ML20080C756

Proposed Tech Specs 4.3.2.2,4.7.1.2.1 & Bases for Spec 3/4.7.1.2 for Afs

ML20080C756
Person / Time
Site:	Callaway
Issue date:	12/09/1994
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20080C755	List: ML20080C753 ML20080C756
References
NUDOCS 9412200123
Download: ML20080C756 (20)

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'A' 13/4.'3.2 ' ENGINEERED SAFETY Ft.ATURES ACTUATION SYSTEM INSTRUMENTATION :

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},IMITING CONDITION FOR OPERAT!s '

3 3.3.2L The Engineethd Safety Features'.*stustionisystem (ESFAS)'instrumentatica '

. channels and interlocks shown'in Table 3.3-3 shall: be OPERA 8LE with their Trip-

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-Sutpoints set' consistent with the values shown'in the Trip Setpoint column of.

f, j Table 3.3-4 end with RESPONSE TIMES as shown in Table 3.3-S.-

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'APPLICA81LITY:.As shown in Table 3.3-3.-

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With an ESFAS' Instrumentation or Interlock Trip Setpoint les's

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conservative.than the value shown in the Trip Setpoint. column.

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but'more conservative than the value shown in'the Allowable Value column of Table 3.3-4' adjust the Setpoint consistant with the, Trip, Setpoint value.

' b.

With~ an ESFAS Instrumentation or Interlock Trip Setpoint less

.j conservative than the value shown in the Allowable Values' column of lable 3.3-4, either:

Adjust the Setpoint consistent with the Trip Setpoint value of ";.

1.

Table 3.3-4 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 Lwas' satisfied for the.affected channel, or 2.

Declare the channel inoperable and apply'the applicable ACTION statement requirements of Table 3.3.3 until the channel is :

restored to OPERA 8LE status with its Setpoint adjusted consistent 3

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.with.the Trip Setpoint value.

Equation 2.2-1 Z + R M S f,TA-

.r Where:

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Z = The value from Column Z of Table 3,3-4 for the affected-u i"

channel,;

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R = The "as measured" value (in percent span) of rack error for tie affected channel.

l S = Either the "as measured" value (in percent span) of the sensor error,'or the value-from Column S (Sensor Error) of Table 3.3-4 for-the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel.

c.

With an ESFAS instrumentation channel or interlock' inoperable,. takeithe

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ACTION shown in Table 3.3-3.

zSURVE LLANCE REQUIREMENTS I

4.3.2.1 Each ESFAS instrumentation channel'and interlock and the ' automatic i

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actuation logic and relays shall be demonstrated OPERABLE by the perfonnance of the ESF AS Instrumentation Surveillance Requirements specified in Table 4.3-2. -

4.3.2.7 the LNGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS functio

a. hall be demonstrated to be within the limit at least once per 18 months Each-Lest shall include at least one train such that both' trains are tested a least once per 36 munths'and one channel per function such that all channels are tested ~

'at least once per N times 18 months where N is the total number of redundant chan-l nels in a specific ESFAS function as shown in the " Total No. of Channels" Column

- i nf fable 3.3-3.

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I PLANT! SYSTEMS'

. AUXILIARY FEEDWATER SYSTEM N, ;

g LIMITING CONDITION FOR OPERATION

' ACTION:-

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Withstwo auxiliary feedwater pumps: inoperable, be in at.least HOT.

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STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT' SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />..

f.

' With three auxiliary feedwater pumps inoperable. immediately.

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r initiate corrective action to restore at.least-one' auxiliary

'feedwater pump to.0PERABLE status as soon as possible.

iSURVEILLANCEREQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall.be demonstrated OPERABLE:-

m At least once per ays on a STAGGERED TEST BASIS by:

1) Verifying that each motor-driven pump develops a ' discharge pressure of greater than or equal.to 1535 psig on recircula-

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tion flow when tested pursuant to Specification 4.0.5;

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2) Verifying that the. steam turbine-driven pump develops a discharge pressure of greater than or equal to 1625 psig at a flow of greater than or equal to-120 gpm.when the secondary-steam supply pressure is greater than 900 psig.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3; l

1 6

CALLAWAY - UNIT 1 3/4 7-4a Amendment No. 55

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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Al_je sf 5 e g 3l days j

4F IVerifying f each non-automatic valve in the flow path that f.0 L is not.10...

