ML20203H924

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Proposed Tech Specs Re ESFAS Instrumentation
ML20203H924
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 12/11/1997
From:
DUKE POWER CO.
To:
Shared Package
ML20203H899 List:
References
NUDOCS 9712190080
Download: ML20203H924 (25)
v • d • e


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TABLE 3.3-4 (Continued)

ENGINEERED SAFETt FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP SETPOINT ALLOWABLE VALUE FUNCTIONAL UNIT

13. Annulus Ventilation Operation
a. Manual Initiation N.A. N.A.
b. Automatic Actuation Logic N.A. N.A.

and Actuation Relays

c. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
14. Nuclear Service Water Operation
a. Manual Initiation N.A. N.A.
b. Automatic Actuation Logic N.A. N.A.

and Actuation Relays

c. Loss-of-Offsite Power 2 3300 V 2 3242 V Containment Spray See Item 2. above for all Containment Spray Setpoints and Allowable Values.

d.

e. Phase "B" Isolation See Item 3.b. above for all Phase "B" Isolatior. S-%oints and Allowable Values.
f. Safety Injection See Item 1. above for all Safety Injection Setpoints ana Allcwable Values.

, .c- -

g. Suction Transfer-Low Pit Level 2 El . 65t:4 f t. 2 El . 552:9- f t.

557.5 55 5.4 9712190000 971211 PDR ADOCK 05000413 P PDR CATAWBA - UNIT 1 3/4 3-35 Amendment No. W s

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' Attachment lb .

Catawba Unit 2 Current-Technical' Specifications. Marked Copy  ;

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' M 'M T 3 1 E j d 3 C I 1 E 1 5 $ U E M I z I idA 4. M d i 15 o 2.ii A A M .0:14

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  • TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRLHENTATION TRIP SETPOINTS e

~

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE

13. Annulus Ventilation Operation
a. Manual Initiation N.A. N.A.

i

b. Automatic Actuation Logic N.A. N.A.

and Actuation Relays

c. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values. ,

t

14. Nuclear Service Water Operation
a. Manual Initiation N.A. N.A.

f b. Automatic Actuation Logic N.A. N.A.

and Actuation Relays >

{

c. Loss-of-Offsite Power a 3500 V 2 3242 V
d. Containment Spray See Item 2. above for all Containment Spray Setpoints and Allowable Values.

. e. Phase "B" Isolation See Item 3.b. above for all Phase "B" Isolation Setpoints and Allowable 1

values.

f. Safety Injection See item 1. above for all Safety Injection 3etpoints and Allowable Values.
g. Suction Transfer-Low Pit Level 2 E1.45t:4 Tt. 2 El . SE?.T f t.

N5 655.9 I

CATAWBA - UNIT 2 3/4 3-35 Amendment No. j f

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- , , , .. .. - . . . =. .. .

Attachment Ic-4

-Catawba Unit 1 Improved.Technica1' Specifications Marked Copy l

F A

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'3.3.2  !

l(. .'

Table 3.3.2 1 (page 5 of 5) ,

Engineered Safety feature Actuation System Instrumentation APPLICABLE MDOE5 OR

  • OTHEP SPECIFIE0 REQUIRCD SURVIILLANCE ALLOWABLE -TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIRCENTS VALUE 5tTPOINT
8. [5FA5 Joterlocks
a. Reactor Trip P-4 1.2.3 1 per F SR 3.3.2.8 NA NA train. 2 trains
b. Pressurizer 1.2.3 3 0 SR 3.3.2.5 a 1944 and 1955 ps19 Pressure. P.11 $R 3.3.2.9 s 1966 psig '

. c. T 1.2.3 1 per 0 SR 3.3.2.5 a 550*F a $53'F P.D. Low Low. loop SR 3.3.2.9

9. Containment Pressure
  • Control System
a. Start Pemissive 1.2.3.4 4 per P SR 3.3.2.1 s 0.45 psid s 0.4 psid train SR 3.3.2.7 SR 3.3.2.9
b. Temination 1.2.3.4 4 per P SR 3.3.2.1 a 0.25 psid a 0.3 psid train SR 3.3.2.7 __

' ' ' ~

SR 3.3.2.9

10. Nuclear Service Water 1.2.3.4 3 per QR SR 3.3.2.1 a 49e* f t a 664T+ ft Suction Transfer . pit SR 3.3.2.9 ff.555.4 El.ss i. 5 -

