ML20248B455

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Proposed Tech Specs Revising Requirements Re Movable Control Assemblies
ML20248B455
Person / Time
Site: Callaway 
Issue date: 08/02/1989
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20248B453 List:
References
ULNRC-2055, NUDOCS 8908090238
Download: ML20248B455 (8)


Text

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Attachment ~3 to ULNRC-2055 l 9 )*

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PROPOSED TECHNICAL SPECIFICATION CHANGES j

l Specification 3/4.. 3 l

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8908090230,890802

-PDR ADOCK 05000483 PDC p

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l. 50 0 L.

REACTIVITY CONTROL' SYSTEMS REVIS:0N 3

3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP' HEIGHT LIMITING CONDITION FOR OPERATION 3'.1.3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within t 12 steps (indicated position) of their group step counter demand position.

APPLICABILITY: MODES 1* and 2?.

J:ruerb A se-J

^ ACTION:

a.

"ith ::: Or ::r: full-1:ngth r:d; /n per ble du: t: b;ing i;;;;;ble-

: re:elt Of ::::::17: 'riction er :::h:nic:1 int rfertn;; er

-4tnewn t: b: untripp;ble, petermine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.

"ith ;;r; th;n ;n; full-length r:d insp;rable Or miseligned fre; the greur step ::ent:r d ;:nd p :ition by ::rt then : 12 steps (ir.diceted peritien), pe in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

"ith One ful'-1:ngth.:d tripp:ble but in:p;r:bl: de: te-eatteee

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j eth;r th:n ddre:: d by f;CTION :., abeve, er misaligned *rer its-greep :tep crenter d-ind height by mere than 12 step: (indic:ted p :iti:n), POWER OPERATION may continue provided that within 1 hour:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod ir declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within 12 steps of the inoperable red while maintaining the rod sequence and insertion limits of Figure 3.1-1.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

I a)

A reevaluation of each accident analysis of Table 3.1-1 is I

performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; i

"See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

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CALLAWAY - UNIT 1 3/4 1-14 AUG 2 0 3S5 l

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REVIStoy

.RfACIIVITY CONTROL SYSTEMS p

e LIMIIING COND1110N FOR OPERATION

' ACTION'(Continued) c)

A power distribution map is obtained from the movable incore detectors and F (2) and F are verified to be q

g within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next nour and~

within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Neutron Flux Trip 5etpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

A C.Ti o nJ :

6.

Rcsbre 4ha. [rioperdk r o h

+o o p rdlt sb.4vs ddh.h 12.

hoves or be,in hot STAND BN W'i+h *n tha, A Cwt.

(.e h o urs.

StlRVEILLANCE REQtilREMENTS 4.1'. 3.~ 1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per L2 hours except during time intervals when the rod position

- deviation monitor is. inoperable. then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1. 3.1. ? Each full-length rod not fully inserted in the core-shall be determined to be OPERABLE by movement of at least 10 steps in any one direction

.it least once per 31 days.

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CAILAWAY a llN I i 1 3/4 1-15

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REVIStoy 1

m i-REACTIVITY CONTROL SYSTEMS

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BASES j

MOVABLE CONTROL ASSEMBLIES (Continued)

In5ctl B

  • The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER. These restrictions provide assurance of fuel rod integrity during continued operation. In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with T,yg greater than or equal to 551*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.

Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal t; asis 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 f requent verifications required if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the~ applicable LCOs are satisfied.

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I Technical Specification Inserts Insert A The ACTION to be taken is based on the cause of inoperability of control rods as follows:

ACTION More Than CAUSE OF INOPERABILITY One Rod One Rod 1.

Immovable as a-result of excessive (a)

(a) friction or mechanical interference or known to be untrippable.

2.

Misaligned by more than + 12 steps (c)

(b)

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(indicated position) from its group j

step counter demand height or from any other rod in its group.

3.

Inoperable due to a rod control urgent (d)

(d) failure alarm or other electrical problem in the rod control system, but trippable.

Insert B For purposes of determining compliance with Specification 3.1.3.1, any immovability of a control rod initially invokes ACTION statement 3.1.3.1.a.