. sealed, or otherwise _ secured in position is in I -

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J its correct position; and 4

Verifying that each automatic valve, other thari AL-HV-30, 31, 2-)

32, and 33, in the flow path is in' the fully open position whenever the Auxiliary Feedwater System is placed in automatic. >,

M6Ve 45 control or when above 10% RATED THERMAL POWER.

. pc 3/9 -4t c..br At least once per 18 months during shutdown by:

1)

Verifying-that automatic valves AL-HV-30, 31, 32, and 33 in the ESW supply to the auxiliary feedwater pumps actuate to their full open position upon receipt of an Auxiliary Feedwater Pump Suction Pressur - w test signal, Verifying that ea )

ipt of an Auxiliary Feedwater Actuation ry feedwater pump starts as designed 2) automatically upon ce test signal, and

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3)

Verifying that each auxiliary feedwater motor-operated discharge valve limits the flow to each steam generator from the motor-driven pump to less than or equal to 320 gpm.

4. 7.1. 2. 2 An auxiliary feedwater flow path shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by verifying normal flow to at least two steam generators from one auxiliary feedwater pump.

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CALLAWAY - UNIT 1 3/4 7-5 Amendment No. 53 l

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a PLAN 1 SYSTEMS BASES SAFETY VALVES (Continued)

' Power Range Neutron' Fln-High Trip Setpoint 'for four loop 109 =

operation, Total' relieving capacity of all safety valves per steam:

X =

.line in lbs/ hour, and y

Y = ' Maximum telieving capec.itv of any one safety valve in lbs/ hour.

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The GreRABILITY of -the Auxiliary Feedwater System ensures that the Reactor Coolac.: aystem can-be cooled down to less than 350*F from normal o e ti cor.<*ftions in the event of a total loss-of-offsite pow ir,u+ = h A. W a r Testing of each electric motor-driven auxiliary feedwater pump on a f uas beut 4* aae Sha p

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j orifice recirculation flow and ensuring a discharge pressure of greater than

,prM[fr%jQity_nt.sactLa'=ath; W, tier.;; ;f the.,Pumf th ---

t m = tot or eoual to 1535 osia ver of 1221 psig.t:

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.::d::tcr fl'ow of 575 gpm at-f

............The steam-driven auxiliary feedwater is capable of delivering a total fed ;.t$ flow of 1145 gpm at FJr s ur's of IJ1LpsigAe-

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Th1s gapac1T.y is sufficient to ensure that adequate feedwater flow is avai able to remove decay heat and reduce the:

Reactor Coolant System temperature to less than 350*F when the RHR System may be placed into operation.

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minisium water volume ensures that sufficient water is available to maintain the RCS at' HOT STANDBY conditions for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss-of-offsite power and then a cooldown to 350*F at 50*F per hour. The contained water volume limit includes an allowance for water not usable because of tank discharge ling location or other physical characteristics.

3/4. 7.1. 4 SPECIFIC ACTIVITY.

The limitations on Secondary Coolant System specific activity ensure that the resultant uf tsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture, this dose alsu includes the effects of a coincident 1 gpm reactor to secondary tutw leak in the steam generator of the affected steam line. These values are 4

consistenL with the assumptions used in the safety analyses.

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.,p INSTRUMENTATION

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LIMITING CONDITION FOR OPERATION 3.3'.2 The' Engineered Safety Features Actuation System (ESFAS) instrumentation em'

channels and. interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints

set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

1 APPLICABILITY: As'shown in Table 3.3 3.

ACTION:

a.

With' an ESFAS instrumentation or Interlock Trip Setpoint less conservative than ?

