Text

Proposed Tech Specs Re Use of Blind Flanges in Place of Containment Purge Valves During Operation
	ML20116F828
Person / Time
Site:	Calvert Cliffs
Issue date:	08/01/1996
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20116F826	List: ML20116F823; ML20116F828;
References
	NUDOCS 9608070169
	Download: ML20116F828 (26)
	v • d • e

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UNIT 1 TECIINICAL SPECIFICATION MARKED-UP PAGES Table of Contents V 3/4 3-12 3/4 6-1 3/4 6-3 3/4 6-14 3/4 6-22 3/4 6-23 l

3/4 9-5 B 3/4 6-3 9608070169 960801

. PDR ADOCK 05000317 P PDR Baltimore Gas and Electric Company l Calvert Cliffs Nuclear Power Plant August I,1996 l

l 1 TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENT

_SECTION 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System ....

Pres s uri ze r . . . . . . . . ..........

............ 3/4 4-28 '

Overpressure Protection. Systems . . . . . . . . .

3/4 4-32 .

. 3/4 4-33 b 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 And.3 Components . . . . . . . .

3/4 4-37 4 3/4.4.11 CORE BARREL MOVEMENT ................ 3/4 4-39 $

3/4.4.12 LETDOWN LINE EXCESS FLOW ..............

3/4 4-41 $

3/4.4.13 REACTOR COOLANT SYSTEM VENTS . . . . . . . . . . . . 3/4 4-42 Y 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i 3/4.5.1 SAFETY INJECTION TANKS ............... 3/4 5-1 '

3/4.5.2 ECCS SUBSYSTEMS - MODES 1, 2 and 3 (t 1750 PSIA) .. 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - MODES 3 (< 1750 PSIA) and 4 . . . . 3/4 5-7 3/4 5.4 REFUELING WATER TANK .......~......... 3/4 5-8 !

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMEN1 CONTAINMENT INTEGRITY . . . . . . . . . . . 3/4 6-1 Containment Leakage . . . . . . . . . . . .... . . .. .. 3/4 6-2 i

l Containment Air Locks . . . . . . . . . . . . . .. 3/4 6-5 Internal Pressure . . . . . . . . . . . . . . 3/4 6-7 Ai r Temperature . . . . . . . . . . . . . . . ....

.... 3/4 6-8 Containment Structural Integrity .......... 3/4 6-9:

Containment-Pury System ...-......... 3/4 6 (

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System .............. 3/4 6-16 Containment Cooling System ............. 3/4 6-18 3/4.6.3 IODINE REMOVAL SYSTEM . . . . . . . . . . . . . . . . 3/4 6-20 l

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CALVERT CLIFFS - UNIT 1 V Amendment No. 188 I l

g TABLE 3.3-3 (Continued) y G '

w g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION b MINIMUM y y TOTAL NO. CHANNELS CHANNELS APPLICABLE E

" FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i5i t lE c- 6. CONTAINMENT PURGE VALVES $

] ISOLATION

[ lf gd,< lf g m[q y

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a. Manual (Purge Valve Control -2/Pcr.ctretian 1/Penetratien 2/Penci.rai.ivu 6 8 Switches) k

b. Containment Radiation -

High Area Monitor 4 2 3 6** 8 R* 7. LOSS OF POWER w

h a. 4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

Undervoltage (Loss of Voltage) : .

b. 4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1, 2, ' 3 7*

Undervoltage (Degraded Voltage)

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3/4.6 . CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT C0E/JNNENT INTEGRITY LIMITING CONDITION FOR OPERATION I 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.' '

)K 1 APPLICABILITY: MODES 1, 2, 3 and 4. l ACTION: i Without primary CONTAINMENT. INTEGRITY, restore CONTAINMENT INTEGRITY 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD within one hour SNUTDOWN or the within befollowing in at least NOT 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . STANDBY within the

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i SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINNENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations **

not capable of being closed by OPERABLE containment automatic f isolation valves and required to be closed during accident conditions are closed by valves, blind-flanges, or deactivated automatic valves secured in their positions, except for valves that are open 3.6.4.1.

under administrative control as pennitted by g Specification b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

c.

By verifying that the equipment hatch is closed and sealed, prior to entering M0DE 4 following a shutdown where the equipment hatch was opened, A onndir J. by conducting a Type B test per 10 CFR Part 50, d . Ta s u i

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Hydrogen containment purge containment pressure control vent isolation valves shall be opened for surveillance testing purposes, only. airborne radioactivity control, and [

The shutdown cooling isolation valves may be opened when the RCS temperature is below 300 F to' establish shutdown cooling flow. d s

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or $

otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTD0WN except that such verification need not be perfomed more often then once per 92 days.

