ML20082M817

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Proposed Tech Spec Section 3/4.7.8 Re Operability Requirements for Main Turbine Bypass Sys
ML20082M817
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 08/27/1991
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20082M812 List:
References
NUDOCS 9109060023
Download: ML20082M817 (17)
v • d • e


Text

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ATTACllMENT 2 [

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i LIMERICK GENERATING STATION .

Docket Hos. 50-352 [

50-353

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PROPOSED TECilNICAL SPECIFICATIONS CllANGES t

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List of Attached Pages  ;

Unit 1  :

11 i xiv l xxi  !

1-8 ,

3/4 2-3  !

3/4 2-9 i 3/4 7-33  !

B 3/4 7-5 l Unit 2 i i

I l 11 xiv xxi ,

1-8 ,

3/4 2-8  ;

3/4 2-9  !

L 3/4 7-33 i i B 3/4 7-5  !

L I t

i I t

9109060023 910827 PDR ADOCK 05000352  ;

P PDR v v

INDEX J p

DEFINITIONS SECTION I

1 DEFINITIONS (Continued) PAGE  !

I 1.22MEMBEP.(S)0FTHEPUBLIC..........................................1-4 [

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1.23 MINIMUM CRITICAL POWER RA110..................................... 1-4  !

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' 1.24 0FFS11E 00SE CALCULATION MANUAL.................................. 1-4  !

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1.25 OPERABLE - OPERABILITY........................................... 1-4  !

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1. 26 OPERAT IONAL CONDIT ION - CONDIT 10N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 l 1.27 PHYSICS TESTS.................................................... 1-4

(

1.28 PRESSURE BOUNDARY LEAKAGE........................................ 1 1. 29 PRIMARY CONTAI NMEN1 I NT EGR ITY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 5 ~  ;

1.30 PROCESS CONTROL-PR0 GRAM.......................................... 1-5 1.31 PURGE --PURGING.................................................. 1-5 1.32 RATED THERMAL P0WER.............................................. 1-6 1.33 RE ACTOR ENCLOSURE SECONDARY CONT AINMENT INTEGRITY. . . . . . . . . . . . . . . . 1-6 1.34 REACTOR PROTECTION SYSTEM RESPONSE TIME.......................... 1-6 1.35 REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY. . . . . . . . . . . . . . . . . .1-6 1.36 REPORTABLE EVENT................................................. 1-7 1.37 ROD' DENSITY...................................................... 1-7 1.38 SHUTOOWN MARGIN.................................................. 1-7

~ 1.39 SITE 80VNDARY.................................................... 1-7 1.40 (Deleted)........................................................ 1-7 1,41 SOURCE CHECK..................................................... 1-7 1.42 STAGGERED TEST BASIS............................................. 1-8 1.43 THERMAL P0WER.................................................... 1-8 1.43A TURBINE BYPASS SYS1EM RESPONSE TIME............................. 1-8 1.44 UNIDENTIFIED LEAKAGE............................................. 1 ,

LIMERICK - UNIT 1 11

INDEX LIMITING CONDITIONS FOR OPlRATION AND SURVEILLANCE REQUIREMENTS .-

PAGE SEC110N N Nil SYSTEMS (Continued) 3/4.7.2 CONTROL ROOM EMERGENCY FRESll AIR SUPPLY SYSTEM - COMMON 3/4 7-6 SYSTEM....................................................

3/4.7.3 REAC10R CORE ISOLATION COOLING SYSTEM...................... 3/4 7-9 3/4.7.4 SNUBBERS.................................................... 3/4 7-11 figure 4.7.4-1 Sample Plan 2) for Snubber functional Test........................ 3/4 7-16 3/4.7.5 SEALED SOURCE CONTAMINATION................................ 3/4 7-1/

3/4.7.6 flRE SUPPRESSION SYSTEMS fire Suppression Water System.............................. 3/4 7-19 Sprav and/or Sprinkler Systems............................. 3/4 7-22 Csp Systems............................................ 3/4 7-24 Halon Systems.............................................. 3/4 7-25 fire liose Stations....................... ................. 3/4 7-26

^

Table 3.7.6.5-1 fire Hose Stations.................... 3/4 7-27 Yard f ire liydrants and Itose Cart Houses. . . . . . . . . . . . . . . . . . . . 3/4 7-29 Table 3.7.6.6-1 Yard fire Hydrants and liose Cart Houses............................ 3/4 7-30 4

flRERATEDASSEMBL'.\S....................................... 3/4 7-31 3/4.7.7 .

