ML20097D634

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Proposed Tech Specs Re AFW Sys
ML20097D634
Person / Time
Site: Callaway Ameren icon.png
Issue date: 02/09/1996
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20097D621 List:
References
NUDOCS 9602130108
Download: ML20097D634 (11)
v • d • e


Text

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'NSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION l i

LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation 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. l APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-4 adjust the Setpoint consistent with the Trip Setpoint value,
b. With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than 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 channel inoperable and apply the applicable ACTION statement requirements of Table 3.3.3 until the channel is restored to OPERABLE status within its Setpoint adjusted consistent with the Trip Setpoint value.

Equation 2.2-1 Z + R + S s TA Where:

I - 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 I95ERT the ACTION shown in Table 3.3-3. W re h 6th SURVEILLANCE REQUIREMENTS gr 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 lehst once per 18 months.

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 I 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.

CALLAWAY - UNIT 1 3/4 3-13 Amendment No.104 l 9602130100 960209 PDR ADOC% 05000483 P PDR . f

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

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Insert *A" l (the provisions of Specification 4.0.4 are not applicable '!

1; for the steam turbine-driven auxiliary feedwater pump for .

entry _into MODE 3. The ENGINEERED SAFETY FEATURES RESPONSE  !

TIME testing for the-steam turbine-driven auxiliary feedwater pump is required to be' completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l j after attaining 2900 psig in all steam generators).  ;

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1 i 4

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. . _ _ _ - -_ _, _ -_ ,- ___ . _ __- w-m___z_.____- _ _ ~ -

,- PLANT SYSTEMS

' 5 AUXILIARY FEEDWATER SYSTEM i ]

LIMITING CONDITION FOR OPERATION l

ACTION _: Continued l

e. With two auxiliary feedwater pumps inoperable, be in at least HOT l l 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 -l initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS f

4.7.1.2.1 Each auxiliary fee water pump shall be demonstrated OPERABLE:

  • 92 i

-+,. At least once per ays on a STAGGERED TEST BASIS by:

b

1) Verifying that each motor-driven pump develops a discharge insu4 pressure of greater than or equal to 1535 psig on recirc.uja-tion flow when tested pursuant to Specification 4.0. %4

) .n m

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3/q 1-5 1

2) Verifying that the steam turbine-driven pump develops discharge pressure of greater than or equal to 1625 psig at a flow of greater than or equal to 120 gpm ter t'.: ::::r.o ry stcr supply p 05:u e ir greater thea 900 9:i;. h r-provisions .

of Specification 4.0.4 are not applicable for entry into MODE (eqdM h bc com plckel w d D

aq w,.3 r+ce hining 2 9eo ps;3 k 4.ll steam je.ne cd oca - %e 1

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

l

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l ) PLANT SYSTEMS j

! SURVEILLANCE REQUIREMENTS (Continued) j i dIAi[konct[ps 3I hs'EQ

--3M Verifying that each non-automatic valve in the flow path that 6 4 is not locked, sealed, or otherwise secured in position is in g,

)

its correct position; and l

-+) l Verifying that each automatic valve, other than AL-HV-30, 31, L) 32, and 33, in the flow path is in the fully open position >

/ whenever the Auxiliary Feedwater System is placed in automatic i 3)i 7"b control or when above 107 RATED THERMAL POWER.

- # A A '

%- At least once per 18 months during shutdown by:

C,

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 i.

Pump Suction Pressurl-Low signal, M; sin,n  ;

2) Verifying that eacq, auxiliary eedwater pump starts as designed

^ '

automatically upon receipt or an Auxiliary Feedwater Actuation

test signal, and
3) Verifying that each auxiliary feedwater motor-operated discharge i

.9}

- valve limits the flow to each steam generator from the motor- ,

driven pump to less than or equal to 320 gpm. l T

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, l e c& A. %Iled.n3:
d. Ab \ e u.3 & ona .pe iB men &s h *Mg 4kJ N. sw bd6e drim ^9N*r1 Md" fwp

.si aAy, a.s 14.siyad AMDd-( yon receipt of an )

Ad%,c) R elo. k < Ac.h. J n -tts+ .rpI (9;ma u he. Qa.kcd.

MN Ai h'*f3 AE+t.f ANd56133 Soo y, in ah Shre 30se.<*d* c5 M p r o d M e a.s et he,clet ew 4,o,q gca n.+ a.plte kte. b ** j b4* M. obr 31 A d'  ;

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

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.v' REVIS10y j

. PLANT SYSTEMS

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BASEC SAFETY VALVES (Continued).

109 = Power Range Neutron Flux-High Trip Setpoint for four loop operation, X = Total relieving capacity of all safety valves per steam line in 1bs/ hour, and Y = Maximum relieving capacity of any one safety valve in 1bs/ hour.

. 3/4.7.I.2 AUXILIARY FEEDWATER SYSTEM The NEdABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolar.t system can be cooled down to less than 350*F from no_rmal_ operatinge c c 'i in the event of a total loss-of-offsite power Wcenp4 Mon with c.Mw

, /or#ft ons the. beoor, 4= one Sh .