Subsequently, ACTION statement 3.1.3.1.a may be exited and ACTION statement 3.1.3.1.d invoked if either the rod control urgent failure alarm is illuminated or an electrical problem is detected in the rod control system.

The rod is considered trippable if the red was demonstrated OPERABL:. luring the last performance of Surveillance Re, trement 4.1. 3.1.2 and met the rod drop time criteria of Specification 3.i.

during the last performance of Surveillance Requirement 4.1.3.4.

It0 FO R/W AT I o t0 D eJ LY, THE.sfr j

3 P A 66.5 SHow TH E PRoPoiEb

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REACTIVITY CONTROL SYSTEMS.

CIM M6E s.crJcoRPoRATED INTO 3/4.1.3 MOVABLE CONTROL ASSEMBLIES

ce is7 me, TECH MIC A L SPECi F8( ATibV5 Fog m a i e i c An o W Pup.Pos Es.

GROUP HEIGHT Pq e.

IoE 3 LIMITING CONDITION FOR OPERATION 3.1.3.1 All full-length shutdown anc control rods shall be OPERABLE and i

positioned within i 12 steps (indicated position) of their group step counter demand position.

i APPLICABILITY: MODES J* and 2*,

ACTION: The ACTION to be taken is based on the cause of inoperability of control rods as follows:

h ACTION More Than CAUSE OF INOPERABILITY One Rod One Rod i

1.

Immovable as a result of excessive (a)

(a) friction or mechanical interference l

or known to be untrippable.

2.

Misaligned by more than i 12 steps (c)

(b)

(indicated position) from its group step counter demand height or from any other rod in its group.

{

(d) 3.

Inoperable due to a rod:controli. urgent._

_ (d) ;__

failure alarm or other electricale om I

problem in the rod control system, but l

trippable.

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ACTION a. - Deteemine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION b. - Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION c. - POWER OPERATION may continue provided that within 1 hour:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod The sequence and insertion limits of Figures 3.1-1.

THERMAL POWER level shall be restricted pursuant to Specifica-tion 3.1.3.6 during subsequent operation, or "See special Test Exceptions Specifications 3.10.2 and 3.10.3.

- UNIT 1 3/4 1-14

IN F O R M ATt o rd O N LM n

REACTIVITY CONTROL SYSTEMS Pa p 2 of 3 LIMITING CONDITION FOR OPERATION ACTION (Continued)

The rod is declared inoperable and the SHUTDOWN MARGIN 3.

requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that; a)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; j

c)

A power distribution map is obtained from the movable intore detectors and F (Z) and F,g are verified to be n

within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and I

d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Neutron Flux Trip 5etpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

Restore the inoperable rods to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or ACTION d.

be in HOT STAN9BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS

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4.1.3.1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions at

. least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the rod position deviation monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each full-length rod not fully inserted in the core shall~be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

- UNIT 1 3/4 1-15

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REVISION 1

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, REACTIVITY CONTROL SYSTEMS Py e -

a, J 2 V-

. BASES l

L NOVA 8tE CONTROL ASSEMBLIES (Continued)

For purposes of determining compliance witE Spec'ification 3.1.3.1, any.

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immovability of a control rod initially invokes ACTION. statement 3.1.3.1.a.

" Subsequently, ACTION statement 3.1.3.1.a may be exited and ACTION statement l

3.1.3.1.d invoked 'if either the rod control urgent failure alarm is-

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illuminated or an electrical problem is detected in the rod control system.

~ The rod is considered trippable if the rod was demonstrated OPERABLE during l

the last performance of Surveillance Requirement 4'.1 3,1.2 ' and met the rod drop time criteria of Specification 3.1.3.4 during the -last performance of L

Surveillance. Requirement 4.1.3.4 The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.. Misalignment of a rod requires measurement of. peaking factors and a restriction in THERMAL POWER. These restrictions provide assurance of fuel rod integrity during continued operation. In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

The maximum tod drop time.estriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with T,yg greater than or equal to 551*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.

r Control rod positions and OPERABILITY of the' rod position indicators are -

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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 me.?toring channel is inoperable.

These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.

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