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the value shown in the Trip Setpoint column but more conservative than the value shown in the A!!owable Value column of Table 3.3-4 adjust the Setpoint consistent with the Trip Satpoint value.

b.

With an ESFAS Instrumentation or Interlock Trip Setpoint less conservativ' than e

the value shown in the Allowable Values column of Table 3.3-4,'either:

1.

Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.

Declare the channelinoperable and apply the applicable ACTION statement R

requirements of Table 3.3.3 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.

Equation 2.2-1 Z + R + S 5 TA I

Where:

Z = The value from Column Z of Table 3.3-4 for the affected channel.'

R = The "as measured" value (in percent span) of rack error for the affected channel.

S = Either the "as measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 3.3-4 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel, c.

With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.

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SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by the performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.

4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months (the provisions of Specification 4.0.4 are not applicable for response time testing of the steam turbine-driven auxiliary feedwater pump for entry into MODE 3). Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels

• Column of Table 3.3-3.

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J PLANT SYSTEMS c)

AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATidN ACTION: -

Continued :

f e, ; With two auxiliary feedwater pumps inoperable, be in at.least HOT STANDBY) 1 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within~ the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.,.

f.

With three auxiliary feedwater pumps inoperable, immediately initiate.

corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

a l

p SURVEILLANCE REQUIREMENTS i

4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

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a.

At least once per 31 days by:

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1) Verifying that each non-automatic valve in the flow path that is not i

locked, sealed, or otherwise secured in position is in its correct position:

and

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2) Verifying that each automatic valve, other than AL-HV-30,31,32, and

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33, in the flow path is in the fully open position whenever the Auxiliary

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Feedwater System is placed in automatic control or when above 10%.

I RATED THERMAL POWER.

l b.

At least once per 92 days on a STAGGERED TEST BASIS by:

1) Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1535 psig on recirculation flow when tested pursuant to Specification 4.0.5:

2) Verifying that the steam turbine-driven pump develops a discharge pressure of greater than or equal to 1625 psig at a flow of greater than or equal to 120 gpm when the secondary steam supply pressure is greater l

than 900 psig. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3:

CALLAWAY - UNIT 1 3/4 7 4a Amendment No. 55

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PLANT SYSTEMS r

SURVEILLANCE REQUIREMENTS (Continued) 4

c. : A't least once per 18 months ' uring shutdown by:

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1) ? Verifying that automatic valves AL-HV-30,'31; 32,'and 33 in the E9W.

supply to the auxiliary feedwater. pumps actuate to their full open position.

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.upon receipt of an Auxiliary Feedwater Pump Suction Pressure-Low test :

signal,-

2) Verifying that each motor driven auxiliary feedwater pump starts as ;

designed automatically upon receipt of an' Auxiliary Feedwater Actuation test signal, and i

3). Verifying that each auxiliary feedwater motor-operated discharge valve -

limits the flow to each steam generator from the motor-driven pump'to.

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less than or equal to 320 gpm.

d.. At least once per 18 months by verifying that the steam turbine-driven auxiliary feedwater pump starts as designed automatically upon receipt of an.-

Auxiliary Feedwater Actuation Test signal (the provisions of Specification.

4.0.4 are not applicable for entry into Mode 3).

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4.7.1.2.2.

An auxiliary feedwater flow path shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2

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by verifying normal flow to at least two' steam generators'from'one auxiliary feedwater.

pump.

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H 1109.=. Power. Range Neutron Flux-High Trip Setpoint for four loop operation (

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. Total rel:eving capacity of all safety valves per steam line in Ibs/ houri and -

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'X

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s b'

. Y

= Maximum relieving capacity of any one safety valve in Ibs/ hour.E 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM

, The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor -

Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a totalloss-of-offsite power in conjunction with a feedwateru line break to one steam generator.

Testing of each electric motor driven auxiliary feedwater pump on a fixed orifice Erecirculation flow and ensuring a discharge pressure of greater than or equal to 1535.

psig verifies the capability of each pump to deliver a total pump flow of.575 gpm at s' steam generator pressure of 1221 psig.' The steam-driven auxiliary feedwater pump is capable of delivering a total pump flow of _1145 gpm at a steam generator pressure of..

