Text

Proposed Tech Specs Tables 3.3-3,3.3-4,3.3-5,4.3-2 & Corresponding Tech Spec Pages,Clarifying Requirements for Containment Pressure Control Sys by More Clearly Detailing Design of Sys
	ML20154S647
Person / Time
Site:	Catawba
Issue date:	05/27/1988
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20154S638	List: ML20154S635; ML20154S647;
References
	NUDOCS 8806090131
	Download: ML20154S647 (14)
	v • d • e

'

ATTACIDiENT 1 PROPOSED TECHNICAL SPECIFICATION AMENDMENTS 8806090131 880527 PDR ADOCK 05000413 P

DCD

.n l

~

}

l TABtE 3.3-3 (Continued)

ENGINEERED SAFE 1Y FEATURES ACTUATION SYSTEM INSTRUMENTATION

-4 E

I E

MINIMUM e

TOTAL NO.

CilANNELS CilANNELS APPLICABLE c

i'E FUNCTIONAL UNIT Of CilANNELS TO TRIP OPERABLE MODES ACTION e

6.

Turbine Trip (Continued) e-ro c.

Steam Generator Water Level-liigh-liigt. (P-14) 4/ steam 2/ steam 3/s.eam 1,2 19*

generator generator in generator in any operating each operating steam steam generator generator d.

Trip of All Main

{

Feedwater Pumps 2/ pump 1/ pump 1/ pump 1,2#

25 Y

e.

Reactor Trip (P-4) 2 2

2 1,2,3 22

w f.

Safety Injection See item 1. above for all Safety Injection initiating functions and requir m nts.

gao(,h i9u m,sfave 7.

Containment Pressure Control.

tftwn (-fenarndso vG System (Tec m:nd.oc/ Stark Per*55d*)

' tert crain lvc ain 2/trai:.

ain 1, 2, 3, 4 g 2d a.

dawmel't spr.g 5 s+m co 3

b.

icrainatica rain 2/trai::

rain 1, 2, 3, 4 X

2. 8 8.

Auxiliary feedwater I

Manual Initiation 1/ train 1/trais.

1/ train 1,2,3 26 a.

b.

Automatic Actuai. ion logic 2

1 2

1,2,3 21 and Actuation Relays 2.lhm (%ck 9ennIs5Ne.-

C denmed AVRe. ben ani

( lico,in Crtni A di O B 1coyn Skmmer 5 slem

~

3 3

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 20 - With less than the Minimum Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 21 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION ! squired by Specification 3.7.1.4.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or initiate and maintain operation of the Control Room Area Ventilation System with flow through the HEPA filters and activated carbon adsorbers.

(

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at lea t HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 27 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

Insext MTIOM 2?) oc glac.e m m gy -g4 3 4 CATAWBA - UNITS 1 & 2 3/4 3-26 Amendment No, y' (Unit 1)

Amendment No. ;W (Unit 2) n

INSERT FOR PACE 3/4 3-26 ACTION 29 - a.

With the number of OPERABLE channels one less than the Total Number of Channels:

1.

Place the inoperable channel in the start permissive mode within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and 2.

Restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the number of OPERABLE channels one less than the Minimum Channels operable requirement:

1.

Place the inoperable channels in the start permissive mode with 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and 2.

Apply the applicable ACTION statement (Contair. ment Spray Technical Specification 3.6.2, Containment Air Return and Hydrogen Skimmer System Technical Specification 3.6.5.6),

i

TABLE 3.3-4 (Continued) n INGINEERED SAFETY FEA10RES ACTUAIION SYSlEM INSTRUMENTATION TRIP SETPOINIS N$

SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA)

Z_

(S)

TRIP SEIP0lNT ALLOWABLE VALUE c-5d

6. Turbine Trip a.

Manual Initiation N.A.

N.A.

p.

b.

Automatic Actuation N.A.

N.A.

m Logic and Actuation Relays c.

Steam Generator Water Level-liigh-liigh (P-14) 1.

Unit 1 5.4 2.18 1.5

< 82.4% of

< 84.2% of narrow Harrow range range instrument instrument span t*

span a

2.