3/4 7-33 3/4.7.8 MAIN TURBINE B(PAS' SYSTEM............. .................... l 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. Sources - Operating................................... 3/4 8-1 Table 4.8.1.1.2-1 Diesel Generator Test Schedule............................ 3/4 8-8 A.C. Sources - Shutdown.................................... 3/4 8-9 3/4.8.2 D. C. SOURCES D. C. Sources - Operating............................... .. 3/4 8-10 LIMERICK - UNIT 1 xiv

. I INDEX  !

s BASES ,

SECTION PAGE lt CONTAINMENTSYSIDi(Continued) I 3/4.6.3 PRIMARY CONTAINMENT ISOLA 110N VALVES................... B 3/4 6-4 l 3/4.6.4 VACUUM RELIEF.......................................... B 3/4 6-4 l 1

3/4.6.5 SECONDARY C0NTAINM[NT.................................. B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT AIMOSPHERE CON 1ROL................. B 3/4 6-6 3/4.7 PLANT SYSTEMS l t

3/4.7.1 SERVICE WATER SYSlEMS - COMMON SYSlEMS................. B 3/4 7-1 i 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM -

COMMON SYSTEM............................................ B 3/4 7-la  !

3/4.7.3- REAC10R CORE ISOEATION COOLING SYSlEM.................. B 3/4 7-la j 3/4.7.4 SNUBBERS............................................... B 3/4 7-2 I 3/4.7.5 SEALED SOURCE CONTAMINATION............................ B 3/4 7-3 j 3/4.7.6 FIRE SUPPRESSION SYSlEMS............................... B 3/4 7-4 l I

3/4.7.7 FIRE RATED ASSEMBLIES.................................. B 3/4 7-4 i t

i 3/4.7.8 MAIN TURBlHE BYPASS SYS1EM............................. B 3/4 7-5 l v

3/4.8 ELECTRICAL POWER SYSTEMS ,

i 3/4.8.1,3/4.8.2,and 3 3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONS11E POWER i OlSTRIBUTION SYSTEMS................................... B 3/4 8-1 i 3/4.0.4 ELECTRICAL EQUIPMENT PR01ECTIVE DEVICES................ B 3/4 8-3 3/4.9 REFUEllNG OPERATION $

- - i 3/4.9.1 REACTOR MODE SWITCH.................................... B 3/4 9-1

{t

. 3/4.9.2 INSTRUMENTA110N........................................ B 3/4 9-1 )

3/4.9.3 CONTROL R00 POSil10N................................... B 3/4 9 l 3/4.9.4 DECAY LIME............................................. B 3/4 9-1  !

r 3/4.9.5 COMMUNICATIONS......................................... B 3/4 9-1  !

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, LIMERICK - UNil 1 ni {

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  • DEf!NITIONS i

STAGGERED TEST BASIS i 1.42 A STAGGERED TEST BASIS shall consist of

a. A test schedule for n systems, subsystems, trains, or other designated i;

components obtained by dividing the specified test interval into n i equal subintervals.  !

b. The testing of one system, subsystem, train, or other designated l component at the beginning of each subinterval. t i

~

THERMAL POWER 1.43 THERMAL POWER shall be the total reactor core heat transfer rate to the f reactor coolant. I i

TURBINE BYPASS SYSTEM RESPONSE TIME 1.43A The TURBINE BYPASS SYSTEM RESPONSE 11ME shall be that time interval from  !

when the turbine bypass control unit generates a turbine bypass valve-flow signal until the turbine bypass valves travel to their required position. l The response time may be measured by any series of seavential, overlapping,  !

or total steps such that the entire response time is measured.  :

UNIDENTiflED LEAKAGE 1.44 UNIDENT!f!ED LEAKAGE sSall be all lenkage which is not IDENT! fled LEAKAGE.

UNRESTRICTED AREA I 1.45 An UNRES1RICTED AREA shall be any area at or beyond the SITE BOUNDARY  !

access to which is not controlled by the licensee for purposes of'  !

protection of individuals from exposure to radiation and radloactive  !

materials, or any area within the SITE BOUNDARY used for residential

  • quarters or for industrial, commercial, institutional, and/or recreational purposes. f VENTILATION EXHAUSl TREATMENT SYSTEM

[

-1.46 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and [

installed to reduce gaseous radioiodine or radioactive material in i particulate form in effluents by passing ventilation or vent exhaust gases '

through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any i effect on noble gas effluents). Engineered Safety feature (ESf) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST  !