CALVERT CLIFFS - UNIT 1 3/4 6-1 Amendment No. 187

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a Insert A i

I By verifying that the containment purge blind flanges are installed an,d sealed prior to entering Mode 4 following a shutdown where the blind flanges were removed, by conducting a Type B test per 10 CFR Part 50, Appendix J. Ifonly one blind flange was removed, only that blind flange must be tested unless testing is required by Technical Specification 4.6.1.2.

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l 3/4.6 CONTAINMENT SYSTEMS l i l SURVEILLANCE REQUIREMENTS (Continued)

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b.

Type B and C tests shall be conducted with gas at P (50 psig) at ;4 intervals of 24 months except for tests involving a r lo

c. Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

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d. All Type B and C test leakage rates shall be calculated using observed data converted to absolute values. 4 ontainment purge isolation valves shall be demonstrated 0P l an e upon entering MODE 5 from power operation mo , unless BLE $

the last illance test has been perfomed w the past l six months or a me after being opened )rior to entering i MODE 4 from shutdown s by ve'rif that wien the measured

leakage rate is added to t age rates determined pursuant to Technical Specification . 2. all other Type B or C ;4-penetrations, the . ned leakage rate ss than or equal to 0.50 L (173 CCM). The leakage rate for ntainment purge ation valves shall also be compared to the tously i

ured leakage rate to detect excessive valve degradation.

f. The containment purse iseld4auutive__ seals shall be ran12eed h' I

with new seals at a frecuency tn ent= av u seal r greater than 2 consecutive fuel reloa cl es . !

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l Exemption to 10 CFR Part 50, Appendix J.

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

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 _ PRIMARY CONTAINMENT Containment Purae System LIMITING CONDITION FOR OPERATION h 6.1.7 The containment purge supply and exhaust isolation valves sh be clo by isolating air to the air operator 'and maintaining the sol oid air su valve de-energized.

APPLICABILI N0 DES 1, 2, 3 and 4.

-ACTION:

a. With one contal valve open, close nt purge supply one exhaust isolation open valve (s )and/

thin one hour or be in at least HOT STANDBY with the next hours and in COLD SHUTDOWN within the following 30 ho .

b. With one containment purg uppl valve inoperable due to gh leakag nd/or one exhaust isolation 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in C0 SHUTDOWN within re)leair the valve (s) within !

following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE , UIREMENTS 4.6.1. The 48-inch containment purge supply and exhaust isolation yk sha be detennined closed at least once per 31 days, by verifying that (

er to the solenoid valve is removed. I CALVERT CLIFFS - UNIT 1 3/4 6-14 Amendment No. 212 N

3/4.6 CONTAINMENT SYSTEMS 3/4.6.4 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4.1 Each containment isolation valve shall be OPERABLE.* '

5PPLICABILITY: MODES 1, 2, 3, and 4.

ACTION: With one or more of the isolation valve (s) inoperable, either:

a. Restore the inoperable valve (s) to 0PERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one or position, deactivated automatic valve secured in the isolation

c. Isolate the affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or

d. 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 ,

e. The provisions of Specification 3.0.4 are not applicable provided that the affected penetration is isolated.

SURVEILLANCE REQUIREMENTS 4.6.4.1.1 Each containment isolation valve shall be demonstrated OPERABLE' ,

. prior to returning the valve to service after maintenance, repair, or I replacement work is performed on the valve or its associated actuator, control, or power circuit by perfomance of a cycling test and verification of isolation time.

Valves that are nonna11y closed may be opened on an intermittent basis under administrative control.

Containment purge isolation valves isolation times will only apply in 440DE A @an the valves are reouired to be OPERABLE and thev'are open.

[^hel: tier, time: for cent:1~"ea+ a"ece 1:01stier va!vog (c Na nr 3

,,GES 1, 2,.t___

wu,.a .,__ 3 ano. .4,.per lecnnicai 5 -,---s

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ped ficetici. 3/4 5.1.', & ring CALVERT CLIFFS - UNIT 1 3/4 6-22 Amendment No. 212 M

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i 3/4.6 CONTAINMENT SYSTEMS i -

SURVEILLANCE REQUIREMENTS (Continued) l 4.6.4.1.2 Each containment isolation valve shall be demonstrated OPERABLE j during the COLD SHUTD0WN or REFUELING M0DE at least once per REFUELING INTERVAL by: l l

j a. Verifying that on each containment isolation Channel A or Channel i i B test signal, each required isolation valve actuates to its l

{ isolation position. i i

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bMe-Wno that on each Containment Radiation-Hinh Te: t Channel A \ !

or Channel B test sim.21: 'eth =9'rco containment purge valves \

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i pa+e t; Micir Isolation position. -

i b c. Verifying that on each Safety Injection Actuation Channel A or I i Channel B test signal, each required isolation valve actuates to

its isolation position.