1221' psig. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350*F when the RHR System may be placed into operation.

L 3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with steam discharge to the atmosphere concurrent with totalloss-of-offsite power and then a cooldown to 350*F at 50 F per hour. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture. This dose also includes the effects of a coincident.1 gpm reactor to secondary tube leak in the steam generator of

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the affected steam line. These values are consistent with the assumptions used in the e

safety analyses, u

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1 aAFETY EVALUATICIf,

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tcj (Thi'sLamendmentLapplication requests airevision to. Technical 7 1

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• f Specifications ; (TS ) c 4. 3. 2 ; 2 ', L 4 '. 7.1.'2.1; J and : Bases Section N

j,y 3 /4 '. 7.1. 2 ;. Specification'4;3.2'.2sisJbeingLrevised to'..

l Did provideian exception tol Specification 4.0.4ifor: entry:into, j

h y ;b 1 Mode 134for response time 1 testing of the Turbine Driven?..

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Auxiliary Feedwater l Pump (TDAFP)'.. " Specification; 4.7.1.2.11'

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..is being revised ~as follows:

- (1) ' The frequencyi of ; testing '.

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't Leach > auxiliary feedwaterupump will be~ reduced'fromionce,per #

31/ days to onceiper 92 ; days, (2)f Specification 4.741'.2.1.b.~2

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,.4 surveillances will be revised to remove the requirementithatN r

the: surveillance for : the 'TDAFP be performed only during y :

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p shutdown, s and'. (3)' Specification 4. 7.1.2.1.b.2 will be -

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1 modified to provide an exception t'o Specification ~4~.0.'4.for RC,

entry.into Mode

3 for verifying the TDAFP automaticallyJ starts.upon~ receipt of an Auxiliary Feedwater Actuation test' signal.

The. Bases'for Specification 3/4.7.1.2'will be modified.to clarify the performance requirements of-the

~

. Auxiliary Feedwater Sys:em (APWS).

L Backgrround

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The Auxiliary Feedwater System'(AFWS) supplies feedwater to j

the steam generators to remove decay. heat from.the reactor-X coolant; system upon the loss of normal-feedwater supply.

The system is served by two motor-driven pumps and one steam 1

X, turbine-driven pump.:

To ensure that the three auxiliary'feedwater pumps sre capable of' performing'their intended safety function, Callaway Technical SpecificationsJrequire the operability of V

the. pumps to be demonstrated. - In part, Surveillance Requirement 4.7.1.2.1.b 2 ensures that the TDAFP.will-automatically start in the event an/ Auxiliary Feedwater'

. Actuation Signal (AFAS) is generated because of a plant transient.

This surveillance is performed _once per.18 months'at shutdown.

In addition,.all three pumps'are' tested at least once per 31 days per: Specification'4.7.1.2.1.a..

Surveillance Requirement-4.7.1.2.1.a.2 includes an exception' a'

to-the provisions of Specification 4.'0.4 for' entry into Mode

'3 for the TDAFP.

Technical Specification 4.0.4 states,'

" Entry into an OPERATIONAL MODE or other specified condition 3:

'shall not.be made unless the Surveillance. Requirement (s)

associated'with a Limiting Condition for Operation has been

performed within the stated' surveillance interval or as-e' otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL MODES as required'to comply with ACTION requirements."

The exception to the requirements of Specification 4.0.4 allows suitable. testing f'

. conditions to be established for the TDAFP.

It is'necessary

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T surveillanceitestiing to prevent; damag'e to the. pump and to

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<>n ensureitheivalidity ofEthe~ surveillance.,;However 1

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Surveillance'RequirementL4.7.1.2'.1.b.2idoes notrhave"a aimilar provision. 1This;appearsLto have:been ani ;

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l administrative oversight.

'A~similar; condition existsJfor-ij m

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-Surveillance Requirement 14'.3.2.2Vas/it?relateelto the?'