TREATMENT SYSTEM components.

VENTipG t

1.47 VENTING shall be the controlled process of discharging air or gas from a F confinement to maintain temperature, pressure, humidity, concentration or j other operating condition, in such a manner that replacement air or gas is .

not provided or required during VENTING. Vent, used in system names, does  :

not imply a VENTING process.

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LIMERICK - UNIT 1 1-8 f

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. POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL-POWER RATIO LlH111HG CONDITION FOR OPERATION 3.2.3 The MlHlHUM CRITICAL POWER RATIO (MCPR) shall be equal-to or greater than the MCPR limit times the Kr both values shown in the CORE OPERATING LIMITS REPORT, provided that the end-of-cycle recirculation pump trip (EOC-RPT) system is OPERABLE per Specification 3.3.4.2 and the main turbine bypass system is OPERABLE per Specification 3.7.8, with; i= (Tave TB1 TA - TB where:

TA = 0.86 seconds, control rod average scram insertion time limit to notch 39 per Specification 3.1.3.3, N

TB

=

0.672+1.65( 1 ) /2(0.016),

n Ng I

i=1 n

I tave " I*I "i i 1 i

n N

I i i=1 n = number of surveillance tests performed to date ir. cycle.

Hj = number of active control rods measured in the i th surveillance test.

Tj = average scram time to notch 39 of all rods measured in the i th survelliance test, and N1

= total number of active rods measured in Specification 4.1.3.2.a.

APPLICABILITY:

OPERATIONAL CONDITION 1, when TilERMAL POWER is greater than or equal to 25% of RATED TilERMAL POWER.

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LIMERICK - UNIT 1 3/4 2-8

4 POWER DISTRIBUTION LIMITS LlHITING CONDITION FOR OPERATION (Continued)

ACTION

a. With the end-of-cycle recirculation pump trip system inoperable per Specification 3.3.4.2, operation may continue provided that, within I hour, HCPR is determined to be greater than or equal to the MCPR limit as a function of the average scram time (shown in the CORE OPERATING LIM 115 REPORT)[0C-RPTinoperablecurve,timestheKrshownintheCORE OPEP.ATING LlHITS REPORT.
b. With MCPR less than the applicable MCPR limit shown in the CORE OPERATING LlH115 REPORT, initiate corrective action within 15 minutes and restore MCPR to within the required limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RA1ED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
c. With the main turbine bypass system inoperable per Specification 3.7.8, operation may continue provided that, within I hour, HCPR is determined to be greater than or equal to the MCPR limit as a function of the average scram time (shown in the CORE OPERATING LlHITS REPORT) main turbine bypass valve inoperabic curve, times the Kr shown in the CORE OPERATlHG LlHITS REPORT.

SURVEILLANCE REQUIRIMENTS 4.2.3 HCPR, with:

a. t = 1.0 prior to performance of the initial scram time measurements for the cycle in accordance with Specification 4.1.3.2, or
b. t as defined in Specification 3.2.3 used to determine the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each scram time surveillance test required by Specification 4.1.3.2, shall be determined to be equal to or greater than the applicable MCPR limit determined from the CORE OPERATING LIMITS REPORT.
a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter completion of a THERMAL POWER increase of at least 10% of RATED THERMAL POWER, and
c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactnr is cperating with a LIMIT!NG CONTROL R0D PATTERN for MCPR.
d. The provisions of Specification 4.0.4 are not applir.able.

LIMERICK - UNil 1 3/4 2-9 iig isi . . . . . . . . . . . . . . . . . -

PtANT SYSTEMS 3/4.7.8 MAIN TURBINE BYPASS SYSTEM LlHITING CONDITION FOR OPERATION 3.7.8 The main turbine bypass system shall be OPERABLE as determined by the _

number of operable main turbine bypass valves being greater than or equal to that specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY: OPERA'i10NAL CONDITION 1, when THERMAL POWER is greater than or equal to 25%~of RATED THERMAL POWER.

ACTION: With the main turbine bypass system inoperable, restore the system to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or take the ACTION required by Specification i 3.2.3.c.