4.6.4.1.3 The isolation time of each power-operated or automatic containment isolation valve chall be determined to be within its' limit when i

2 tested pursuant to Technical Specification 4.0.5. -

l CALVERT CLIFFS - UNIT 1 3/4 6-23 Amendment No. 212 k

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3/4.9 REFUELING 0PERATIONS SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment penetrations shall be detemined to be either in its required condition or capable of being closed by an OPERABLE automatic containment purge valve within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months $

prior to the start of and at least once per 7 days during CORE ALTERATIONS and movement of irradiated fuel in the containment by: g

a. Verifying the penetrations are in their required condition, or S

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CALVERT CLIFFS - UNIT 1 3/4 9-5 Amendment No. 194

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3/4.6 CONTAINNENT SYSTEMS BASES'

! 3fb6,b2 _ Containment Purae Supply and Exhaust Isolation Valves l i !

i This limitation ensures inment purge supply and e5haust-valves I i will be maintained shut during MOD ontair ~ . p Wssurization may l occur as the result of LOCA or. =L a ions. The capability

) of these valves to ng a containment pressurtz ent and j

J gation of these lines has not been established.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 1

! 3/4.6.2.1 Containment Sorav System i '

The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leaka are consistent with the assumptions used in the accident analyses. ge rate j 3/4.6.2.2 Containment Coolina System 4

! The OPERABILITY of the Containment Cooling System ensures that 1) the l l

containment air temperature will be maintained within limits during nonnal l operation, and 2) adequate heat removal capacity is available during post-

LOCA conditions. ,

l 3/4.6.3 IODINE REMOVAL SYSTEM j

The OPERABILITY of the containment iodine filter trains ensures that sufficient iodine removal capability will be available in the event of a '

i LOCA. The reduction in containment iodine inventory reduces the resulting SITE B0UNDARY radiation doses associated with containment leakage. Tne i

i operation of this system and resultant fodine removal capacity are j consistent with the assumptions used in the LOCA analyses. i l 3/4.6.4 CONTAINMENT ISOLATION VALVES

{ The OPERABILITY of the containment isolation valves ensure that the i containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified in plant procedures ensures that the release of t radioactive material to the environment will be consistent with the j assumptions used in the analyses for a.LOCA.

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{ CALVERT CLIFFS - UNIT 1 B 3/4 6-3 Amendment No. 187

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ATTACHMENT (4)

UNIT 2 TECHNICAL SPECIFICATION MARKED-UP PAGES Table of Contents V 3/4 3-12 3/4 6-1 3/4 6-3 3/4 6-10 3/4 6-18 3/4 6-19 3/4 9-5 B 3/4 6-3 l

I Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant August 1,1996

l0 4 TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

.E8.G.E 1 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant S Pressurizer . . .ystem ............... 3/4 4-28 i

................ 3/4 4-32 Overpressure Protection Systems . . ... . . . . . 3/4 4-33 1

i 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components . . . . . . .

' 3/4 4-37 i 3/4.4.11 CORE BARREL MOVEMENT ............... 3/4 4-39 $

3/4.4.12 LETDOWN LINE EXCESS FLOW ............. 3/4 4-41 $

3/4.4.13 REACTOR COOLANT SYSTEM VENTS ...........

3/4 4-42 $

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS l

.............. 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - MODES 1, 2 AND 3 (> 1750 PSIA)

_, . 3/4 5-3 l 3/4.5.3 ECCS SUBSYSTEMS - MODES 3 (< 1750 PSIA) AND 4 . . . 3/4 5-7 3/4 5.4 REFUELING WATER TANK ............... 3/4 5-8 3/4.6 CONTAINMENT SYSTEMS l

! 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY . . . . . . . . . . . . 3/4 6-1 Containment Leakage . . . . . . . . . . . . . . . .

. . 3/4 6-2 Containment Air Locks . . . . . . . . . . . . . . 3/4 6-5 Internal Pressure . . . . . . . . . . . . . . 3/4 6-7 Air Temperature . . . . . . . . . . . . . . . ...

