Text

Proposed Tech Specs 3/4.3 Re instrumentation,3/4.5 Re ECCS & 3/4.6 Re Containment Sys
	ML20117L799
Person / Time
Site:	Calvert Cliffs
Issue date:	09/10/1996
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20117L784	List: ML20117L780; ML20117L799;
References
	NUDOCS 9609170150
	Download: ML20117L799 (22)
	v • d • e

- . - - - . -- .. .

f ATTACHMENT (3)

I i

1 i

i i

i UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES 4

3/4 3-19 3/4 3-20 3/4 3-21 3/4 3-22 3/4 5-4 3/4 5-5 3/4 5-6 3/4 6-15 3/4 6-16

B 3/4 3-1 9609170150 960910 PDR ADOCK 05000317 P PDR Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant September 10,1996

N -

9 TABLE 4.3-2 w G P g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w b CHANNEL MODES IN WHICH "

q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E FUNCTIONAL UNIT CHECK CALIBRATION TEST

' REQUIRED E c-

'i

1. SAFETY INJECTION (SIAS) y

~

a. Manual (Trip buttons) NA NA REFUELING INTERVAL NA

[

b. Containment Pressure - High S REFUELING 1, 2, 3 Q f INTERVAL

c. Pressurizer Pressure - Low S REFUELING ,3 /

w INTERVAL c j/

2 d. Automatic Actuation Logic NA NA G )(z)(y') ,3

" 2. CONTAINMENT SPRAY (CSAS)

a. Manual (Trip buttons) NA NA REFUELING NA i

b. Containment Pressure - High INTERVAL I S REFUELING Q , 2, 3 l INTERVAL g -

c. Automatic Actuation Logic NA NA Q )(4) , 2, 3

3. CONTAINMENT ISOLATION (CIS)#

E a. Manual CIS (Trip buttons) NA NA REFUELING NA

$ INTERVAL f' S b. Containment Pressure - High S REFUELING

,5 ' c. Automatic Actuation Logic NA INTERVAL NA M9(MD , 1,2,3 2, 3 /l 5

m

g TABLE 4.3-2 (Continued) w G P ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w '

b CHANNEL MODES IN WHICH q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

" FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED %

C

'i>

4. MAIN STEAM LINE ISOLATION (SGIS) y

a. Manual SGIS (MSIV Hand Switches NA NA REFUELING NA d and Feed Head Isolation Hand INTERVAL /

Switches) :

b. Steam Generator Pressure - Low S REFUELING ,2,3 hc1 INTERVAL o m c. Automatic Actuation Logic NA NA M Q )(S) , 2, 3 % ,

5 5. CONTAINMENT SUMP RECIRCULATION (RAS)

Y 3 8 a. Manual RAS (Trip Buttons) NA NA REFUELING NA f INTERVAL l

b. Refueling Water Tank - Low NA REFUELING 1, 2, 3 {

Q '

INTERVAL

)

c. Automatic Actuation Logic NA NA fQ 1,2,3 d

6. CONTAINMENT PURGE VALVES ISOLATION k a. Manual (Purge Valve Control NA NA REFUELING NA i 2"

=>

Switches) INTERVAL <

k b. Containment Radiation - High Area REFUELING 6**

)

s Monitor S

INTERVAL Q

j) i E'

m

. . _ . - . = _ , - . . - . . . . -. . . _ . . . . . . . - . - - .. . - . . - _ _ - - . ~ . . - - .

g TABLE 4.3-2 (Continued) 'R G

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE001REMENTS -u b CHANNEL MODES IN WHICH

q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

" FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED R

' 1 c 5

7. LOSS OF POWER y

}

~

a. 4.16 ky Emergency Bus Undervoltage 1,2,3 \*

NA REFUELING Q 2 (Loss of Voltage) INTERVAL F

b. 4.16 kv Emergency Bus Undervoltage NA REFUELING Q 1,2,3 l (Degraded Voltage) INTERVAL $

