a.

Reactor Vessel Water Level -

G Low, Level 1

> 16.5 inches *

> 14.3 inches b.

Main Steam Line Radiation - High 1 3.0 x full power background

< 3.6 x full power background c.

Main Steam Line Pressure - Low

> 807.0 psig

>7 psig

~M S. 7.

~

d.

Main Steam Line Flow - High 1 183 psid 1 4H-e.

Condenser Vacuum - Low

> 8.5 inches Hg. vacuum

> 7.6 inches Hg. vacuum f.

Main Steam Line Tunnel Temperature - High

~< 154.4 F

~< 158.9*F l

??3 5

g.

Main Steam Line Tunnel

%Gh

(

a Temperature - High 1 103.6*F i 107.4*F

~gy oeg h.

Turbine Building Main Steam Line "EE O

Temperature - High

< 134.4*F

< 138.9'F 5 w 1.

e i.

Manual Initiation NA NA

g TAB I3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS-l c

ALLOWABLE j

TRIP FUNCTION.

TRIP SETPOINT VALUE

~

A.

DIVISION 1 TRIP SYSTEM 1.

RHR-A (LPCI MODE) AND LPCS SYSTEM f

a.

Reactor Vessel Water Level - Low, Level 1 1 16.5 inches

• 1 14.3 inches b.

Drywell Pressure - High 1 1.68 psig i 1.88 psig c.

LPCS Pump Discharge Flow - Low (Bypass) 2 1350 gpm 2 1200 gpm d.

Reactor Vessel Pressure - Low-(LPCS Injection 577.7 1 15 psig 577.7 + 30, -95 psig Valve Permissive)

" si

'^^ 5 n '"-_--'^-

ig e.

Reactor Vessel Pressure - Low (LPCI Injectio 2 ^J " ; "

Valve Permissive)

/, 627.18 and

• S 31. 02.

B 448 c_ y_J _5 ? n. l i

.2 seconds f.

LPCI Pump A Start Time Delay Relay i 5 sewnJ5 g.

LPCI Pump A Discharge Flow - Low (Bypass) 1 1650 gpa 1 1450 gpm h.

Manual Initiation NA NA 2.

AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A"

[

a.

Reactor Vessel Water Level - Low, 1 16.5 inches *-

> 14.3 inche_s_

to Level 1

,,,,,,g {} g joq,g b.

Manual Inhibit NA NA

=_

c.

ADS Timer

< 105 seconds

< t W seconds d.

Reactor Vessel Water Level - Low, Level 3

[177.7 inches *

[177.1 inches (Permissive) 1 e.

LPCS Pump Discharge Pressure - High 1 145 psig, increasing 1 125 psig, increasing (Permissive) f.

LPCI Pump A Discharge Pressure - High 1 125 psig, increasing 1 115 psig, increasing (Permissive) g.

Manual Initiation NA NA 99

%aa

~ 9-N O

s~c*

)

TABLE 3.3.3-2 (Continued)

[

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS x

ALLOWABLE TRIP SETPOINT VALUE TRIP FUNCTION E

Z B.

DIVISION 2 TRIP SYSTEM 1.

RHR B AND C (LPCI MODE) a.

Reactor Vessel Water Level - Low,

> 16.5 inches *

> 14.3 inches Level I b.

Drywell Pressure - High 5 1.68 psia

< 1.88 psiQ

' S ll * ' E

• M a

er s ive LPCI Pump B 508.0

• 5, -10 psig 500.0 10, 40 psig l

LPCI Pump C 505.5 5, -10 psig

• 500.0 10, 40 psig j

d.

LPCI Pump B Start Time Delay Relay 5 5 seconds 1.5.25 seconds LPCI Pump Discharge Flow - Low (Bypass)

> 1650 gpm

> 1450 gpm e.

f.

Manual Initiation NA NA

,p Y

2.

AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "B" U

a.

Reactor Vessel Water Level - Low,

-> 16.5 inches *

> 14.3 inches

~

~

Level 1 b.

Manual Inhibit NA NA.

_" 5- _"d I*

c.

ADS Timer

< 105 seconds

< +1+ seconds d.

Reactor Vessel Water Level - Low, Level 3

[177.7 inches *

[177.1 inches (Permissive) e.

LPCI Pump B and C Discharge Pressure - High

> 125 psig, increasing

> 115 psig, increasing (Permissive) j f.