Unit 2 9.7 2.18 1.5

<78.1% of

<79.9% of narrow J, j Harrow range range instrument w

instrument span 1

span g

t.

d.

Trip of All Hain N.A.

N.A.

{

feedwater Punp.,

q e.

Reactor Trip (P-4)

N.A.

E A.

f.

Safety injection See Item 1. above for all Safety Injection Setpoints and Allowable y "c Values.

~

7. Containment Pressure Control P'

O *W E System (,Tenndon /%d bessNel b =}c

a. C d'=ta t "c;;i n i. _

E

=4cdament Seq Sysicm

-' O. ' ;n i d

< 0. '5 nid e N.A.

N.A.

C b

Tc;c!=9 ian N.A.

N.A.

-i 0.3 p;?d 1 0.25 p;id g

8. Auxiliary feedwater o

V a.

Manual InitiaLion N.A N.A.

N.A.

N.A N.A.

b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays l

. l* 1.:

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS 4.

Steam Line Pressure-Low (Continued) l 10)

Control Room Area Ventilation N.A.

)

J Operation 11)

Annulus Ventilation Operation 5 23 12)

Auxiliary Building Filtered 1

Exhaust Isolation N.A.

13)

Containment Sump Recirculation N.A.

b.

Steam Line Isolation 57 5.

Containment Pressure-High-High a.

Containment Spray

< 45 5 65(3)/76(4) b.

Phase "B" Isolation Nuclear Service Water Operation N.A.

c.

Steam Line Isolation 17 d.

Containment Air Return and Hydrogen 1 600 Skimmer Operation 6.

Steam Line Pressure - Negative Rate-High Steam Line Isolation 17 7.

Steam Generator Water Level-High-High a.

Turbine Trip 1 3 b.

Feedwater Isolation 57 8.

T

~l0*

avg Feedwater Isolation N.A.

i 9.

Doghouse Water Level-High Feedwater Isolation N.A.

j 10.

St:rt Nr-itch >e dentainm+ Sq Sysh Containment Pressure Control System N.A.

(.7ectrun. Men / We4 Perminiw0 11 7 eci-inetion T

Containment Pressure Control System N.A.

(%tnah'ra lS{ set femisswe) j

% %amakAteh k ~dihdr*p 5 % c Syk CATAWBA - UNITS 1 & 2 3/4 3-39

T4BLE 4.3-2 (Continueo) oD ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E

5URVEILLANCE REQUIR MENT 5

?

TRIP ANALOG ACTUATING MODES c-21 CllANNEL DEVICE MASTER SLAVE FOR WilICH d

CilANNEL CilANNEL. CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRAfl0N TEST TEST LOGIC TEST TEST TES IS REQUIRED

~

S. Feedwater Isolation (Continued) ro b.

Steam Generator S

R H

N.A.

1, 2 Water Level-High-High (P-14)

T,yg-Low (P-4 c.

L Interlock)

S R

M N.A.

N.A.

1, 2 h

d.

Doghouse Water i.

t' Level-High H.A.

N.A.

R(4)

N.A.

1, 2 l

v a

w e.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

5 I

c, 6.

Turbine Trip a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2 E

b.

Automatic N.A.

N.A.

M(1)

Q 1, 2 1

Actuation Logic and 4

Actuation Relays l@gg@

c.

Steam Generator S

R H

N.A.

1, 2 0

Water Level-High-High E @:@

(P-14) ee d.

Trip of All Main N.A.

N.A.

R(4)

N.A.

1, 2 l

E 2z Feedwater Pumps PP dN e.

Reactor Trip (P-4)

N.A.

K.A.

R(4)

N.A.

1,2,3 l

22

' 3.

f.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

7 E $$

7. Containment Pressure

_C Control System (Tectrundt a[hd 9erm155Nc) h N.A.

N.A.

1, 2, 3, 4 a a.Et:rt N r-irciJe S

R M

b..'c-irEier, p 5 a_a s d

R M

N.A N.A.

N.#

1,2,3,4

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS r

CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION i

3.6.2 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the refueling water storage tank and transferring suction to the containment sump.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one Containment Spray System inoperable, restore the inoperable Spray System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 fours; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the'following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS I

4.6.2 Each Containment Spray System shall be demonstrated OPERABLE:

L a.