Testing of each electric motor-driven auxiliary feedwater pumplin a fixed f orifice recirculation flow and ensuring a discharge pressure of greater than

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,e 1t 1535 psic hvea ies ability of each pump to deliver a tota f' 1 :ict:r flow of 575 gpm at ajpressure of 1221 psiD: thi .tl cn ~:? N n,.e . . . a u . , < . .u + - - - - - ' --- m t

- Ubd 5 5b5b b$ $$55 flow of U45 gp'm [t a M A M 1EE [ psia M #TMeJapacity s sufficient to ensure tt --tfrc: :f th: :t:= ;. c. oy...

, t atloequaT.e fee r o T ava11ame to remove cay heat and reduce the p Reactor Coolant System temp rature to I ess than 350' when th

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HR stem may a g be placed into operation. 1 d

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e. g aq ani @f 3/4.7.1.3 CONDENSATE STORAGE TANK @ pakrP W 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 hnurs 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 voluee limit includes an allowance for water not usable because of tank discharge ling location or other physical o characteristics.

3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that i

the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline vilues 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 the affected steam line. These values are

' consistent with the assumptions used in the safety analyses.

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CALLAWAY - UNIT 1 B 3/4 7-2 M --

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Y Attachment 3 Re-typed Technical Speci fi cation pages Page 3/4 3-13 Page 3/4 3-13a Page 3/4 7-4a Page 3/4 7-5 Page B 3/4 7-2 A. .

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'i.

._.. INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation l channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints l set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

.a. With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than ]

the value shown in the Trip Setpoint column but more conservative than the value 1 shown in the Allowable Value column of Table 3.3-4 adjust the Setpoint l

. consistent with the Trip Setpoint value.

b. With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than ,

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 i 4 affected channel, or i 2. Declare the channelinoperable and apply the applicable ACTION statement

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

Equation 2.2-1 Z + R + S s TA  ;

. 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, 1 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.

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. l n

i

CALLAWAY J UNIT 1 3/4 3-13 Amendment No.104 i

s--h-- , w -- -- -,----- -----____---__..__------__---_.---__-_---------._.____-----4

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INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) 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 the steam turbine-driven auxiliary feedwater pump for entry into MODE 3. The ENGINEERED SAFETY FEATURES RESPONSE TIME testing for the steam turbine-driven auxiliary feedwater pump is required to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 2900 psig in all steam generators). Each test shallinclude 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.

CALLAWAY - UNIT 1 - 3/4 3-13a Amendment No.104

3- 1

-A PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION ACTION: Continued

[

e. With two auxiliary feedwater pumps inoperable, be in at least HOT 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 initiate j- corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

4 SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

j

a. - At least once per 31 days by:
1) Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; and
2) Verifying that each automatic valve, other than AL-HV-30,31,32, and
33, in the flow path is in the fully open position whenever the Auxiliary Feedwater System is placed in automatic control or when above 10%

RATED THERMAL POWER.

u

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; and

, 2) Verifying that the steam turbine-driven pump develops a discharge i

pressure of greater than or equal to 1625 psig at a flow of greater than or equal to 120 gpm (required to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 2 900 psig in all steam generators - the provisions of Specification 4.0.4 are not applicable for entry into MODE 3).

4 i

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

s PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

=

- c. 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 Pressure-Low test f signal,
2) Verifying that each motor-driven auxiliary feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal, and
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.

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 (required to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 2 900 psig in all steam generators - the provisions of Specification 4.0.4 are not applicable for entry into MODE 3).

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.

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

i i- (

l PLANT SYSTEMS -

3 BASES-SAFETY VALVES (Continued)

.109 =' Power Range Neutron Flux-High Trip Setpoint for four loop operation, . .;

I X = ' Total relieving capacity of all safety valves per steam line in Ibs/ hour, and Y. = Maximum relieving capacity of any one safety valve in Ibs/ hour.

3/4.7.1.2 - AUXlLIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor 1 Coolant System can be cooled down to less than 350 F from normal operating conditions in the event of a total loss-of-offsite power in conjunction with a feedwater -

line break to one steam generator.

l Testing of each electric motor-driven auxiliary feedwater pump on a fixed orifice

_ ]

' recirculation 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 a ]

steam generator pressure of 1221 psig. Testing the steam turbine-driven auxiliary ,

feedwater pump at greater than or equal to 120 gpm and ensuring a discharge .)

pressure of greater than or equal to 1625 psig verifies the capability of the pump to  ;

deliver a total pump flow of 1145 gpm at a steam generator pressure of 1221 psig.

The capacity of any auxiliary feedwater pump 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.

3/4.7.1.3 CONDENSATE STORAGE TANK 1

The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT l 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 cooldcwn 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 l effects of a coincident 1 gpm reactor to secondary tube leak in the steam generator of '

(L .the affected steam line. These values are consistent with the assumptions used in the safety analyses.

CALLAWAY - UNIT 1 B 3/4 7-2

_ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - .

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