ML20247N134

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Proposed Tech Spec 3/4.1.3.4 Revising Control Element Assembly Drop Time Limits,Introducing Use of Arithmetic Average Drop Time & Addition of Table 3.1-1
ML20247N134
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 07/31/1989
From:
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13303B109 List:
References
NUDOCS 8908020290
Download: ML20247N134 (15)


Text

_ _ _ _ - - -

REVISED 6/30/89 htEACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full lengtn (shutdown and regulating) CEA drop time, from a withdrawn position greater than or equal to 145 inches, shall be less than or equal to 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:

T,yg greater than or equal to 520*F, and a.

b.

All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

With the drop time of any full length CEA determined to exceed the above limit, be in at least HOT STANDBY within six hours.

g SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:

a.

For all CEAs fcilowing each removal and reinstallation of the reactor vessel head, b.

For specifically affected individuals CEAs following.any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.

At least once per refueling interval.

l 0

SAN ONOFRE-UNIT 2 3/4 1-20 AMENDMENT NO. 73 8908020290 89o73j fDR ADOCK O$000361 FDC

e, j

i REACTIVITY CONTROL SYSTEM i

t

. BASES-

'MOYABLE CONTROL ASSEM LIES (Continued)

The CPCs provide protection to the core in the event.of.a large misalignment (greater than or equal to 19 inches) of a CEA by app 3ying appropriate. penalty factors to the calculation to account for the misaligned CEA.. However, this misalignment would cause distertion of the core power distribution. This distribution.may,. in turn, have a significant effect on 1), the available SHUTDOWN MARGIN,. 2) the time dependent long tem power distributions relative to those used in generating LCGs and LSSS setpoints, and 3) the ejected CEA worth used in the safety analysis. Therefore, the ACTION. statement associated with the large misalignment of a CEA requires a prompt realignment of.the misaligned CEA.

The ACTION statements applicable to miseligned or inoperable CEAs include-requirements.to align the OPERABLE CEAs in a given group with the inoperable CEA.. Conformance with these alignment requirements bring the core, within a short period.of time, to a configuration consistent with that assumed in

. generating LC0 and LSSS setpoints. However, extended operation with CEAs significantly "nserted in the core may lead to perturbations in 1) local burnup, 2) peaking factors and 3) available shutdown margin which are more adverse than the conditions assur:!d to exist ir the safety analyses and LCO and LSSS setpoints determination. Therefore, time limits have been imposed on

. operation with inoperable CEAs to prec1ede such adverse conditians from dev11oping.

Operability of at least two CEA position indicator channels is required to determine CEA positions and thereby ensure compliance with the CEA alignmen:,

and insertion limits. The CEA " Full In" and " Full Out" limits provide an addi-tional independent means for determining the CEA positions when the' CEAs are at

.either their fully inserted or fully withdrawn positions. Therefore, the ACTION j-statements applicable to inoperable CEA position indicators permit continued J

operations when tha positions of CEAs with inoperable position indicators can be verified by the " Full In" or " Full Out" limits. Setting the "RSPT/CEAC Inoperable" addressable constant in the CPC's to indicate to the CPC's that one or both of the CEAC's is inoperable does not necessarily constitute the inoper-ability of the RSPT rod indications from the respective CEAC.

Operability of the CEAC rod indications is determined from the cormal surveillance.

CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verificatit.ns required if an automatic monitoring channel is inoperable.

Tht>Je verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

TN maximum CEA drop time restriction is consistent with the assumed CEA r.op time used in the safety analyses. Nessurement with T,yg greater than or equal to 520*F and with all reacter coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

SAN ONOFRE-UNIT 2 B 3/4 1-4 AMEN 0 MENT NO. 32 MAR 01 985

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%EACTIVITY tONTROL SYSTEMS -

-CEA' DROP TIME LIMITING' CONDITION FOR OPERATION 3.1.3.4 The full. length:(shutdown and regulating) CEA arithmetic average and the individual CEA' drop times, from a withdrawn

. position. greater than or equal to.145 inches, shall be within.at

.least one of the limit sets of Table 3.1-1.

lThe drop time shall'

-be..from when. power is interrupted.to.the CEA drive mechanism until the CEA reaches its 90 percent'inserLion position.with:

T,,, greater than or equal to 520 F,. and

-a.

b..