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. turbine-drivenLauxiliaryifeedwater pump-testing 1to supporc:

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(Engineered; Safety Features.(ESP). response time. testing.

.j 1Therefore,<a^ modification'to Surveillance 4 Requirement'

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,/413.2.2Lis:also' required.-

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Jq3,./ stated previously, the Surveillance Requirement-to verify, f

the. auxiliary feedwater pumps automatically 1 start upon:

< receipt ;of' an AFAS (4 ;7.1'.2.1.b.2).is required to be...

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. performed at shutdown.- For.the TDAFP, the.requirementcto:

9 perform the surveillance'only at shutdown-is. inconsistent with the exception'to specification 4 0.4 since suitable j~

. steam! conditions'are not established until Mode 3 (Hot Standby) is attained. -Therefore, Specification 4.7;1.2.1.b.2 willlbe modified to remove'the "at shutdown" requirement for the TDAFP.

3 The three. auxiliary feedwater pumps are currently' required _

to be tested' pursuant to Specification 4.7.1.2.1.a.at least

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once per 31 days.

This amendment request also proposes-to modify Specification 4.7.1.2.1.a-to lengthen the interval..

between Auxiliary Feedwater.' pump surveillance tests from'31 days to 92 days..This adopts the y

Standard Technica1LSpecifications~ provisions of-the improved =

-< Westinghouse Plants (NUREG 1431).and incorporates the recommendations of NRC-d Generic Letter 93-05,.Line-Item Technical Specifications

?

Improvements'to Reduce Surveillanc'e Requirements for Testing H

During Power Operation.

This will eliminate approximately.

1 24 pump tests and the associated out-of-service time per

'l 4-year.

This: change has been evaluated for impact on the-Callaway Probabilistic Risk Assessment Model.

This change j

will slightly reduce.the:Callaway Plant core damage.

frequency (CDF) and will eliminate unnecessary pump. starts H

and decrease the possibility of human: errors associated with

, restoration from testing.

This change.is compatible with' Callaway's operating experience since all. Auxiliary

'Feedwater pumps consistently meet the' acceptance criteria for ASME Section XI testing when tested pursuant to Specification 4.0.5.

'(

Bases Section 3/4.7.1.2 is to be changed to clarify the assumed conditions the Auxiliary Feedwater. pumps are required to function under and the performance requirements G

for each pump.

The Auxiliary Feedwater Safety System Functional Assessment (SSFA 94-02 (AL)) identified errors in'

'l

-the. wording in the Technical' Specification bases.

The' bases

'j are to be. modified to clarify that the 575 GPM and 1145 GPM 1

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M flow values 'are. t'ot'al:gyggt flows 1(not' flow to the ' entrance

]

Cy' H

Lof c the; steam _ generators).'. iThis fis' consistentiwith Final fZ~+

iSafetyqAnalysis1 Report Table.10.4-12 which describes;the; 1

,b'

" components.10These(values include ~an: allowance-for.

4 WW KrecirculationsflowJto the CST.: The' Motor +DrivenlAuxiliary.

Peedwater Pumps (MDAFP's)s have' a minimum recirculation ~ flow.

a

("'.,s

" of?75.GPM backito the'CSTJand;theLTDAFP has:a minimum -

N recirculation flow of 120?GPM back to'the. CST withLan.

"p ( '

s

'additionali25 GPM being recirculated'through.an integral

,' d Ti

?bearingicooler.i This results in nominaliflow' rates.of 5002 N.

GPMffor,the,MDAFP'soand 1000 GPMJfor theiTDAFP to theisteam

.cd' i;

Lgenerators..:The FSAR Main.Feedwater LinejBreakl analysis-1

" assumes'563 GPM'is deliveredLto three intact steam-m

' generators with 4701GPM'being supplied'by the TDAFP;and 93..

. J, GPM provided fromLone running'MDAFP.

Nominalicooldown y

values"for the Auxiliary Feedwater System'are estimated at'

'250fGPM perLateam generator.