Low Pit Level SR 3.3.2.11

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d Catawba Unit 1 3.3 35 4/ZGf si r

-m-w p .y -.--- , -,v..m- .c p - *. w4

= _ _ - . - _ ._ . _ .

i Att'achmenti- id ,

Catawtia. Unit 2 Improved Technic 11 Specifications Marked Copy-

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ESFAS Instrumentation 3.3.2 Table 3.3.21 (poes 5 of 5)

Erwineered Safety Feature Actuation Systemi Instrumentation APPLICutE MODES OR

  • OfMER SPECIFIED REGUIRCD SURVEILLANCE ALLOWABLE TRIP FUNCTION colelfl0NS CNANNELs coeffl0N$ REQUIRE 8ENTS YAlta SETPOINT
4. E5fA5 Interlocks
s. Reactor Trip, P 4 1,2,3 - 1 per F st 3.3.2.8 NA NA train, 2 trains
b. Pressurlaer 1,2,3 3 0 $t 3.3.2.5 a 1964 and 1955 psis Pressure, P 11 54 3.3.2.9 s 1966 psis .
c. T *L 1,2,3 1 per 0 st 3.3.2.5 a 550'F a 553*F ,

P% ow Low, loop SR 3.3.2.9 9 Contelnment Pressure Control system

e. Start Permissive 1,2,3,4 4 per P st 3.3.2.1 s 0.45 paid s 0.4 paid train st 3.3.2.7 54 3.3.2.9
b. Terminetton 1,2,3,4 4 per P st 3.3.2.1 a 0.25 paid a 0.3 paid train st 3.3.2.7 54 3.3.2.9
10. Nucteer service Water 1,2,3,4 . 3 per 0,R st 3.3.2.1 a 95T.Y ft a 49t:t*ft suction Transfer - pit 54 3,3.2.9 g556.4 Low Pit Level st 3.3.2.11 E).55% 6

(.

Catawba Unit 2 3.3-35 c5/ZG/A

,_ Attachment le ,

NUREG 1431 Technical Specifications Marked Copy

~

and Catawba Nuclear Station Units'1 and 2 Current Technical Specifications Marked Copy r

e ESFAS Instr'unentation 3.3.2

' tabte 3.3.21 case. 4 of as Egineered safety feature Actuetten system instrumentatten APPLICAsti Nepts OR Ofuta PWCita M iI800 Meutatt anyt3LLaeCE ALLEhmsLt Ceeltles (namutLs Coeltleus arestneuests 1eIP m vnLUE- stiPolWiWF F

l F. Auteentle suit to Centetrument ' --- H -

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!centinued) '

8 MI l

  • tew 1,2,3,4 4 g L se 3.3.2.1 t (153% t (1815 3R 3.3.2.5 3R 3.3.2.9 Sa 3.3.2.10 Coincleont with sefer to psart 1 (sofety injectlan) for ett inittetten '

safety injectlen fwetlans requirements. ,

and Celacident with 1 , ,4 4 g ga 3.3.2 Centatteent su'P 8 (301 in. t t } in.

l'*L"818h sa 3.3 .5 h m se 3 .2.9 at. [7e3j te et, g Ift se .3.2.10

4. EsfAs intertects
s. Rewter Trip, P.4 1,2,3 1 per I 88 3.3.2.M h4 m train. 2 trains q
b. Preeeuriser
  1. f** " 8. P*II 1,2,3 3 gp WQ g 9, se 3.3.2.5 pote SE 3.3.2.9 g e. 1 -ta= tow, P 12 1,2,3 i ,.c yo -

n . 9.t t u[r h g 3. .. 9 h g l85 le esentations any con n enty atteusbte wel tre en setsdiint stud]y s

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b. 7t'N I,tal" f'" h " P s , . 'W '

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4 TABLE _ (Conti==d)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRiseITATION TRIP SETPOINTS FUNCTIO M TRIP SETPOINT ALL0tMBLE VALifE Annulus Ventlia ion Operation

a. Manual I tlation M.A. N.A.
b. Aut Ic Actuation Logic M.A. N.A.

and tuation Relays

c. S ety injection ee Item 1. above for all Safety jection Setpoints and A11 ~ "le nes_  ;

10 34. Nuclear Service Water M I Manual Initi ion N.A N.A.