... 3/4 6-8 Containment Structural Integrity ......... 3/4 6-9 l Icntair.a.ert Nrg: Sy:te : ............. 3/4 6-11 .I l

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System ............. 3/4 6-12 i j Containment Cooling System ............ 3/4 6-14 3/4.6.3 IODINE REMOVAL SYSTEM . . . . . . . . . . . . . . . 3/4 6-16 i

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CALVERT CLIFFS - UNIT 2 V Amendment No. 178

g TABLE 3.3-3 (Continued) w w

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION n MINIMUM E C TOTAL N0. CHANNELS CHANNELS APPLICABLE $

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E

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i 6. CONTAINMENT PURGE VALVES E g ISOLATION g ;7 4 g 7 g[x

a. Manual (Purge Valve Control 4/ Penetration -1/Penetrat10n 2/ Penetration 6" 8 \ E Switches)

b. Containment Radiation - High Area Monitor 4 2 3 6" 8 R

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7. LOSS OF POWER

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a. 4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

M Undervoltage (Loss of Voltage)

b. 4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

Undervoltage (Degraded Voltage)

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3/4.6 CONTAINMENT SYSTEMS i

3/4.6.1 PRIMARY CONTAINMENT CONTAI M ENT INTEGRITY 1

LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAIMENT INTEGRITY shall be maintained.* '

4 l APPLICABILITY: MODES'1, 2, 3 and 4.

ACTION: Without primary CONTAIMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOW within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGP.ITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations **

4 not capable of being closed by 0PERABLE containment automatic 4

isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated i

automatic valves secured in their positions, except for valves y' that are open under administrative control as pemitted by Specification 3.6.4.1.

b. By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

c. By verifying that the equipment hatch is closed and sealed, prior to entering MODE 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test per 10 CFR Part 50,

Appendix J. _

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Hydrogen purge containment vent isolation valves shall be opened for

, containment pressure control, airborne radioactivity control, and X surveillance testing purposes only.

I The shutdown cooling isolation valves may be opened when the RCS temperature is below 300 F to establish shutdown cooling flow. y' Except valves, blind flanges, and deactivated automatic valves which .;k are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOW except that such i

verification need not be perfomed more often then once per 92 days.

CALVERT CLIFFS - UNIT 2 3/4 6-1 Amendment No. 164

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i Insert A By verifying that the containment purge blind flanges are installed and sealed prior to l entering Mode 4 following a shutdown where the blind flanges were removed, by

, conducting a Type B test per 10 CFR Part 50, Appendix J. If only one blind flange was removed, only that blind flange must be tested unless testing is required by Technical Specification 4.6.1.2.

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3/4.6 _ CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Type B and C tests shall be conducted with gas at P (50 psig) at Q' intervals of 24 months except for tests involving air locks.

c. Air locks shall be tested and demonstrated OPERABLE per g Surveillance Requirement 4.6.1.3.

d. All Type B and C test leakage rates shall be calculated using observed data converted to absolute values. V

e. tainment purge isolation valves shall be demonstrated 0 any upon entering MODE 5 from POWER OPERATION BLE

, unless t'

the last elllance test has been perfonne n the past 6 months or any after being opened rier to entering H0DE 4 from shutdown by ver ng that when the measured leakage rate is added to t age rates determined pursuant to Technical Specificat .6.1.2.b 11 other Type B or C %

penetrations, ombined leakage rate ss than or e~ qual to 0.50 L. ( , O SCCM). The leakage rate for containment purg ' olation valves shall also be compared to t eviously

!ae ured leakage rate to detect excessive valve degrada ine o ns r rentains in servira greater than 4 con 3Etutwe-heLrQcycles.

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Exemption to 10 CFR Part 50, Appendix J.

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

j 3/4.6 CONTAINMENT SYSTEMS l l

3/4.6.1 PRIMARY CONTAINMENT

! _ Containment Purae System i

LIMITING CONDITION FOR OPERATION

3. 1.7 The containment purse supply and exhaust isolation va'lv clos shall be air sup by isolating air to the air operator and maintaining t solenoid valve deenergized.

APPLICABILIT MODES.1, 2, 3 and 4.

ACTION:

a.

With one containm t purge supply and r one exhaust isolation valve open, close the open alve(s) withi one hour or be in at least HOT !