SURVEILLALCE REQUIREMENTS 4.7.8 The main turbine bypass system shall be demonstrated OPERABLE at least once per:

2 a. 31 days by cycling each turbine bypass valve through at least one complete cycle of full travel,

b. refueling cycle by performing a system functional test which includes simulated automatic actuation, and by verifying that cach automatic valve actuates to its correct position, and
c. refueling cycle by determining TURBINE BYPASS SYSTEM RESPONSE TIME to be less than or equal to the value specified in the CORE OPERATING LIMITS REPORT.

a LIMERICK - UNIT 1 3/4 7-33 l

f '

PLANT SYSTEMS BASES 3/4 7.8 MAIN 1URBINE BYPASS SYSTLM -

The required OPERABILITY of the main turbine bypass system is consistent with the assumptions of the feedwater controller failure analysis in the cycle specific transient analysis.

The main turbine bypass system is required to be OPERABLE to limit peak pressure -

in the main steam lines and te maintain reactor pressure within acceptable limits during events that cause rapid pressurization such that the Safety Limit MCPR is not exceeded. -With the main turbine bypass system inoperable, continued operation is based on the cycle specific-transient analysis which has been performed for the ,

feedwater controller failure, maximum demand with bypass failura.

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LIMERICK - UNIT 1 B 3/4 7-5 {

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INDEr OEFINITIONS .

SECTION 1 DEFINITIONS (Continued) PAGE [

i 1.22 MEMBER (S)-Of THE PUBLIC.......................................... 1 i 1.23 MINIMUM CRITICAL POWER RAT 10..................................... 1-4 l

1.24 0FFSITE DOSE CALCULATION MANUAL.................................. 1-4 1.25 OPERABLE - OPERABILITY........................................... 1-4 r i

1.26 OPERATIONAL COH91T10N - CON 0lT10N................................ 1-4 e

1.27 PHYSICS TESTS.................................................... 1-4 i s

1. 28 PRE f $URE BOUNDARY LE AKAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 5 l 1

1.29 PRIMARY CONTAINMENT INTEGRI'Y.................................... 1-5  ;

1.30 FnusJSS CONTROL PR0 GRAM.......................................... 1-5 I i

1.31 PURGE - PURGING.................................................. 1-5 [

t 1.32 RATED THERMAL'P0WER.............................................. 1-6  !

1.33 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY................ 1-6 i 1.34 REACTOR PROTECTION SYSTEM RESPONSE TIME................... ,..... 1-6  !

1.35 REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY............,..... 1-6 .

I 1.36 REPORTABLE EVENT................................................. 1-7 '

1.37 R0D DENSITY......................................................

.s 1-7 .

t 1.3B SHUTDOWN MARGIN.................................................. 1-7 *

1. 3 9 S I T E B 0V N D AR Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 7 l r

1.40 (0eleted)........................................................ 1-7 l-1.41 SOURCE CHECK..................................................... 1-7

1. 42 STAGG E RE D T E ST BAS I S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 f s
1. 4 3 T H E RM A L P 0W E R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 8 1.43A TURBINE BYPASS SYSTEM RESPONSE TIME............................. 1-8  ;

P 1,4 4 U N I D E N T I F I E D L E AK AG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -8  ;

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LIMERICK - UNIT 2 ii i

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INDEX .

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS  !

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SECTION _ _ PAGE i PLANT ~ SYSTEMS (Continued) {

3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - COMMON I SYSTEM.................................................... 3/4 7-6 I

3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM...................... 3/4 7-9 .

i 3/4.7.4 SNUBBERS.................................................... 3/4 7-11 ,

i figure 4.7.4-1 Sample Plan 2) For Snubber i Functional Test........................ 3/4 7-16  !

3/4.7.5 SEALE0 SOURCE CONTAMINATION................................ 3/4 7-17 3/4.7.6 FIRE SUPPRESSION SYSTEMS  !

Fire Suppression Water System.............................. 3/4 7-19 l Spray and/or Sprinkler Systems............................. 3/4 7-22  ;

1 C02 Systems............................................ 3/4 7-24 .

Halon Systems.............................................. 3/4 7-25 f Fire Hose Stations......................................... 3/4 7-26 ,

Table 3.7.6.5-1 Fire Pose Stations.................... 3/4 7-27 Yard Fire Hydrants and Hose Cart Houses.................... 3/4 7-29 Table 3.7.6.6-1 Yard Fire Hydrants and Hoce ,

Cart Houses............................ 3/4 7-30  ;

3/4.7.7 FIRE RATED ASSEMBLIES....................................... 3/4 7-31 j 3/4.7.8 MAlH TURBINE BYPASS SYSTEM.................................. 3/4 7-33 l 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. Sources - Operating................................... 3/4 8-1 Table 4.8.1.1.2-1 Diesel Generator Test  !