At least once per 31 days by verifying that each valve (manual, j

power-operated, or automatic) in the flow path that is not locked, i

sealed, or otherwise secured in position, is in its correct position; L

b.

By verifying, that on recirculation flow, each pump develops a differential pressure of greater than or equal to 185 psid when tested pursuant to Specification 4.0.5; c.

At least once per 18 months during shutdown,*" by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Phase "B" Isolation test signal, and 2)

Verifyingthateachspraypumpstartsautomaticallyona Phase B Isolation test signal.

I if ing thatJac spr is p Jr v from,sta b

f ntaipe(nt P es e Co ro1J 7 stem wh n a cont t

j phyre press is les t)afi or equal 0.25 ps

, and a

1s 1)cwed to s rt at gr ttr than or e al to 0.45 psid j

(

rel tive to the outside a

sphere,

_J li

- This surveillance need not be performed until prior to entering HOT SHUT 00VN following the Unit 1 first refueling.

l CATAWBA - UNITS 1 & 2 3/4 6-18

CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) f) Ver' ying th each sp sy pump ischarge alve clo s or is 4

pr ented f om openi by the ontainme Pressur Control S stem wh the con ainment ospher pressure is less t an r equa to 0.25 id and i allowed o open greater han or equal o 0.45 p d relati to the utside a.osphere, and 5

Ver fying th each spr y pump i automat' ally dee rgized b the Cont nment Pr sure Co rol Sys m when th contai ent tmosphere ressure i less t n or eq 1 to 0.25 psid re ative to the ou ide atmos here.

J g__

d.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

s CATAWBA - UNITS 1 & 2 3/4 6-19

CONTAXNMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) f.

Verifying that the motor-operated valv; in the hydrogen skimmer suction line opens automatically and the hydrogen skimmer fans receive a start permissive signal; and g.

Verifying that with the fan off, the air return fan check damper is closed.

4.6.5.6.2~

t least nee per months each Conta ment Air R turn and 7

Hydrogen kimmer S tem sha be demo strated OPE BLE by:

f Verif ng that ach air eturn fan is deenergize or is pr ented fr..

star ing by t Contai ent Pressur Control Sy tem when e contai -

me intern pressur is less tha or equal 0.25 psi, relati' t the out de atmos ere; and b.

Verifyi that eac air return an isolati n damper oses or s preven ed from o ning by the ontainment ressure ntrol Sy tem when he contai ent internal pressure i less than or equal to 0.25 psid and 's allowed to pen at gre er than o equal t f

0.4 psid, re ative to the utside atm phere.

L i

-J i

l 1

CATAWBA - UNITS 1 & 2 3/4 6-49

ATTACIDfENT II DISCUSSION AND NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS i

1

DISCUSSION AND NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS As described in Chapter 6 and Section 7.3 of the Catawba FSAR, certain Engineered Safety Features (ESP) (i.e., the Containment Air Return and Hydrogen Skimmer (VX)

System and the Containment Spray (NS) System) are provided to prevent overpressurizing the containment in the event of a LC0A. The Containment Pressure Control System (CPCS) is provided to prevent excessive depressurization of the containment through inadvertent or excessive operation of these Engineered Safety Features.

The CPCS allows operation of the NS and VX Systems only shen they are required for reducing containment pressure and inhibits their operation when they are not required for containment protection.

The CPCS is designed for operation over a pressure range of -5 to +60 psig. For accuracy, the containment pressure sensors are designed to respond to the reduced range of -5 to +5 psig, though not adversely affected by pressure transients up to 6C psig. The CPCS is designed such that it does not affect the accuracy, margb., or response of the ESF Actuatinn System as the start permissive setpoint is below the ESFAS setpoint for high containment pressure.

The start permissive and termination features of the redundant trains of the Containment Pressure Control System are provided by eight independent pressure sensors (four per train). These pressure sensors interlock the controls of the NS System and the VX Fans and Hydrogen Skimmer System to prevent their operation when containment pressure is below approximately 0.25 psig. The CPCS control logic is presented in the attached Figure.