Manual Initiation NA NA 1

E' % 3

%gA we5

"' E 3 O

sa*

8

}

TABLE 3.3.9-2 PLANT SYSTEMS ACTUATION INSTRUMENTATION SETPOINTS 7

ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE c_

'5

]

1.

CONTAINMENT SPRAY SYSTEM a.

Drywell Pressure.- High

< 1.68 psig

<-1.88 psia b.

Containment Pressure - High 7 8.35 psig 7 0.C57sig 8M d.

Timers 5 14.3 inches c.

Reactor Vessel Water Level-- Low,, Level 1 7 16.5 inches *

(1) System A and B 10.85 0.3 minutes 10.85 1 0.6 minutes (2) System B 35 1 2 seconds 35 i 3 seconds e.

Manual Initiation NA NA 2.

FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM g

a.

Reactor Vessel Water Level - Piot., Level 8

< 219.5 inches *

< 220.1 inches Y

3.

SUPPRESSION POOL MAKEUP SYSTEM M

a.

Drywell Pressure - High

< 1.68 psig

< 1.88 psig

~

b.

Reactor Vessel Water Level - Low, Level 1 5 16.5 inches

• i 14.3 inches c.

Suppression Pool Water Level - Low i 591' 6.9" elevation i 591' 5.64" elevation d.

Suppression Pool Makup Timer 7 29.4 minutes

.7 30.0 minutes i

e.

SPMU Manual Initiation NA RA "See Bases Figure B 3/4 3-1.

I i

l l

ENA 2ga

>SD O

i

" G, o

i f.

l 1

i.

= -

r PY-CEI/NRR-1969L Attcchment 2 ECCS Instrumentation Page 5 of 10 3.3.5.1 Tabte 3.3.5.1-1'(page 1 of 5)

Emergency Core Cooling system Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED l

OTHER REQUIRED F#0M SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE

• ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 1.

Loi Pressure Coolant injection-A (LPCI) and Low Pressure Core spray (LPCS) subsystams a.

Reactor Vessel Water 1,2,3, 2(b)

B sR 3.3.5.1.1 a 14.3 inches SR 3.3.5.1.2 Level - Low Low Low, Level 1 4(*),5(*)

sR 3.3.5.1.3 SR 3.3.5.1.5 sR 3.3.5.1.6 SR 3.3.5.1.7 b.

Drywell Pressure - High 1,2,3 2(b) s SR 3.3.5.1.1 s 1.88 psig l

SR 3.3.5.1.2 4

SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.7-c.

LPCI Punp A 1,2,3, 1

C SR 3.3.5.1.2 5 5.25 SR 3.3.5.1.4 seconds start - Time Delay Reiay 4(a) 5(*)

sR 3.3.5.1.6 d.

Reactor vesset 1,2,3 1

C SR 3.3.5.1.1 2 482.7 psig

$R 3.3.5.1.2 and Pressure - Low (LPCS SR 3.3.5.1.3 5 607.7 psig Injection valve SR 3.3.5.1.5 Permissive)

SR 3.3.5.1.6 4(a) $(a) 1 B

SR 3.3.5.1.1 1 482.7 psig SR 3.3.5.1.2 and SR 3.3.5.1.3 s 607.7 psig SR 3.3.5.1.5 g

SR 3.3.5.1.6

90. O J i

e.

Reactor vessel 1,2,3 1

C sR 3.3.5.1.1 e

psis SR 3.3.5.1.2 and Pressure-Low (LPCI SR 3.3.5.1.3 s M P 6 psis T.57.4 injection Valve SR 3.3.5.1.5 Permissive)

SR 3.3.5.1.6 490.0 4(a), 5(*)

1 B

SR 3.3.5.1.1 2

psig SR 3.3.5.1.2 and P !:!:l i ! " " @

sR 3.3.5.1.6 i

f.

LPCs Puup Discharge 1,2,3, 1

E SR 3.3.5.1.1 2 1200 ppm SR 3.3.5.1.2 F(ow - Low (Bypass) 4(*),5(*)

SR 3.3.5.1.3 4

SR 3.3.5.1.5 SR 3.3.5.1.6 (continued)

(a) When associated subsystem (s) are required to be OPERABLE.

(b) Also required to initiate the associated dieset generator and AEG1 subsystem.