8. CVCS ISOLATION R*

West Penetration Room / Letdown NA- REFUELING Q 1,2,3,4 $

P Heat Exchanger Room Pressure - High INTERVAL t ,

)

9. AUXILIARY FEEDWATER

a. Manual (Trip Buttons) NA NA REFUELING NA t; INTERVAL ( ,

b. Steam Generator Level - Low S REFUELING Q 1, 2, 3 C INTERVAL l .

k c. Steam Generator AP - High S REFUELING Q 1, 2, 3 l

=>

INTERVAL o i

[

d. Automatic Actuation Logic NA NA MQ) 1, 2, 3 F' i E!

m l

. 1 e

3/4.3 INSTRUMENTATION I

TABLE 4.3-2 (Continued)

TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c). ,

Must be OPERABLE only in M0DE 6 when the valves are required OPERABLE and they are open.

(1 logic circuits shall be tested manually at leas r <

0 h 5 'Y

(2) SIAS logic circuits A-10 and B-10 shall be r.thh testewith

%aar'+erl the ;

exception of the Safety Injection Tank isolation v . The SIAS l logic circuits for these valves are exempted from testing during operation; however, these logic circuits shall be tested at least i once per REFUELING INTERVAL during shutdown.

f (3) '

SIAS logic circuits A-5, and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown. e 17 (4)

CIS logic circuits A-5 and B-5 are exempted from testing during

, operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.

1 (5)

SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown. I (6)

CSAS logic circuits A-3 and B-3 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.

y-CALVERT CLIFFS - UNIT 1 3/4 3-22 Amendment No. 208

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

I SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE *:

a. At least on(ce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated s positions with power to the valve operators l removed:

Valve Number Valve Function Valve Position

1. MOV-659 Mini-flow Isolation Open !

2. MOV-660 Mini-flow Isolation Open j

3. CV-306 Low Pressure SI Open Flow Control

b. At least once per 31 days by:

1. Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open. M*" Io e %5.2.C

.f Verifying)that automatic in the each flowvalve path(manual, power-operated that is not locked, sealed,oror

.g snegdJn positi nitscorrectposition.j C. AY l eu s + once eu at da y s b y -

d. t. yay nspe on w c

~

That no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be perfomed:

1. For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and

2. Of the areas affected within containment at the completion of containment entry when CONTAINHENT INTEGRITY is established.

6. # Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to increasing the RCS pressure above 1750 psia by verifying, via local indication at the valve, that t CV-306 is open.

l l

Whenever 365 F and less,flowthetesting into the high pressure RCS safety is required injection at RCS temperat pump shall .

recirculate RCS water (suction from RWT isolated) or the controls of Technical Specification 3.4.9.3 shall apply.

CALVERT CLIFFS - UNIT 1 3/4 5-4 Amendment No. 185

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

. 3/4.5 EMERGENCY CORf C0OLING SYSTEMS (ECCS)

SURVEILLANCE REQUIREMENTS (Continued)

[p At least once per REFUELING INTERVAL by:

1. Verify 1 g the Shutdown Cooling System open-pemissive interlock prevents the Shutdown Cooling System suction isolation valves from being opened with a simulated or actual RCS pressure signal of 1309 psia.

2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens,

~

etc.) show no evidence of structural distress or corrosion.

3. Verifying that a minimum total of 289.3 cubic feet of solid (

granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.

4. Verifying that a sample from the TSP baskets provides t adequate pH adjustment of water borated to be representative 4 of the post-LOCA sump condition. 5

}. g t least once per REFUELING INTERVAL, during shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation test signal.

2. Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Test Signal:

a. High-Pressure Safety Injection Pump.

b. Low-Pressure Safety Injection Pump. -

4 CALVERT CLIFFS - UNIT 1 3/4 5-5 Amendment No. 207

3/4.5 EMERGENCY CORE C0OLING SYSTEMS (ECCS)

SURVEILLANCE REQUIREMENTS (Continued) i

! hl y By performing a flow balance test during shutdown following completion of HPSI System modifications that alter system flow characterist'ics and verjfying the following flow rates for a single HPSI' Pump System :

N j 1. The,, sum of the three lowest flow legs shall be greater than i 470 gpm.