! b. Automatic ctuation Logic .A. N.A.

and Act tion Relays O c.

d.

Loss- -Offsite Power C tainment spray a 3500 V a 3242 V See Ites 2. above for a Centainment Spray Setpoints a Allowabl

e. Phase "B" Isolation See Item 3.b. above f all Phase "S" Isolation Set nts and Allowable l

Values.

Safety Injection See Iten I. above er all Safety Injection Set nts and Allowable V lues.

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e fg.Suction Transfer-Low Pit Level I

= EI. , M ft. 2 E1. [ ft.

551.5 5 ta 555. '

id 8 t AREA OF bHWF [*

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w CATAWBA - UNIT 2 3/4 3-35 . Amendment No. P

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.s TABLE - (Continued) h ENGINEERED SAFETY F1'ATURES ACTUATION SYSTEM INSTMEOfTATION TRIP SETPOINTS L FUNCTIO M ,

TRIP SETPOINT ALLOWABLF VALUE

%'. annulus Ventila on vyci.L e

a. Manual I tiation N.A. N.A.
b. Aut tic Actuation Logic M.A. M.A.

an Actuation Relays (c. afety Injection e Item 1. above for all Safety In etion Setpoints and Allowable values to J/. Nuclear Service Water @ -

fa. Manual Initia on M.A. N.A.

b. Automatic tuation Logic M.A. N.A.

and Actua on Relays

c. Loss-o -Offsite Power a3 Y a 3242 V -
d. Co ainment Spray Item 2. above for all C tai. _..s 5piay 5etpoints and All

~

le V

e. ase "B" Isolation See Item 3.b. above for 1 Phase "B" Isolation Setpoints a Allowable Values.

Safety Iniection See Item 1. above r all Safety injection Setpoints a Allowable values.

Suction Transfer-Low Pit level a El. . ft. 2 El. 3r,r:g ft, SS'1. S 5S S.'$

Anes or C"^*e l

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, f' CATAW8A - UNIT 1 3/4 3-35 Amendment No. g r l

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Attachment:

2a  ;

Catawba UnitJ1 Current' Technical Specifications -i i

' Remove Pages: -Insert Pages:-

3/4 3-35 3/4 3 ,

6 4

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a Y "

w ) w- . et w

TABLE 3.3-4 (Continued)- ,

EMElNEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

. FUNCTIONAL UNIT TRIP'SETPOINT ALLOWABLE VALUE  ;

113. Annulus Ventilation Operation

a. Manual Initiation- N.A. N.A.
b. Automatic Actuation Logic - N.A. M.A.

~ and Actuation Ralays c.- Safety Injection See Item 1. 'above~for all Safety Injection Setpoints and Allowabie' Values'.-

14. Nuclear Service Water Operation
a. Manual Initiation N.A. N.A.
b. Automatic Actuation Logic N.A. :N.A.

and Actuation. Relays c .- Loss-of-Offsite Power- 2 3500 V 2 3242 V

d. -Containment Spray See Item 2. above 'for all Containment Spray Setpoints and Allowable Values.
e. - Phase "B" Isolation See Item 3.b. above for all Phase "B" Isolation Setpoints'and Allowable Values.
f. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable' Values..
g. Suction Transfer-Low Pit Level 2 El. 557.5 ft. 2 El. 555.4 ft.

CATAWBA - UNIT 1 3/43-35 Amendment No.

' f* ,

9 Attachment 2b

. .  ?

. Catawba Unit 2. Current Technical Specifications f

Remove ~Pagest  : Insert Pages: ,

3/4z 3-35 .3/4 3-35 I

k a

4 a

+

f

TABLE 3.3-4 (Continued) , ,

d. ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION' TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPal!!I ALLOWABLE VALUE
13. Annulus Ventilation Operation
a. Manual Initiation .N.A. N .' A . -
b. Automatic Actuation Logic N.A. M.A.

and Actuation Relays

c. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
14. Nuclear. Service Water Operation
a. -Manual Initiation M.A. N.A.
b. Automatic Actuation Logic N.A. N.A.

and Actuation Relays

c. Loss-of-Offsite Power 2 3500 V -2 3242 V
d. Containment Spray See Item 2. above for all Containment Spray Setpoints and Allowable Values.-
e. Phase "B". Isolation See Item 3.b. above for all Phase "B" Isolation Setpoints and Allowable Values.
f. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
g. Suction Transfer-Low Pit Level 2 El. 557.5 ft. 2 El. 555.4 ft.