-Bases section 3/4.7.1.2 is also changed toiclarifyithat the associated pressure'is-intended to be' steam generator.

pressure. -The pressure of:1221 psig. corresponded to a steam i

, generator pressure equivalent _to thel setting of the lowest Main-Steam safety valve plus accumulation (1185'psig'+ 3%).

. Union Electric has proposed an amendment to the operating

. license via letter ~ULNRC-3069_on September.12,.1994 (NRC TAC No. M90476) which would allow the' steam generator safety

. valves to;be'modeled without accumulation.. However, the valven would be modeled with a-plus.-3%, minus'1%'setpoint, tol erance.

Therefore, the maximum steam generator pressure

'l psig remains unchanged.

These changes are editorial n

c

[

oo and simply' correct errors in the original wording..

L wo Lluw values are design values found in the FSAR and'in design documentation.

Evaluation L

The proposed changes to Technical Specifications'4 3.2.'2, 4.7.1~.2.1, and the Bases for Specification 3/4.7.1.2 do not involve an unreviewed safety question because operation of the'Callaway. Plant with the changes'would nots-1.

Increase the probabilityjof occurrence or the-

consequences of an accident or malfunction of equipment-important to safety' evaluated previously~in the safety.

analysis report.

The changes proposed by this Technical' Specification?

l amendment do not affect the performance parameters'of the' Auxiliary Feedwater System (AFWS).

The changes proposed involve a decrease in the frequency offpump testing from once per 31 days to once'per 92. days ss-recornmended by NRC Generic Letter 93-05 and reflected'

~

in NUREG'1431-(T/S 4.7.1.2.1.a).

This change will decrease the out-of-service time of the AFWS due to m

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C.nOtestingA.lThis;changeiwill ileo dhcEease the7numbe',of(

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ors V cwill;therefore decrease th'e probability:of a

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Lrestoration' error: rendering the systemLincapable.of=

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The pumpsEwillibez.

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'JP required to' meet the-samefacceptance criteria <and;willL y

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a

%n:.g~h 3 i 1XI.; 1 Asistated : earlier, i the loverallieffectJ s a : slight-i Ni c'

,w : decrease;ini he CDF for.Callaway.3iTheseiproposed?

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,s VJ l changes /willcalsoLeliminate an?inconsistencyc among?

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' Specifications:4.-7.1.2;1.b.21and'4'.3.2.2 and" l:.

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.~ Specification ; 4. 7.1~. 2.1.a. 2 ' regarding i an ' exception, to '.'f

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9!

,e 18pecification"4'.0.'4; for entry :into Mode r3"fors the! L W -

n TM

'TDAFP.1 tThe, methodology-and acceptance: criteria;of' l

surveillance' testing will not be changed...The' ability:

4 of the-AFWS:to: perform:itsgintended' function during y

accident condition ~s willocontinue'toibe demonstrated-l E

sM via surveillance testing..The proposedichanges to the" Technical ~ Specifications.do not'affectuany-accident:

initiators for.any accident' evaluated in the. Safety.

Analysis Report.

TheaBasesLchanges.are corrections toL errors which have no-effect on any accident: initiators:

1 nor equipment failure modes.

0 4

2.

Create a possibility.for an accident,or. malfunction of

'l a.different' type than any previously evaluated in the-s 1

Safety Analysis Report.

The proposed;Technicalt specification changes do not' modify any equipment nor a

x f-

create.any'potentialLaccident initiators. ;The; proposed 1

change herein'of potential' interest is the exception toi

~m i

specification 4.0.4'for entry into Mode.3.for TDAFP.

j response' time testing:and: auto-start testing.

This allowance is already recognized via Specification l

.l L4.7.~1.2.1.a.2.and NUREGt1431',nStandard Technical' i

Specifications - Westinghouse Plants.

No new'fallure j

modes.are created since the method and acceptance'

>4 criteria for surveillance' testing are unchanged.

3 '.

Reduce the margin of' safety as defined in'the basis [for l

any technical: specification'.- The Bases for' 1

Specification 3/4.7.1.2 are to'be clarified to g,

correctly state the design flow and pressure paraneters-a for the AFWS.