The proposed Technical Specification changes are intended to clarify and provide further detail of the functions of the CPCS. The changes would also add a CPCS specific ACTION statement which would direct plant personnel to place any inoperable CPCS channels in the safe (start permissive) mode and either place the unit in a shutdown condition or apply the applicable VX or NS ACTION statement depending on the number of inoperable channels.

This is more conservative than the current ACTION statement since the proposed ACTION statement and the VX and NS specifications contain shutdown requirements whereas the current CPCS ACTION statement would allow continued operation.

Please note that the proposed ACTION Statement is ACTION 29. A new ACTION 28 was proposed in my letter dated March 11, 1988 concerning item 8.f.

It is also proposed that Surveillance Requirement 4.6.2c.3), c.4), c.5),

4.6.5.6.2a. and 4.6.5.6s2b. be deleted. These surveillances will continue to be performed under the proposed new Trip Actuating Device Operational Test Surveillances on Table 4.3-2, for items 7.a and 7.b.

These new proposed l

surveillances will encompass the current requirements plus allow all of the requirements for the CPCS to be maintained in one locat an of the Technical

)

Specifications. As stated in FSAR Section 7.6.5 the CPCS is capable of being tested with the unit on-line. The requirement contained in Surveillance 4.6.2c.

to conduct the tests during shutdown was originally intended to apply to actuation of NS System components.

Since the CPCS surveillances do not require operation of NS System equipment, the CPCS surveillances can be done with the plant operating. Therefore, deletion of the requirement to test during shutdown is appropriate and will not impact the safe operation of the station. The net result of this proposed amendment would be added clarification to the

. 't.'

. Technical Specifications which cover the CPCS, more restrictive yet more prescriptive ACTION requirements and no impact on any currently required Setpoints or Surveillance Requirements.

10 CFR 50.92 (c) states that "a proposed amendment... involves no significant hazards considerations, if operation of the facility in accordance with the proposed amendment would not:

(1) Involve a significant 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.

I The proposed amendment does not increase the probability or consequences of any previously evaluated accident. The changes are clarification of the description of existing instrumentation.

The new ACTION statement will be at least as conservative as the existing ACTION statement. The Trip Setpoints will not be affected and the Surveillance Requirements will still be required. Also, the CPCS was designed so that testing could be performed during power operation.

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

The changes are clarification and do not involve a change in the design or allowed modes of operation of the station.

All current setpoints and Surveillance Requirements will be maintained and applicable ACTION Statements will be more restrictive.

The preposed changes do not involve a significant reduction in a margin of safety. The proposed changes are clarification for existing instrumentation and the new ACTION statement is at least as conservative as the existing ACTION statement. The Surveillance Requirements and Setpoints will not be changed by this amendment. Also, the CPCS was designed to allow testing during power operation.

4 For the reasons stated above, Duke Power concludes that the proposed amendments do not involve Significant Hazards Considerations.

1 l

t

j1 II l

f DN A

t

,f ne m

l n

j D

ia C

N lA t e I

v nr G

T ou O

N C s L

EMY P

s l

T N A *H 4

i R

h e O

D f

R U T

gr

/

N A

I T

AP P S

iP 2

lA i

v S

T S l

E l

N G

e O

i R

S lg v

C T

T l

A N E I

D N H V i

i i

s E

E N

CtL l

E s

M5eA e

A N

N S

i lV O

m v

E l

l I

l e

L r

i P

A AL e

s O

T C

TY NO P

s NA S e

OR O i

I t

m v

C C P r

r i

S a

e s

r t

P s

e i

a S

m v

t l

r r

i i

m a

e s

t P

s i

S S

i t

m r

r c

a e

i t

P g

o S

t E

L V

r N R N RL a

E B

T E

E EA t

E P

N Gt V O

R G MN O

f E

O9 S

n S

A O HA P

R L

T t

i T

R l F iT S

O D K[

C a

S D K r

Y S

Y SL I

H H

N I

E I

ON NRUR I

N T E E

R RRN P

N EP S

f-UA O

i E

RM O

A I

T AT F T

P A

L S

E S

O RD C

R I

A erusser P

A t

nn:

i u

an r n T l I

a t

no C

2cE0EM 0h gd g Te 2 <2 9 a

ON

}4. N T Y" f'

I

'

ML20154S647

Text

Navigation menu

Search