CATAWBA - UNIT 2 3/43-35 Amendment No.

s  :.

e ,

--Attachment-2c

. Catawba Unit 1-ImprovAd_ Technical Specifications i

Remove Pages: Insert-Pages:

3.3-35 3.3-35 s

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P' 4

f-i i

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ESFAS Instrumentatien 3.3.2 Table 3.3.21(page5of5) ingineered f afety Feature Actuation System Instrwnentation APPLICABLE H0 DES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCilDN CONDIT!DN5 CHANNELS CONDITION 5 REQUIREMENTS VALUE SETPOINT

8. . tSFA5 Interlocks
a. Reactor Trip, P-4 1.2.3 1 per F SR 3.3.2.8 NA NA train, 2 trains
b. Pressurirer 1.2.3 3 0 SR 3.3.2.5 a 1944 and 1955 psig Pressure. P 11 SR 3.3.2.9 s 1966 psig
c. T.,1. Low Low, 1,2,3 1 per 0 Sk 3.3.2.5 a $50*F a 553*F P 17 loop SR 3.3.2.9
9. Containment Pressure Control System
a. Start Permissive 1.2.3.4 4 per P SR 3.3.2.1 s 0.45 psid s 0.4 Psid train SR 3.3.2.7

$R 3.3.2.9

b. Termination 1,2,3,4 4 per P SR 3.3.2.1 a 0.25 psid a 0.3 psid train SR 3,3.2.7 SR 3.3.2.9
10. Nuclear Service Water 1,2,3,4 3 por Q,R 5R 3.3.2.1 a E1. 555.4 El. 557.5 Suction Transfer - pit SR 3.3.2.9 ft it Low Pit Level SR 3.3.2.11 Catawba Unit 1 3.3-35 10/14/97

'l

. Attachment 2d Catawba Unit 2. Improved Technical Specifications

- Remove Pages: Insert Pages:

-3.3 35 3.3-35 i

l t

1

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 5)

. Engineered Safety Feature Actuation $ystem Instrumentation APPLICABLE MODE $ OR OTHER

$PECIFIED REQUIRED SURVE!LLANCE ALLOWABLE TRIP FUNCil0N CONDITlDNS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

8. EsrA5 Interlocks
a. Reactor Trip, P 4 1,2,3 1 per F SR 3.3.2.8 NA NA train, 2 trains
b. Pressuriter 1,2,3 3 0 SR 3.3.2.5 a 1944 and 1955 psig Pressure, o.11 SR 3.3.2.9 s 1966 psig
c. 1,2,3 1 per 0 SR 3.3.2.5 a $50*F a 553*F T*D.LowLow, P. loop SR 3.3.2.9
9. Containment Pressure Control System
a. Start Permissive 1,2,3,4 4 per P SR 3.3.2.1 s 0.45 psid s 0.4 psid train SR 3.3.2.7 SR 3.3.2.9
b. Termination 1,2,3,4 4 per P SR 3.3.2.1 a 0.25 psid a 0.3 psid train SR 3.3.2.7 SR 3.3.2.9
10. Nuclear Service Water 1,2,3,4 3 per Q,R $R 3.3.2.1 a El. 555.4 a El. 557.5 J

$uction Transfer - pit SR 3.3.2.9 ft ft i Low Pit Level SR 3.3.2.11 Catawba Unit 2 3.3-35 10/14/97

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Attachment 3 -t Description of Proposed Changes and Technical-Justification Change to Technical. Specification on Engineered Safety Features Actuation System Instrumentation

A' change _is requested to Technical-Specification (TS) 3/4.3.2 Eng!neered Safety Features. Actuation System Instrumentation. (The corresponding proposed Improved 1echnical Specification is 3.3.2.) Specifically, a change

!- to tne Trip Setpoint and Allowable Value in the Nuclear Service hater System Suction _ Transfer-Low Pit Level _

contained-in the Table of Engineered Safety Features 1 Actuation Systsn Instrumentation is being requested. The JTrip Setpoint and Allowable Value are contained in '

Functional' Unit 14 9 of Tcble 3.3-4 of the current TS and Function 10 of Table 3.3.1-1 of the proposed Improved TS.