J .

l L , A By verifying that the HPSI pumps develop a total head of 2900 ft.

on recirculation flow to the refueling water tank when tested j pursuant to Specification 4.0.5.

1 4,

i A HPSI Pump System is a HPSI pump and one of two safety injection headers These limits contain allowances for instrument error, drift or fluctuation.

CALVERT CLIFFS - UNIT 1 3/4 5-6 Amendment No. 169

3/4.6 CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Soray System LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a Containment Spray Actuation Signal and Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal. Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.

APPLICABILITY: MODES 1, 2, and 3*.

ACTION: With one Containment Spray System inoperable, restore the inoperable spray system to 0PERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least NOT 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 .

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:

a. At -

1. Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

M a .- ' Move +o

/, [. Verifying that each valve (manual, power-operated, or 9. c. 2.1. b automatic) in the flow path that is not locked, sealed or otherwise secured in position is positioned to take suctio b ., $ + from4he. ssure-High test signal.

least o n RWLo W hConta

& e. Per 92. na y. oys

-Ruut. I G E , u b hutdown, by:

I 1. Verifying that each automatic valve in the flow path actuates

to its correct pe$1 tion on the appropriate ESFAS test signal.

1 1 2. Verifying that each spray pump starts automatically on the appropriate ESFAS test signal.

i 4

i With pressurizer pressure > 1750 psia.

CALVERT CLIFFS - UNIT 1 3/4 6-15 Ar::ndment No. 212 l

3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l d, f. I At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is i unobstructed. '

s 1

i P

CALVERT CLIFFS - UNIT 1 3/4 6-16 Amendment No. 212 l

3/4.3 INSTRUMENTATION -

BASES

~

3/4.3.1 and 3/4.3.2 . PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation ' systems and bypasses ensure thatJ) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint 2) the specified coincidence logic is maintained 3) sufficient redundancy is maintained to pemit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the -

overall system functional capability is maintained comparable to the original' design standards. The periodic surveillance tests perfomed at the minimum frequencies are sufficient to demonstrate this capabi' quarterly frequency for the channel functional tests for these siity. The g3i teils is t based on the analysis presented in the NRC-approved Topical Repc(tSGD- 7 A RPSlf$ RAS Futandad-

"e s ra s TT5&ou 'R ay rn + a13 m+4ng-LasAnnlamengtb g arg,

+ nut Far,,non . w

,j ncies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not appitcable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the ,

total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times. The response time limits are contained in UFSAR Chapter 7, and updated in accordance with 10 CFR 50.71(e).

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitorina Instrumentatign The OPERABILITY of the radiation monitoring channels ensures that 1) the ~

radiation levels are continually measured in the areas served by the

individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

CALVERT CLIFFS - UNIT 1 B 3/4 3-1 Amendment No. 193

ATTACHMENT (4)

UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES 3/4 3-19 3/4 3-20 3/4 3-21 3/4 3-22 3/4 5-4 3/45-5 3/4 5-6 3/4 6-11 3/4 6-12 B 3/4 3-1 Baltimore Ges and Electric Company Calvert Cliffs Nuclear Power Plant September 10,1996

g TABLE 4.3-2 g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS w b CNANNEL MODES IN WNICN !Q q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE *

{ FUNCTIONAL UNIT CNECK CALIBRATION TEST REQUIRED k c-i'i

-e

1. SAFETY INJECTION (SIAS) *

a. Manual (Trip buttons) NA NA REFUELING NA INTERVAL

b. Containment Pressure - High S REFUELING Q 1,2,3 .