No plant design, changes are involved and the method and manner of' plant operation remain'the.

same.

The specific ~ surveillance test methodology and acceptance criteria remain unchanged.

.l ww Based on the previous discussions as well as those presented h

1

'in the Significant Hazards-Evaluation, the proposed-Technical-Specification changes do not adversely affect or.

-endanger the health or safety of the general public or-

' involve a significant safety. hazard.

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Attachment'4 Sionificant Hazards Evaluation

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?-SIGNIFICSMT EAEARDB EVALUATI M fi m,

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This Jamendment applicationfrequests. a revisionL to? Technical 3 c

x, Specifications <(TS)d4.3.2.2, 4.7.1.2.1,;andi. Bases lSection l 3 /4. 7.1. 2.; ; Specification ' 4 '. 3'. 2. 2 iis ? being ; revised toj provide)annexception'to Specification;4.0.4ifor entry [into Mode 3. for eresponset time testing :of the: Turbine ' Driven '

Auxiliary 1Feedwater Pump;(TDAFP).

SpecificationL4;7.1.2.1'. '

c,

.-is being revised as'follows.:

L(1) TheNfrequency'of Etesting

>"3j-jeach: auxiliary'feedwater pump will'be1 reduced from-once peri J

31' days 3tolonce:per 92 < days, :(2):: Specification 4 '.7.1;2.1.b.'2 y

m surveillances.will'.beLreviseduto remove the' requirement?thatL theesurveillance for.the"TDAFP be performed)only during,,

a s

.chutdown, and (3).. Specification 4.7.1.2.1.b.2 will-be o

.i modified to provide:an exception:to SpecificationJ4.0.4 for;.7' entry into Mode 3 for. verifying ~the TDAFP autom 7 ically;.

5 starts upon receipt'of;anl Auxiliary:Feedwater Actuation 1 test':

4 signal.

The Basesifor. Specification 3/4.7.1.2 will be.

modified to clarify the performance. requirements--of'the.

Y Auxiliary Feedwater System.(AFWS).

The proposed Technical Specification changes do not involve-a^

a significant hazards consideration per.101CFR50.92"because,

Loperation of Callaway P17.nt with the. changes would' nots, c

1.

Involve'a signif3 cant. increase in the probability or; consequences of an accident previously evaluated.L The Callaway Final' Safety Analysis Report has.beencreviewed:

and been found to:be unaffected by these proposed

>j changes.

The changes proposed by this. Technical.

Specification amendment do not. affect.theoperformance parameters of the-Auxiliary Feedwater System?(AFWS).

The' changes proposed, involve a decrease in.the~

frequency-of pump; testing from once per.31 days to once per 92 days as. recommended by NRC Generic: Letter 93-05 and reflected in NUREG 1431'(T/S 4'.7.1.2.1.'a).

This change will decrease.the out-of-service time of the AFWS due to. testing.

This change will also decrease the number of component manipulations performed on':the system and will'therefore decrease the. probability of a restoration error rendering theLsystem incapableEof; perfoming its intended function.

t The pumps will be required to meet the same' acceptance criteria and will; continue to be;. monitored: as required by ASME Section XI. lAs stated earlier, the overall effect.is a slight decrease in the CDF for Callaway.

2 These proposed changes will also eliminate an inconsistency among Specifications'~4.7.1.2.1'.b.2 and-4.3.2.2 and: Specification 4.7.1.2.1.a.2 regarding an exception to specification 4.0.4 for. entry into Mode 3-

",~

for the TDAFP.

The methodology and acceptance criteria of~ surveillance testing will not be changed.

The L

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?during accidenticonditions willicontinue.toLbe' m:f./i

! demonstrated via surveillanceltesting.: :Th'e propos'ed. '

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m cchangeaxto thetTechnicalsSpecificationsido;.nottaffect m

anyl accident 1initiatorscfor any..accidentievaluatedFin!