Schedule............................ 3/4 8-8  !

A.C. Sources - Shutdown.................................... 3/4 8-9 l 3/4.8.2 D. C. SOURCES i

0. C. Sources - Operating.................................. 3/4 8-10  :

LIMERICK - UNIT 2 xiv .

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?

?

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. - - .. - .. .=. . -- -

f-INDEX BASES l:

SECTION PAGE t

CONTAINMENTSYSTEMS(Continued) i 3/4.6.3 PRIMARY CONTAINMENT-lSOLA110N VALVES................... B 3/4 6-4  !

3/4.6.4 VACUUM REllEF.......................................... B 3/4 6-4  ;

3/4.6.5 SECONDARY CONTAINMENT.................................. B 3/4 6-5 I 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL................. P 3/4 6-6 f 3/4.7 PLANT SYSTEMS i 3/4.7.1 SERVICE WATER SYSTEMS - COMMON SYSTEMS................. B 3/4 7-1 (

3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - l COMMON SYSTEM............................................ B 3/4 7-1 j 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.,................ B 3/4 7-la f 3/4.7.4 SHUBBERS.........,.....................................

B 3/4 7-2 [

3/4.7.5 SEALED SOURCE CONTAMINATION............................ B 3/4 7 3 r

3/4.7.6 FIRE SUPPRESSION SYSTEMS............................... B 3/4 7-4 3/4.7.7 FIRE RATED ASSEMBLIES..................................

B 3/4 7-4 l t

3/4.7.8 MAIN TURBINE BYPASS SYSTEM............................. B 3/4 7-5 l 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and t i

3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONSITE POWER j DISTRIBUTION SYSTEMS................................... B 3/4 8-1 >

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................ B 3/4 8-3  !

3/4.9 -REFUELING OPERATIONS r

3/4.9.1 REACTOR MODE SWITCH.................................... B 3/4 9-1 i 3/4.9.2 INSTRUMENTATION........................................ B 3/4 9-1  :

3/4.9.3 CONTROL R00 POSIT 10N................................... B 3/4 9-1 f 3/4.9.4 DECAY TIME............................................. B 3/4 9-1  !

3/4.9.5 COMMUNICATIONS......................................... B 3/4 9-I f l

LIMERICK - UNIT 2 xxl

DEFINITIONS STAGGERED TEST BASIS 1.42 A STAGGERED TEST BASIS shall consist of:

i

a. A test schedule for n systems, subsystems, trains, or other designated components obtained t,y dividing the specified test interval into n equal subintervals. -  ;
b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval, ,

THERMAL POWER

  • i 1.43 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM RESPONSE TIME 1.43A The TURBlWE BYPASS SYSTEM RESPONSE TIME shall be that time interval from '

when the turbine bypass control unit generates a turbine bypass valve flow signa 7 until the turbine bypass valves travel to their required position.

  • The response time may be measured by any series of sequential, overlapping, I

or total steps such that the entire response time is measured. '

UNIDENTIFIED LEAKAGE 1.44 UNJMNTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.  ;

UNRESTRICh d AREA 1.45 An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive -

materials, or any area within the SITE B0UNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.  ;

r -

VENTILATION EXHAUST-TREATMENT SYSTEM ,

1.46 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and ,

installed to reduce gaseous radioiodine or radioactive material in  !

particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters fer the purpose of removing iodines or particulates-from the gaseous exhaust stream prior to~the  ;

release to the environment (such a system is not considered to have any ,

effect on noble gas effluents). Engineered Safety Feature (ESF)

  • atmospheric cleanup systems are not considered to be VENTILATION EXHAUST -

TREATMENT SYSTEM components.

l VENTING 1.47 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is l not provided or required during VENTING. Vent, used in system names, does ,

not imply a VENTING process.  !

i  :

LIMERICK - UNIT 2 1-8 I

PO!!ER' DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO  :

LIMITING CONDITION FOR OPERATION  !

li 3.2.3 -The MINIMUM CRITICAL POWER RATIO (MCPR) shall be coual to or greater than l the MCPR limit. times the.Kr both values shown in the CORE OPERATING LIMITS REPORT, provided that the end-of-cycle recirculation pump trip (E0C-RPT) system l 1s OPERABLE per Specification 3.3.4.2 and the main turbine bypass system is OPERABLE per Specification 3.7.8, with:

T t = L ave TB) ,

TA - TB ,

where:

TA = 0.86 seconds, control rod average scram insertion  ;

time limit to notch 39 per Specification 3.1.3.3, e i

Ng TB

=

0.672+1.65( )ij(0.016), f n

Ng I  ;

i=1 i n

{

I  ;

T ave

" i"I "I i T l

n N

I $

i=1 r

i n = number of surveillance tests performed to date in cycle, .