INTERVAL 1

c. Pressurizer Pressure - Low S REFUELING 2, 3 Cf Q ,

INTERVAL r - -

')(z)(3

$ d. Automatic Actuation Logic NA NA , 2, 3

\d 2. CONTAINMENT SPRAY (CSAS)

a. Manual (Trip buttons) NA NA REFUELING NA INTERVAL -

b. Containment Pressure - High S REFUELING , 2, 3 .

INTERVAL (

c. Automatic Actuation Logic NA NA M O) G , 2, 3 l

3. CONTAINMENT ISOLATION (CIS)'

[ a. Manual CIS (Trip buttons) NA NA REFUELING NA Ei

)

INTERVAL i

" b. Containment Pressure - High S REFUELING Q 2, 3 t

Q )(q)

Ei , c. Automatic Actuation Logic NA INTERVAL NA g d

/ ,

, 2, 3 d h

g TABLE 4.3-2 (Continued) R a r- '

w h ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS C CNANNEL MODES IN WNICN q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE g

" FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED m

' i c >

5 4. MAIN STEAM LINE ISOLATION (SGIS) y L

a. Manual SGIS (MSIV Hand Switches NA NA REFUELING NA )

and Feed Head Isolation Hand INTERVAL g{ '

Switches)

b. Steam Generator Pressure - Low S REFUELING Q ,2,3 T ,

INTERVAL O <

w c. Automatic Actuation Logic NA NA M G )(5) 1,2,3 S 5. CONTAINMENT SUMP RECIRCULATION (RAS) w s y a. Manual RAS (Trip Buttons) NA NA REFUELING NA INTERVAL g{

b. Refueling Water Tank - Low NA REFUELING Q 1,2,3 <

i INTERVAL o -

c. Automatic Actuation Logic NA NA #Q) 1,2,3

~.

6. CONTAINMENT PURGE VALVES ISOLATION E a. Manual (Purge Valve Control NA NA REFUELING NA ' '

$ Switches) INTERVAL <

I b. Containment Radiation - High S REFUELING Q 6" b

$ 0 Area Monitor INTERVAL ,

~

]

?,

E

g l r- TABLE 4.3-2 (Continued) y a

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE U b

q CNANNEL MODES IN WHICH CHANNEL CNANNEL FUNCTIONAL UNIT FUNCTIONAL SURVEILLANCE 8

{ CHECK CALIBRATION c

. TEST REQUIRED' !'

5

7. LOSS OF POWER 5

" d

a. 4.16 kv Emergency Bus Undervoltage iE NA REFUELING (Loss of Voltage) Q 1, 2, 3 % s

b. INTERVAL 4.16 ky Emergency Bus Undervoltage NA REFUELING P / .

1,2,3 8.

(Degraded Voltage)

INTERVAL Q

f -'

l CVCS ISOLATION West Penetration Room / Letdown NA Y Heat Exchanger Room Pressure - High REFUELING Q 1, 2, 3, 4 {

5 INTERVAL e -

9. AUXILIARY FEEDWATER

a. Manual (Trip Buttons) NA NA REFUELING NA F,

b. Steam Generator Level - Low INTERVAL $

S REFUELING Q 1, 2, 3 l

k

=

c. Steam Generator AP - High S INTERVAL REFUELING Q 1,2,3 c h

$ d. INTERVAL 5

E Automatic Actuation Logic NA NA

/G) .

1, 2, 3 o-.

a i *

3/4.3 INSTRUNENTATION i

l' i

TABLE 4.3-2 (Continued)

TABLE NOTATION l Containment isolation of non-essential penetrations is also initiated j by SIAS (functional units 1.a and 1.c).

3 i Must be OPERABLE only in N0DE 6 when the valves are required OPERABLE 1 and they are open.

1

! I logic circuits shall be tested manually at least once na' 1 -H- ays.

f (2) SIAS logic circuits A-10 and B-10 shall be test th the i

exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during

} operation; however, these logic circuits shall be tested at least

! once per REFUELING INTERVAL during shutdown.