9 i

~ PERRY - UNIT I 3.3-39 Amendment No. 69 i

)

PY-CEI/NRR.1.9691, Attcchscnt 2' ECCS Instrumentation Page 6 of 10 3.3.5.1 l

Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooting System Instrtsnectation 4

APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CH.*.NNELS PER REQUIRED SURVEILLANCEe ALLOWABLE FUNCTION CONDITIONS FUNCTION W ION A.1 REQUIREMENTS VALUE 1.

Low Preer.we Coolant Injection 4 (LPCI) and Low Pressure Core Spray (LPCS)

. SuLv,ystems (continued) 9 LPCI Pump A Discharge 1,2,3, 1

E Sw 3.3.5.1.1 2 1450 ppm-SR 3.3.5.1.2 Flow-Low (Bypass) 4(a) $(a)

SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 h.

Manual Initiation 1,2,3, 1

C SR 3.3.5.1.6 NA 4(a) $(a) 2.

LPCI B and LPCI

• Subsystems a.

Peactor Vessel Wa ur 1,2,3, 2(b)

B SR 3.3.5.1.1 m 14.3 inches SR 3.3.5.1.2 Level - Low Lom tow, ga) ds!

SR 3.3.5.1.3 Level 1 SR 3.3.5.1.5 SR 3.3.".1.6 SR 3.3.5.1.7 b.

Drywell Pressure-High 1,2,3 2(b)

B SR 3.3.5.1.1 s 1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.7 c.

LPCI Ptsup B 1,2,3, 1

C SR 3.3.5.1.2 5 5.25 Start ~ Time Delay SR 3.3.5.1.4 seconds Relay 4(*),5(a) sR 3.3.L t.6

%0,0 e 46the psig d.

Reactor Vessel 1,2,3 1 per C

SR 3.3.5.1.1 7

Pressure - Low (LPCI subsystem SR 3.3.5.1.2 and SR 3.3.5.1.3 s Here psig injection Valve Permissive)

SR 3.3.5.1.5 for LPCI B; SR 3.3.5.1.6 and fa Psig and s 54th6 psig 53'1. l for LPCI C 3.3.5.1.1 N 466:e psis 4(*),5(a) 1 per B

SR subsystem SR 3.3.5.1.2 and SR 3.3.5.1.3 s 5tthe psig SR 3.3.5.1.5

- for LPCI B; SR 3.3.5.1.6 and a

psig and s 546r6 psis for LPCI C (continued)

) When masociated subsystem (s) are required to be OPERABLE.

(b) Alto required to initiate the associated diesel generator and AEGT subsystem.

. PERRY - UNIT 1 3.3-40 Amendment No. 69

3r.

PY-CEI/NRR-1969L

.ECCS Instrumentation Attcchment 2_

3.3.5.1 Page 7 of 10 a

Table 3.3.5.1 1 (page 4 of 5)

[mergency Core Cooling System Instrunentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED _

SURVE!LLANCE

• ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 3.

High Pressure Core Spray (NPCS) System (continued)

'f.

HPCS Ptap 1,2,3, 1

E SR 3.3.5.1.1 e 120 psig SR 3.3.5.1.2 Discharge Pressure - High 4(a) $(a) gg 3,3,$,$,3 SR 3.3.5.1.5 (sypass)

SR 3.3.5.1.6 g.

HPCS System Flow 1,2,3, 1

E SR 3.3.5.1.1 a 600 ppm SR 3.3.5.1.2 Ra te - Low 4(a) 5(a)

SR 3.3.5.1.3 (Bypass)

SR 3.3.5.1.5 SR 3.3.5.1.6 h.

Manual Initiation 1,2,3, 1

C SR 3.3.5.1.6 NA 4(a) 5(*)

4.

Automatic Depressuritation System (ADS) Trip System A a.

Reactor vessel 1,2(d) 3(d) 2 F

SR 3.3.5.1.1 e 14.3 inches Water Level - Low SR 3.3.5.1.2

. SR 3.3.5.1.3 g m,9 3 g,

. Low Low, Level 1 SR 3.5.5.1.5 g

SR 3.3.5.1.6 g gg,g ny, b.

ADS Initiation 1,2(d) 3(d) 1 G

SR 3.3.5.1.2 e 'U e < -

SR 3.3.5.1.4 Timer SR 3.3.5.1.6 c.