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' the Final'. Safety Analysis: Report J(FSAR);..- TheLBases :

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'changesfare correctionsrto errors,which'have'noieffacts

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Lon:Lany Lacaident initiators nor equipment:ffailureimodes.

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Create' the possibility ofD a' new oridifferent kind Lof"..

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' accident from any.previouslyl evaluated? ?The-proposed-yV Technical (Specification changes dofnot modify;any n'_,

Lequipment nor create:any potentialiaccidenteinitiators.-

4,

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1The, proposed change hereinJof;potentialqinterest is;the:-

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-exception to Specificationf.4.0.4:forl entry;into Mode 3>

e '~'

^

'_.m for;TDAFP. response time'testingfand auto-start testingL ThisLallowance'is alreadyLrecognizedivia Specificationi L,M

'4.7.1;2.1.a.2"andiNUREG 14311 Standard Technical 4

p specifications - Westinghouse ~' Plants.,

r

,Y 3.

Involve a significant: reduction in a' margin;of safety.'

The4 Bases for-Specification 3/4.47.i.2lare to'be-clarified to correctly state.theidesign' flow and.

~

pressure.parametersifor the AFWS.

No' plant. design'.

changes are involved in any of.the proposed changesiand-the. method.and manner of.plantLoperation; remain the-

~r same.

TheLspecific surveillance. test-methodology and"

+

acceptance' criteria remain unchanged.

'As discussed above,-the proposed) change!does-not involvela

significant'. increase in the probability or consequences of m

an-accident previously evaluated or.; create the possibility-of a new or-different kind'of accident from any;previously-revaluated.._These changes do not' result'in a significant reduction in a margin of: safety.

Therefore,.it has been determined'thatLthe proposed changes do;not involve a

.significant hazards. consideration.-

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.j Environmental Consideration 4

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$p ENVIBMMENTAL CMSIDERATIM,

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This;amendmentiapplicatibn' requests a revision;to! Technicall

($

(Specificationsf(TS)n4.3.2.2,f4.7.1.2.1, and Bases...Section W!

J 3 /4. 7.1.' 2.. ' Spe'cification 14. 3. 2. 2 llis :.being :. revised to; L provide an: exception toLSpecification'4.0.4 forientryLinto'

/8,

Mode

3 :! for; response 1 time; testing 1of the iTurbine~ Driven:

/?*'

. Auxiliary Feedwaterf Pump i:(TDAFP).'.<, Specification. 4.7.1.2.1:

1 LisLbeing revised,as follows:

(1).The frequency of testing.

ac, '

each auxiliary:feedwater pump will-be reduced from'once;perc J 31 days ' to.once per ; 92 ' days,. -(2) : Specification.4.7.1.2'.1.b.2 L surveillances1will-be revised to: remove'the,requirementsthatj the: surveillance'for'the'TDAFP be-performed only during:

J shutdown,; and (3)( Specification. 4.7.1.2.1.b.2..will be ;

Lmodified;to provide.an' exception to Specification 4'.0'4?for' entry into Mode 3 for. verifying the TDAFP(automatically..

starts upon receipt of an Auxiliary Feedwater Actuation: teeth M,

signal.

The' Bases'for Specification 3/4.7.1.2'.will be modified.to clarify the performance requirements'offthe.

Auxiliary Feedwater' System-(AFWS).

, s, L

'The proposed amendment' involves changes with respect {to the

' c use.of. facility. components. located within the restricted areas as defined in 10:CFR Part 20.

Union' Electric has

~ determined thatithe proposed amendment involves no; significant hazards consideration, no significant'. increase in'the amounts nor significant change in the' types of any effluents that may be released-offsite, and no significant' increase.in individual ~or? cumulative' occupational 1 radiation j

'q.

exposure.

Accordingly,z the proposed amendment-meets the.

]

eligibility criteria for categorical exclusion set forth in M

10 CFR51.22 (c) L (9).

Pursuant to 10 ' CFR51.22 (b;. no

'2 environmental impact statement or. environmental assessment

.t need be prepared in connection with the, issuance'of?this amendment.

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