STANDBY within the nex hours d in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one containment pur supp inoperable due to high eakage, re and/or exhaust isolation valve ir the valve (s) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in COLD SHUTD0 within the fo ging 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE UIREMENTS ~

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4.6.1.7 he 48-inch containment purge supply and exhaust isola shall e determined closed at least once per 31 days, by verifyin valves po t r to the solenoid valve is removed. i l

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j CALVERT CLIFFS - UNIT 2 3/4 6-10 Amendment No. 189 k l

3/4.6 _ CONTAINMENT SYSTEMS 3/4.6.4 _ CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION :

1 3.6.4.1 Each containment isolation valve shall be OPERABLE.* '

APPLICABILITY: MODES 1, 2, 3, and 4.

l ACTION: With one or more of the isolation valve (s) inoperable, either: .

a. Restore. the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or

c. Isolate the affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or l

d. 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 . j

e. The provisions of Specification 3.0.4 are not applicable provided that the affected penetration is isolated. ;

1 SURVEILLANCE REQUIREMENTS 4.6.4.1.1 Each containment isolation valve shall be demonstrated OPERABLE' prior to rcturning the valve to service after maintenance, repair, or replacement work is performed on the valve or its associated actuator, control, or power circuit by performance of a cycling test and verification of isolation time.

Valves that are normally closed may be opened on an intermittent basis under administrative control.

Containment purge isolation valves isolation times will only apply in MODE 6 when _the valves are reauired _to be OPERABLE and they are open.

leclaticn times fer containment purge iscletien velves is N;i 70r- \

NODES 1, 2, 3 and 4 per Tech-ical Specificatien 3/4 5.1.7, during j whicAt4me these velves mu t =ein clnsed.

CALVERT CLIFFS - UNIT 2 3/4 6-18 Amendment No. 189 I

3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 4.6.4.1.2 Each containment isolation valve shall be demonstrated 0PERABLE during the COLD SHUTDOWN or REFUELING M0DE at least once per REFUELING INTERVAL hy:

a. Verifying that on each containment isolation Channel. A or Channel B test signal, each required isolation valve actuates to its l isolation position. i b M.that on each Containment Radiation High T rd-channel A '

' 'h i Dort;Channer iv sne1ra isolation tv i s'cr-'. Mcyuired n. containment purge valves i

b4 Verifying that on each Safety Injection Actuation Channel A or 1 Channel B test signal, each required isolation. valve actuates to its isolation position.

4.6.4.1.3 The isolation time of each power-operated or automatic containment isolation valve shall be determined to be within its limit when !

tested pursuant to Technical Specification 4.0.5. .- i i

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CALVERi .LIFFS - UNIT 2 3/4 6-19 Amendment No. 189 if

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3/4.9 REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment penetrations shall be detennined to be either in its required condition or capable of being &

closed by an OPERABLE automatic containment purge valve within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of and at least once per 7 days during C0RE ALTERATIONS s and movement of irradiated fuel in the containment by: ' c

a. Verifying the penetrations are in their required condition, or 4 i ca!o l

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CALVERT CLIFFS - UNIT 2 3/4 9-5 Amendment No. 171

3/4.6 CONTAINMENT SYSTEMS BASES

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374.R Containment Purae Supply and Exhaust Isolation Valves i This limita ntainment purge and exhaust valves l will be maintained ~ shut during ontainment pressurization may l

l occur as the result o s eam line nditions. The capability l of these c ose during a containment press on event and 1

l e isolation of these lines has not been established. '

l l 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS L

3/4.6.2.1 Containment Soray System l The OPERABILITY of the Containment Spray System ensures that containment l depressurization and cooling capability will be available in the event of a '

l LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.

3/4.6.2.2 Containment Coolina System .

The OPERABILITY of the Containment Cooling System ensures that 1) the containment air temperature will be maintained within limits during normal ,

operation, and 2) adequate heat removal capacity is available during post-LOCA conditions.

3/4.6.3 IODINE REMOVAL SYSTEM .

I The OPERABILITY of the containment iodine filter trains ensures that sufficient iodine rerraval capability will be available in the event of a LOCA. The reduction in containment iodine inventory reduces the resulting ;

SITE B0UNDARY radiatien doses associated with containment leakage. The i

operation of this systan and resultant iodine removal capacity are consistent with the assumptions used in the LOCA analyses.

3/4.6.4 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensure that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified in plant procedures ensures that the release of radioactive material to the environment will be consistent with the %'

assumptions used in the analyses for a LOCA.

l l

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l CALVERT CLIFFS - UNIT 2 B 3/4 6-3 Amendment No. 164 l

l

ATTACIIMENT (5) i l

1 CONTAINMENT PURGE SYSTEM ILLUSTRATION (PRESENT ARRANGEMENT) l BalttIniore Gas and Electric Company Calvert Cliffs Nuclear Power Plant August 1,1996

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l CONTAINMENT PURGE SYSTEM ILLUSTRATION (MODIFIED ARRANGEMENT) l l

l Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant August 1,1996

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