All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTIQH:

a.'

.With either the arithmetic average CEA drop time OR any individual.CEA drop. time determined to exceed the limits,. restore the CEA drop time to within the limits prior to proceeding to Modes 1 or 2.

SURVEILLANCE REQUIREMENTS 4.1.3.4.1 The CEA; drop-time of full length CEAs shall be demons-l trated through measurement prior to reactor criticality:

a.

For all CEAs following each removal and reinstallation of the vessel head, b.

.For all-CEAs following any maintenance on or modifica-l tion to the CEA drive system which could-affect the drop time of those specific CEAs, and c.

At least once per refueling interval.

4.1.3.4.2 For each CEA drop time measurement performed under surveillance 4.1.3.4.1, confirm that the appropiate CPC and COLSS addressable constant adjustments that conservatively bound both the arithmetic average CEA drop time AND the slowest individual CEA drop time measured have been made prior to reactor critica-lity.

l SAN ONOFRE-UNIT 2 3/4 1-20 AMENDMENT NO. __

. -g.

TABLE 3.1-1 CEA Drop Time Limits (Seconds)

SET AVERAGE INDIVIDUAL I

5 3.0 5 3.2 II 5 3.2 s 3.4 III

$ 3.4 1 3.6 i

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l

. SAN ONOFRE-UNIT 2 3/4 1-20a AMENDMENT NO. _

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REACTIVITY CONTROL SYSTEM-

~ BASES MOVABLE CONTROL ASSEMBLIES (Continued) b The CPCs provide protection to the c' ore in the event of a large misalignment (greater than or equal to 19 inches) of a CEA by applying e

' appropriate penalty factors to the calculation to account for the misaligned CEA. However,-this misalignment would cause distortion of the core power distribution. This distribution say, in turn,- have a significant effect on

1) the.available SHUTDOW MARGIN, 2) the time dependent long term power -

distributions relative'to those used in generating LCOs and LSSS setpoints, and 3) the ejected CEA t.,rth used in the safety analysis. ' Therefore, the ACTION statement associated with the large misalignment of.a CEA requires a prompt realignment of the misaligned CEA.

The ACTION statownts applicable to misaligned or inoperable CEAs include-requirements to align the OPERABLE CEAs in a given group with the inoperable CEA..Conformance with these alignment requirements bring the core, within a short period.cf time, to a configuration consistent with that assumed in 4

generating.LCO and LSSS setpoints.

However, extended operation with CEAs significantly inserted in-the core may lead to perturbations in 1) local burnup, 2) peaking factors and 3) available shutdown margin which are more adverse than.the conditions assumed to exist in the safety analyses and LCO and LSSS setpoints. determination. Therefore, time-limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing.

Operability of at least two CEA position indicator channels is required to

.detemine CEA positions and thereby ensure compliance with the CEA alignment and insert!on limits.

The CEA " Full In" and " Full Out" limits provide an addi-tional independent means for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions.

Therefore, the ACTION statements applicable to inoperable CEA position indicators permit continued operations when the positions of CEAs with inoperable position indicators can be. verified by the " Full In" or " Full Out" limits.

Setting the "RSPT/CEAC Inoperable" addressable constant in the CPC's to indicate to the CPC's that one or both of the CEAC's is inoperable does not necessarily constitute the inope y

ability of the RSPT rod indications from the respective CEAC.

Operability of

/

the CEAC rod indications is determined from the normal surveillance.

CEA positions and "PERABILITY of the CEA position indicaters are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more friquent verifications required if an auumatir, monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

/&WmaWrr p^

1

-The-max 4r CEA drep t4as-restHct% 4s-coLsi te" wit d CE" t

4 ' ment wi asure grea er an or

-drep-

,yg equal to 520*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

SAN ONOFRE-UNIT 2 B 3/4 1-4 AMEN 0 MENT NO. 32 MAR 01985

7-_ ; ~

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' Replace section of' Bas'es, onlpage B3/4 1-4, indicated as (A) to

~

~

.q.

, read:.

.The? arithmetic ~ average CEA~ drop time restrictions are-consistent with the: CEA drop times 'used in the' safety

~

analysis.

The maximum ~. individual CEA drop time restrictions.

are used to limit the CEA drop. time distributions about the

. average.. ~ COLSS and CPC addressable constant:ndjustrents have'been conservatively-determined to. accommodate these CEA drop time' combinations.