(3)

SIAS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least j once per REFUELING INTERVAL during shutdown. j j (4)

CIS logic circuits A-5 and B-5 are exempted from testing during i operation; however, these logic circuits shall be tested at least

! once per REFUELING INTERVAL during shutdown.

l (5) l SGIS logic circuits A-1 and B-1 are exempted from testing during i operation; however, these logic circuits shall be tested at least j once per REFUELING INTERVAL during shutdown. f l (6)

CSAS logic circuits A-3 and B-3 are exempted from testing during l operation; however, these logic circuits shall be tested at least i once per REFUELING INTERVAL during shutdown. 1 CALVERT CLIFFS - UNIT 2 3/4 3-22 Amendment No. 186

l'.

3/4.5 EMERGENCY C0RE C0OLING SYSTEMS (ECCS)

SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE *:

l a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves j are in the j'ndicated positions with power to the valve operators t removed: '

s l

! Valve Number Valve Function Valve Position

1. MOV-659 Mini-flow Isolation Open

} 2. MOV-660 Mini-flow Isolation Open

3. CV-306 Low Pressure SI Open

! Flow Control

{!

b. At least once per 31 days by:

n -

j . Verifying that upon a Recirculation Actuation Test SignaC i containment sump isolation valves open.

eve .4o i N ' #* # ' C

/,[ Verifying)that automatic ineach the flowvalve path(manual, that is notpower-operated locked, sealed, oror I

_ tharwja C . A + l ess + on c e c

e 2 d

a sb in,isinitscorrectpositionj

! . . y a y sua nTpecli n w c verifieiI that no loose debris (rags, 1

{ trash, clothing, etc.) is present in the containment which could i be transported to the containment sump and cause restriction of

the pump suctions during LOCA conditions. This visual inspection

shall be performed: l

( ,

! 1. For all accessible areas of the containment prior to

! establishing CONTAINMENT INTEGRITY, and I

~

2. Of the areas affected within containment at the completion

of containment entry when CONTAINMENT INTEGRITY is

i established.

i l'

e. / Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to increasing the RCS pressure above 1750 psia by verifying, via local indication at the valve, that CV-306 is open.

Whenever flow testing into the RCS is required at RCS temperatures of 301 F and less, the high pressure safety injection pump shall recirculate RCS water (suction from RWT isolated) or the controls of Technical Specification 3.4.9.3 shall apply.

CALVERT CLIFFS - UNIT 2 3/4 5-4 Amendment No. 178

3/4.5 IMERGENCY C0RE COOLING SYSTEMS (ECCS)

SURVEILLANCE REQUIREMENTS (Continued)

[Mf.AtleastonceperREFUELINGINTERVALby:

~

1. Verifyin'g the Shutdown Cooling System open-permissive interlobk prevents the Shutdown Cooling System suction isolatio) valves from being opened with a simulated or actual RCS pressure signal of 1309 psia.

2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

) 3. Verifying that a minimum total of 289.3 cubic feet of solid l

granular trisodium phosphate dodecahydrate (TSP) is {

contained within the TSP storage baskets. l

4. Verifying that a sample from the TSP baskets provides 2 adequate pH adjustment of water borated to be representative 4 of the post-LOCA sump condition. L '

3 . [ At least once per REFUELING INTERVAL, during shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation test signal.

l 2. Verifying that each of the following pumps start ,

automatically upon receipt of a Safety Injection Actuation i Test Signal:

a. High-Pressure Safety Injection Pump.

b. Low-Pressure Safety Injection Pump.

f 1

CALVERT CLIFFS - UNIT 2 3/4 5-5 Amendment No. 185

~

i

. j 3/4.5 EMERGENCY CORE C0OLING SYSTEMS (ECCS)

SURVEILLANCE REQUIREMENTS (Continued) ;

~y i

k,,gd' y performing a flow balance test during shutdown following l completion of HPSI System modifications that alter system flow l

characteristics and verjfying the following flow rates for a

single HPSliPump System

s l 1. The l 470,, gpm.

sum of the three lowest flow legs shall be greater than l L, , ,k( By verifying that the HPSI pumps develop a total head of 2900 ft 7 '

' on recirculation flow to the refueling water tank when tested pursuant to Specification 4.0.5.

l I

i A HPSI Pump System is a HPSI pump and one of two safety injection l headers.