Reactor vessel 1,2(d) 3(d) 1 F

SR 3.3.5.1.1 e 177.1 inches I

SR 3.3.5.1.2 water Levet -Low, Level 3 SR 3.3.5.1.3 SR 3.3.5.1.5 (Confirmatory)

SR 3.3.5.1.6 d.

LPCS Punp 1,2(d) 3(d) 2 G

SR 3.3.5.1.1 2 125 psig SR 3.3.5.1.2 Discharge Pressure - High SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 e.

LPCI Pupp A 1,2(d) 3(d) 2 G

SR 3.3.5.1.1 1 115 psig Discharge SR 3.3.5.1.2 Pressure - High SR 3.3.5.1.3 j

SR 3.3.5.1.5 SR 3.3.5.1.6 f.

Manual Initiation 1,2(d) 3(d) 2 G

SR 3.3.5.1.6 NA (continued) 1 (a) When associated subsystem (s) are required to be OPERABLE.

(d) With reactor steum dome pressure > 150 psig.

~ PERRY - UNIT 1 3'.3-42 Amendment No. 69

-r-PY-CEI/NRR-1969L ECCS Instrumentation Attcchment 2 3.3.5.1 i

Page 8 of 10-Table 3.3.5.1 1 (page 5 of 5)

Emergency Core Cooling System Instrunentwtf on r

APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER RZQUIRED SURVEILLANCE,

ALLOWABLE FUNCTION CONDIT!GNS FUNCTION ACTION A.1 REQb!REMENTS VALUE 5.

ADS Trip System B a.

Reactor vessel Water 1,2(d) 3(d) 2 F

SR 3.3.5.1.1 a 14.3 inches SR 3.3.5.1.2 Level - Low Low Low, SR 3.3.5.1.5 p, gog,Js y,,,J, 'I SR 3.3.5.1.3 Levet 1 gaq,f3gj SR 3.3.5.1.6 b.

ADS Initiation Timer 1,2(d) 3(d) 1 G

SR 3.3.5.1.2 i*"x._p SR 3.3.5.1.4 SR 3.3.5.1.6 c.

Reactor vessel Water 1,2(d) 3(d) 1 F

SR 3.3.5.1.1 a 17'7.1 SR 3.3.5.1.2 inches Level-Low, Level 3 SR 3.3.5.1.3 (Confirmatory)

SR 3.3.5.1.5 SR 3.3.5.1.6 l

d.

LPCI Pumps B & C 1,2(d) 3(d) 2 per pump G

SR 3.3.5.1.1 a 115 psig Discharge SR 3.3.5.1.2 SR 3.3.5.1.3 Pressure - High SR 3.3.5.1.5 SR 3.3.5.1.6

[

e.

Manual Initiation 1,2(d) 3(d) 2 G

SR 3.3.5.1.6 NA i-(d) With reactor steam dome pressure > 150 psig.

PERRY - UNIT 1 3.3-43 Amendment No. 69 i

i __

I

g.

v

.m_

.._u._

< m _

m

..._2

' Primary Containment and Drywell' Isolation Instrumentation 3.3.6.1 PY-CEI/NRR-1969L tr.ble 3.3.6.1 1 (page 1 of 6)

Primary Contairsment and Drywell isolation Instrunentation Page 9'of 10 APPLICABLE CONDIi10NS MODES OR REQUIRED REFERENCED' OTHER-CHANNELS FROM j

SPECIFIED PER TR'P REQUIRED SURVEILLANCE ALLOWABLE-1 FUNC110N CONDITIONS SYSTEh ACTION C.1 REQUIREMENTS VALUE 1.

Main Steam Line Isolation t

a.

Reactor vessel Water 1,2,3 2

0 SR 3.3.6.1.1 a 14.3 inches SR 3.3.6.1.2 Level - Low Low Low, SR 3.3.6.1.3 Level 1 SR 3.3.6.1.4 LR 3.3.6.1.5 SR 3.3.6.1.6

~l 45. "1

- b.

Main Steam Line 1

2 E

SR 3.3.6.1.1 2 7 & & psig Pressure - L ow SR-3.3.6.1.2-SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 g gq.3 c.

Main Steam Line 1,2,3 2 per MSL D

SR 3.3.6.1.1 49+ psid F L ow - Migh SR 3.3.6.1.2 i

SR 3.3.6.1.3 i

SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 d.