The~ appropriate set;of adjustment

. factors that. bound:both the. arithmetic average CEA drop time and the slowest individual >CEA drop time are-installed prior

-to' criticality following the performance of the CEA' drop'

~

time' surveillance.

1 i

i I

1

___________________________________________a

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. 1-4

'. '.f' ATTACHMENT C

---_...__w_._______.__m_.._-________

t REVISED 6/30/8

)

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' REACTIVITY CONTROL SYSTEMS

{

CEA DROP TIME LIMITING CONDITION FOR OPERATION The individual full length (shutdown and regulating) CEA drop time, 3.1.3.4 from a withdrawn position greater than or equal to 145 inches, shall be less than or equal to 3.2 seconds from when the electrical power is interru::ted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:

T,y greater than or equal to 520'F, and a.

b.

All reactor coolant pumps operating.

APPLICABILITY: MODES I and 2.

ACTION:

1 With the drop time of any full length CEA determined to exceed the a.

above limit, 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 />.

es b

SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:

For all CEAs following each removal and reinstallation of the a.

reactor vessel head, For specifically affected individuals CEAs following any maintenance b.

on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and At least once per refueling interval.

c.

l l

O b

AMENDMENT NO. 61 SAN ONOFRE-UNIT 3 3/4 1-20 l

l REACTIVITY CONTROL SYSTEMS BASES MOVA8LE CONTROL ASSEMBLIES (Continued)

The CPCs provide protection to the core in the event of a large misalignment (greater than or equal to 19 inches) of a CEA by applying appropriate penalty factors to the calculation to account for the misaligned CEA. However, this misalignment would cause distortion of the core power 1

-distribution. This distribution may, in turn, have a significant effect on 1).the available SHUTDOWN MARGIN, 2) the time dependent long tens power distributions relative to those used in generating LCOs and LSSS setpoints, and 3) the ejected CEA worth used in the safety analysis.

Therefore, the ACTION statement associated with the large misalignment of a CEA requires a prompt realignment af the misaligned CEA.

The ACTION statements applicable to misaligned or inoperable CEAs include-requirements to align the OPERABLE CEAs in a given group with the inoperable CEA. Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in l

generating LC0 and LSSS setpoints.

However, extended operation with 'CEAs i

significantly inserted in the core may lead to perturbations in 1) local I

burnup. 2) peaking factors and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCD and LSSS setpoints determination. Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from l

developing.

Operability of at least two CEA position indicator channels is required to determine CEA puttions and thereby ensure compliance with the CEA L

alignment and insertion Ifmits. The CEA " Full In" and " Full Out" limits provide an additional independent means for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions.

Thereforn, the ACTION statements applienble to inoperable CEA position

. indicators permit continued operations when the positions of CEAs with inoperable position indicators can be verified by the " Full In" or " Full Out" limits. Setting the "RSPT/CEAC Inoperable" addressable constant in the CPC's to indicate to the CPC's that one or both of the CEAC's is inoperable does not necessarily constitute the inoperability of the RSPT rod indications from the I

respective CFAC. Operability af the CEAC rod indications is determined from the nonnal surveillance.

CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inopere,ble.

These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

The maximum CEA drop time restriction is consistent with the assumed CEA drop time used in the safety analyses.

Measurement with T,yg greater than or equal to 520"F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experiences g g du?ing a reactor trip at operating conditions.

SAN ONOFRE-UNIT 3 8 3/4 1-4 AMENDMENT N0. 21

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i ATTACHMENT D i

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REACTIVITY CONTROL; SYSTEMS

.CEA DROP TIME

' LIMITING CONDITION'FOR' OPERATION 3'.1.3.4 The full length (shutdown'and regulating) CEA arithmetic

. average and.thenindividual'CEA drop times, from a withdrawn position. greater than or equal to.145 inches,~shall-be within-at

'least one of;the limit sets of Table 3.1-1.

The drop time shall be from when power is interrupted to-the CEA drive nechanism until'the CEA reachesiits 90. percent insertion. position with:

a.

Ti,f greater than or equal to 520 F,.and b.

All reactor coolant' pumps operating.

L APPLICABILITY: MODES 1 and 2.

i ACTION:-

a.;

With either the arithmetic average CEA drop time OR any individual CEA drop time determined to exceed the

-limits, restore the CEA drop time to within the limits prior to proceeding to Modes 1 or 2.