These limits contain allowances for instrument error, drift or fluctuation.

CALVERT CLIFFS - UNIT 2 3/4 5-6 Amendment No. 149 i

l

3/4.6 CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Conte.inment Soray System LIMITINGCONDIT[0NF0li0PERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a Containment Spray Actuation Signal and Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal. Each spray system flow path from the containment sump shall be via an 0PERABLE shutdown cooling heat exchanger.

- APPLICABILITY: MODES 1, 2, and 3*.

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 30 following STANOBY hours. within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0WN within the SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:

a. At least once per 31 days by:

V

(

Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open and that a recirculation mode flow path via an 0PERABLE shuviown cooling at exchanger is established.

g

l. [ Verifying that each valve (manual, power-operated, or ~4' L I' automatic) in the flow path that is not locked, sealed or b otherwise secured in position is positioned to take suction N+.Ateas + o Me pe, 91 danq e :MLyD M a= ant Pressure-High test signal.

c. E. A leas once r.KYAL , ing shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on the appropriate ESFAS test signal.

2. Verifying that each spray pump starts automatically on the appropriate ESFAS test signal.

With pressurizer pressure t 1750 psia.

CALVERT CLIFFS - UNIT 2 3/4 6-11 Amendment No. 189 l

, , , j 3/4,6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

! s,

d. [ At least once per 5 years by perfonning an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructe .

1 s 1

i 4

i i

I i

i l

l I

l CALVERT CLIFFS - UNIT 2 3/4 6-12 Amendment No. 189 l

9 3/4.3 INSTRUMENTATION -

BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF1 INSTRUMENTATION f

The OPERABILITY of the protective and ESF instrumentation systems and bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or~ combination thereof exceeds its setpoint, 2) the specifitd coincidence logic is maintained. 3) sufficient redundancy is maintained to pemit a channel to be out of service for testing or maintenance, and 4) sufficient ~ system functional capability is available for protective and ESF purposes from diverse parameters.

- The OPERABILITY of these systems is required to provide the overall '

reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient i conditions. The integrated operation of each of these systems is l consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the

overall system functional capability is maintained comparable to the

! original design standards. The periodic surveillance tests perfomed at

the minimum frequencies are sufficient to demonstrate this capability. The j quarterly frequency for the channel functional tests for these sy s is t based on the analysis presented in the NRC-approved Tc ical Repo N-327. I , i l jr e art; egy.yo3, a 1

(@'f s Ms nohyo g Aelag7etge- 7~er+ g r ved en

== " W ,.rtu .'"Tmc p ov es '

i assurance that the protective and ESF action function associated with each l channel is completed within the time limit assumed in the accident 1 analyses. No credit was taken in the analyses for those channels with

response times indicated as not applicable.

1 l Response time may be demonstrated by any series of sequential, overlapping j

or total channel test measurements provided that such tests demonstrate the .

total channel response time as defined. Sensor response time verification

may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times. The response time limits are contained in UFSAR Chapter 7, and

' updatedinaccordancewith10CFR50.71(e).

s

3/4.3.3 MONITORING INSTRUMENTATION i

l 3/4.3.3.1 Radiation Monitorina Instrumentation 4

i The OPERABILITY of the radiation monitoring channels ensures that 1) the i radiation levels are continually measured in the areas served by the

! individual channels and 2) the alam or automatic action is initiated when the radiation level trip setpoint is exceeded.

)'

i 1

CALVERT CLIFFS - UNIT 2 B 3/4 3-1 Amendment No. 170 l

i

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ML20117L799

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