Both the current 1TS and the proposeo Improved TS specify the Trip Setpoint for the Suction Transfer-Low Pit Level to be greater thaa or equal to El. 554.4-ft., with an Allowable Velue of greater thar. or equal to El. 552.9 ft. This amendment, oncs approved, would revise the Trip Setpoint to greater than or equal to El. 557.5 ft., with an Allowable Value of greater than or equal to El. 555.4 ft.

1 I

s TECHNICAL JUSTIFICATION

Background

The Nuclear Service Water Pump Intake Pit Level Transmitters are safety-grade instruments which alert the operators that a low level condition exists in the pumphouse pits and initiate a swap of'the pit suction source from Lake Wylie to the Standby Nuclear Service Water Pond upon emergency low level. The setpoints for the pit suction source swapover-rre based on Net. Positive Suction Head Requirements for the-haclear Service Water Pumps.

The TS required Trip Setpoints are nominal values at which

the bistables are set for each functional unit in the table.

To accommodate the instrument drift. assumed to occur between

4*

operational tests-and the accuracy to which Sotpointsican:bel measured and calibrated, = Allowable Values are specified. G m

- Justi fication The proposed-Technical: Spec'ification change provides more-conservative values for the Suction Transfer-Low Pit Level

-Trip Setpoint and_ Allowable Value than the existing Technical Specification. The proposed values ensure

-sufficient Net Positive Suction Head to the Nuclear Service ,

Water System pumps allowing sufficient _ margin for instrument error to account for current instrument error calculation-methodology, o

Subsequent to the time of. initial plant licensing, the methodology for calculating instrument loop uncertainty was revised _to a more conservative technique. The new method identifies more possible error terms and thus yields more conservative numbers. As part of an overall self-imorovement' process, the calculations supporting the Suction Transfer-Low Pit Level Trip Setpoint and Allowable Value

, were_ revised using the new methodology and the conclusion is t that the allowance for instrument loop error should be 1.8 feet for the pit level instruments.

A review was conducted to evaluate the effects of this revised instrument error on the existing level setpoint and allowable value. During the review, it was determined that the instrument error indicated in the existing calculations was 1 foot. These ca]culations had been performed in accordance with more generalized engineering procedures and

-the original Westinghouse setpoint methodology.

Also during this review, it was identified that the existing Trip Setpoint and Allowable Value contained in TS may not ensure adequate Net Positive Suction Head to the Nuclear Service Water Pumps. The minimum Net Positive Suction Head requirement for the Nuclear Service Water Pumps was investigated. It was determined that adequate Net Positive Suction Head would be available to the Nuclear Service Water Pumps with a minimum actual _ pit level of El. 555.4 ft. For added conservatism, it was decided to maintain a minimum level of El._557.5 ft.

The_ existing TS specify that the suction transfer pit low

-level Trip Setpoint be greater than or equal to El. 554.4 ft, with an Allowable Value of greater than or equal to El.

552.9 ft. These limits do not ensura adequate Net Positive Suction Head for the Nuclear Service Water Pumps. In-order to provide _this assurance, it is requested that the Trip

f.-

Setpoint be revised to El. 557.5 ft. and the Allowable Value

  • be: revised to El, 555.4 ft. These revised values provide-

-assurance-that suction swapover.will occur at a pit level <

that would provide continued Net Positive Suction head for tile Nuclear Service Water- Pumps af ter accounting for instrument error.

The Instrument Data Sheets,-calculations, and procedures currently in use at the site specify a Trap Setpoi.. of El.

557.5 ft. This omendment to the TS to reflect the revised value is'being requasted so that the Limiting Condition for Operation will comply with the requirements of 10 CFR 50.36, which states that the TS must provide the lowest functional capability of a component or system.

c' e

a .

Attachment 4 No Significant Hazards Considerations Evaluation As required by 10CFR50.91, this analysis is provided concerning whether the requested amendment involves significant hazards considerations, as defined oy 10CFR50.92. An amendment request involves no significant hazards considerations if operation of the facility in accordance with the requested amendment would not: 1)

Involve a sis ,1ficant increase in the probability or consequences of an accident previously evaluated; or 2)

Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)

Involve a significant reduction in a margin of safety.