. SURVEILLANCE REQUIREMENTS 4.1.3.~4.1' The'CEA drop time of full length CEAs shall be demons-l

-trated through measurement prior to reactor criticality:

a.

For all CEAs following each removal and reinstallation of~the vessel head, b.

For all CEAs following any maintenance on or modifica-l tion to the'CEA drive system which could affect the drop time of those specific CEAs, and I

c.

At least once per refueling interval.

4.1.3.4.2-For each CEA drop time measurement performed under surveillance ~4.1.3.4.1, confirm that the appropiate CPC and COLSS addressable constant adjustments that conservatively bound both

.the arithmetic average CEA drop time AND the slowest individual CEA drop-time measured have been made prior to reactor critica-Ility.

)

1 l

I l

SAN.ONOFRE-UNIT 3 3/4 1-20 AMENDMENT NO. __

1

(.

3--,.

.y--------

j

~-

' TABLE 3.1-1 CEA Drop Time Limits (Seconds)

SET AVERAGE INDIVIDUAL I

$ 3.0 5 3.2 II' i 3.2

$ 3.4 III s 3.4 s 3.6 i

t

)

SAN ONOFRE-UNIT 3-3/4 1-20a AMENDMENT NO. _

...a______

, l{ r.

H"

]

9-REACTIVITY CONTROL' SYSTEMS BASES' MOVA8LE CONTROL ~ ASSEMBLIES (Continued)

The CPCs provide protection to the core in the event of a large misalignment (greater than or equal to 19 inches) of a CEA by applying appropriate penalty factors to the calculation to account.for the misaligned CEA.' However, this. misalignment would cause distortion of the core power distribution. This distribution may, in turn, have a significant effect on

1) the available SHUTDOWN MARGIN, 2) the time dependent long tem power distributions relative to those used in generating LCOs and LSSS setpoints, and 3) the ejected CEA worth used in the safety analysis.

Therefore, the H

ACTION statement associated with the large misalignment of a CEA requires a prompt realignment of the misaligned CEA.

The-ACTION statements applicable to misaligned or inoperable CEAs include-

. requirements to align the OPERABLE CEAs in_a given group with the inoperable

- CEA.'

Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LC0 and LSSS setpoints. However, extended operation with 'CEAs significantly inserted in the core may lead to perturbations in 1) local burnup,,2) peaking factors and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LC0 and LSSS setpoints determination. Therefore, time limits have been imposed on operation with' inoperable CEAs to preclude such adverse conditions from developing.

Operability of at least two CEA position indicator channels is required to determine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits. The CEA " Full In" and " Full Out" limits provide an additional independent means for determining the CEA positions when

~

the CEAs are at either their fully inserted or fully withdrawn positions.

Therefore, the ACTION statements applicable to inoperable CEA position

' indicators permit continued gerations when the positions of CEAs with inoperable position indicators can be verified by the " Full In" or " Full Out" limits.

Setting the "RSPT/CEAC Inoperable" addressable constant in the CPC's i

to indicate to the CPC's that one or both of the CEAC's is inoperable does not f

necessarily constitute the inoperability of the RSPT rod indications from the o

respective CEAC. Operability of the CEAC rod indications is determined from

/j the normal surveillance.

CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the applicable

'LCO's are satisfied.

W 3 M m W n v e W v-

-The-maaimus CE.8 d ;: t4ee-restrist49n g jM uped-CEA g-op-tire v asuremen w grea r th W 6r

,yg equal to 520*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times-experiencehAR 0 1 1985 during a reactor trip at operating conditions.

SAN ONOFRE-UNIT 3 B 3/4 1-4 AMENDMENT No. 21

Replace section of Bases, on page B3/4 1-4, indicatsd as (A) to read:

The arithmetic average CEA drop time restrictions are consistent with the CEA drop times used in the safety analysis.

The maximum individual CEA drop time restrictions are used to limit the CEA drop time distributions about the average.

COLSS and CPC addressable constant. adjustments have been conservatively determined to accommodate these CEA drop time combinations.

The appropriate set of adjustment factors that bound both the arithmetic average CEA drop time and the slowest individual CEA drop time are installed prior to criticality following the performance of the CEA drop time surveillance.

_ - - _