Condenser vacuum-Low 1,2(*),

2 D

SR 3.3.6.1.1 t 7.6 inches Sk 3.3.6.1.2 Hg vacuum 3(*)

SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 e.

Main Steam Line Pipe 1,2,3 2

D SR 3.3.6.1.1 s 158.9'F runnel SR 3.3.6.1.2 SR 3.3.6.1.4 i

Temperature - High SR 3.3.6.1.5 f.

Main Steam Line Turbine 5,2,3 2

0 SR 3.3.6.1.1 5 138.9'F Building SR 3.3.6.1.2 Temperature-4tigh SR 3.3.6.1.4 SR 3.3.6.1.5 1

]

g.

Manual Initiation 1,2,3 2

G SR 3.3.6.1.5 NA 2.

Primary Containment and Drywell Isolation a.

Reactor vessel Water 1,2,3 2 *'

H SR 3.3.6.1.1 a 127.6 inches Level - Low Low, Level 2 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 i

(continued)

(a) With any turbine stop valve not closed.

(b) Required to ir.itiate the associated drywel*. (solation function.

PERRY.- UNIT 1 3.3-54 Amendment No. 69 i

7

~

RHR Containment Spray System Instrumentation 1

3.3.6.2 PY-CEl/NRR-1969L Table 3.3.6.2 1 (page 1 of 1) -

RHR Containment Spray System Instrunentation Page 10 of 10-CONDITIONS l'

REQUIRED REFERENCED CHANNELS FROM PER TRIP REQUIRED SURVEILLANCE ALLOWABLF FUNCTIce!

SYSTEM ACTION A.1 REQUIREMENTS VALUE

' 1.

Drywell Pressure-High 2

B SR 3.3.6.2.1 5 1.88 psig SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 8 11 2.

Containment Pressure - High 1

C SR 3.3.6.2.1 5 & 05 psig 3

SR 3.3.6.2.2 4

SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 3.

Reactor vesset Water 2

s SR 3.3.6.2.1 e 14.3 inches 1

SR 3.3.6.2.2 Level - Low Low Low, SR 3.3.6.2.3 Level 1 SR 3.3.6.2.4 SR 3.3.6.2.5 4.

System A and System 8 1

C SR 3.3.6.2.2 e 10.25 minutes and Timers SR 3.3.6.2.4 s 11.45 minutes SR 3.3.6.2.5 5.

System B Timer 1-C SR 3.3.6.2.2 a 32 seconds and SR 3.3.6.2.4 5 38 seconds SR 3.3.6.2.5

]

6.

Manual Initiation 1

C SR 3.3.6.2.5 NA l

f PERRY - UNIT 1.

3.3-63 Amendment No. 69

r.

4 PY-CEI/NRR-1969L Page 1 of l' SIGNIFICANT HAZARDS CONSIDERATION The standards-used to arrive at a determination that a request for amendment involves no significant hazards considerations are included in the Commission's Regulations, 10 CPR 50.92, which state that the operation of a facility in accordance with the proposed amendment would not (1) involve a

~

significant increase in the' probability or consequences'of an accident previously evaluated, (2) create the' possibility of a new or different kind I

- of accident from any accident previously evaluated, or (3) involve a significant reduction in the margin of safety.

The proposed change has been reviewed with respect to these three factors and it has been determined that the proposed change does not involve a j

significant hazard because:

1.

The-proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed revised Trip Setpoints and Allowable Values are more conservative than those currently approved in the Technical Specifications. Therefore, any proposed system or component actuations j '

will occur earlier, resulting in a more conservative plant response.

Thus, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

4 The proposed change to the Technical Specifications does not introduce any new components nor does it modify the design of any existing components. Other than making Trip Setpoints and Allowable Values of existing instrumentation more conservative, the change does not affect the design or function of any plant system, structure, or component, nor does it change the way plant systems are operated. Thus, the possibility of a new or different kind of accident previously evaluated is not created.

3.

The proposed change does not result in a significant reduction in the margin of safety.

i Since the proposed revised Trip Setpoints and Allowable Values are more conservative than the existing values, the' margin of safety would be

. increased'by. issuance of the changes. Thus, the proposed change does not result in a significant reduction in the margin of safety.

4 F

x

_