Ni

= number.of active control rods measured in the i th surveillance test, Tj = average scram time to notch 39 of all rods measured  !

in the i th surveillance test, and N1

= total number of active rods measured in Specification  !

4.1.3.2.a. i I

APPLICABILITY OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to l 25% of RATED THERMAL POWER. I LIMERICK - UNIT 2 3/4 2-8  !

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) )

ACTION

a. With the'end-of-cycle recirculation pump trip system inoperable per r Specification 3.3.4.2, operation may continue provided that, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, MCPR is determined to be greater than or equal to the MCPR limit as a function of the average scram time shown in the appropriate figure in the CORE OPERATING LIMITS REPORT, for EOC-RPT inoperable curve, times the ,

Kr shown in the CORE OPERATING LIMITS REPORT.

With MCPR less than the applicable MCPR limit shown in the CORE OPERATING :

b.

LIMITS REPORT, initiate corrective action within 15 minutes and restore ,

MCPR to within the required limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER  !

to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, g

c. With the main turbine bypass system inoperable per Specification 3.7.8, ,

operation may continue provided that, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, MCPR is determined .

to be greater than or equal to the MCPR limit as a function of the  !

average scram time (shown in the CORE OPERATING LIMITS REPORT) main turbine bypass valve inoperable curve, times the Kr shown in the CORE -

, OPERATING LIMITS REPORT. .

1 SURVEILLANCE REQUIREMENTS

?

4.2.3 HCPR, with:

a. T = 1.0 prior to performance of the initial scram time measurements .

for the cycle in accordance with Specification 4.1.3.2, or i

b. T as defined in Specification 3.2.3 used to determint the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each scram time surveillance test required by Specification 4.1.3.2, ,

shall be determined to be equal to or greater than the applicable MCPT. limit  !

determined from the appropriate figure in the CORE OPERATING LIMITS REPORT times the Kr shown in the CORE OPERATING LIM 115 REPORT. ,

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ,
b. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL F0WER, And  ;
c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITlHG CONTROL R00 PATTERN for MCPR. i
d. The provisions of Specification 4.0.4 are not applicable. l l

i l LIMERICK - UNIT 2 3/4 2-9  ;

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4 PLANT SYSTEMS ~  !

-3/4.7.8 MAIN TURBlNE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION 3.7.8 The main turbine bypass system shall be OPERABLE as-determined by the number of' operable main turbine bypass valves being greater than or equal to that  ;

specified in the CORE OPERATING LIMITS REPORT. ,

1 APPLICABILITY: OPERATIONAL CONDITION -1, when THERMAL POWER is greater than or l equal to 25% of RATED THERMAL POWER.

ACTION:- With the main turbine bypass system inoperable, restore the system to i OPERABLE status within 1 heur or take the ACTION required by Specification  :

3.2.3.c. i SURVElLLANCE REQUIREMENTS f i

4.7.8 The main turbine bypass system shall be demonstrated OPERABLE at least once [

per:

}

a. 31 days by cycling each turbine bypass valve'through at least one  ;

complete cycle of full travel, j

b. refueling cycle by performing a system functional test which includes [

simulated automatic actuation, and by verifying that each automatic valve  ;

actuates to its correct position, and j t

c. refueling cycle by determining TURBINE BYPASS SYSTEM RESPONSE TIME to be j less than or equal to the value specified in the CORE OPERATING LIMITS
  • REPORT.

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LIMERICK - UNIT 2 3/4 7-33 (

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~ PLANT-SYSlEMS ,

BASES l 3/4 7.8 MAIN TURBINE BYPASS SYSTEM l The required OPERABILITY of the main turbine bypass system is consistent with the j assumptions of the feedwater controller failure analysis in the cycle specific '

--transient analysis.  ;

The main turbine bypass system is required to be OPERABLE to limit peak pressure )

in the main steam lines and to maintain reactor pressure within acceptable limits -i during events that cause rapid pressurization such that the Safety Limit MCPR is  !

not exceeded. With the main turbine bypass system inoperable, continued operation I is based on the cycle specific trarsient analysis which has been performed for the i feedwater controller failure, maximum demand with bypass failure. i f

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LIMERICK - UNIT 2 B 3/4 7-5

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