Criterion 1 - Would operation of the facility in accordance with the requested amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

The Nuclear Service Water System is the ultimate heat sink for various QA Condition 1 heat loads during normal operation and design basis events. The system supports Emergency Core Heat Removal operation by providing cooling to the Component Cooling System via the Component Cooling Heat Exchangers and also to the Diesel Generators via the Diesel Generator Engine Jacket Water Cooler System Heat Exchangers. Other QA-1 loads include the Containment Spray Heat Excnangers and the Control Area HVAC System / Control Area Chilled Water System. The System also provides assured makeup to the Component Cooling System, Spent Fuel Pool, Auxiliary Feedwater and Containment Seal Water Injection systems. The Standby Nuclear Service Water Pond (SNSWP) is the assured source for the Nuclear Service Water System. A swap of the suction source for the Nuclear Service Water system from Lake Wylie to the SNSWP is required upon the loss of Lake Wylie. This swap is accomplished by level transmitters located in the Nuclear Service Water System pump pits. The setpoint at which this swapover occurs is established to ensure adequate Net Positive Suction Head to the Nuclear Service Water pumps. The revised TS Trip Setpoint and Allowable Value are necessary to ensure the pumps' Net Positive Suction Head requirements are satisfied.

c' e

-This amendment affects only the level at which the suction swapover occurs. Increasing the Net Positive Suction Head available to the Nuclear Service Water pumps does not adversely affect operation of the pumps. The increase in the suction transfer low pit transfer-setpoint will result ,

in'a reduction of the differential pressure across the SNSWP pit isolation valves. The reduced differential pressure will not. adversely impact the SNSWP pit isolation valvet.

The proposed change does not impact the method of accomplishing the swapover or any additional operational features of the Nuclear Service Water System.

The change does not impact the initiators of any accidents, nor does the change have the potential to impact the consequences of any accident in which the swapover is assumed to occur. Therefore, it is concluded that the proposed change will not increase the probability or consequences of an accident previously evaluated.

Criterion 2 - Will operation of the facility in accordance with the requested amendment create the possibility of a new or different kind of accident from any previously_ evaluated?

This amendment proposes limits for the suction transter that are more conservative than that contained in existing TS.

The effects of this change on operation of the Nuclear Service Water System are limited to the Net Positive Suction Head of the Nuclear Service Water pumps and the differential pressure across the SNSWP pit isolation valves. Neither of these changes would have an adverse effect on Nuclear Service Water System performance. No nes failure modes are created by this change, and no potential for previously unanalyzed accidents is created.

Criterion 3 - Will operation of the facility in accordance with the requested amendment involve a significant reduction in the margin of safety?

Implementation of the requested amendment will not involve a significant reduction in a margin of safety. Operation of the facility in accordance with the requested amendment will result in an increase in the available Nat Positive Suction Head available to the Nuclear Service Water system pumps.

Based upon the preceding analyses, Catawba Nuclear Station concludes that the requested amendment does not involve a significant hazards consideration.

O Attachment 5 Environmental Assessment Pursuant to 10 CFR 51.22(b), an evaluation of this license amendment request has been performed to determ!ne whether or not it meets the criteria for categorical exclusion set forth in 10 CFR 51.22 (c) (9) of the regulations.

This proposed amendment to the Catawba Units 1 and 2 Technical Specifications revises the current Trip Setpoint and Allowable Value for the Nuclear Service Water System Suction Transfer - Low Pit Level to a more conservative value. Operation of the facility in accordance with this amendment has been reviewed and determined not to involve a significant harards consideration. The Nuclear Service Water System is the ultimate heat sink for various heat loads during normal operation and design basis events, and Nas no direct impact on any effluent generation or control systems. The change in Trip Setpoint and Allowable /alue for the Nuclear Service Water System Suction Transfer to a more conservative value does not impact the type or quantity of effluents from the station. The proposed change to the setpoint does not impact individual or cumulative occupational radiation exposure.

It has been determined that there is:

1) No significant hazards consideration (see Attachment 4);
2) No significant change in the types, or significant increase in the amounts, of any effluents that may be re] eased offsite; and
3) No significant increase in individual or cumulative occupational radiation exposures involved.

Therefore, this amendment to the Catawba Technical Specifications meets the criteria of 10 CFR 51.22 (c) (9) for categorical exclusion from an environmental impact statement.

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