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Proposed Tech Specs Re Control Rod Drive Coupling & Control Rod Operability.Significant Hazards Consideration Encl
	ML20083H328
Person / Time
Site:	LaSalle
Issue date:	01/05/1984
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20083H320	List: ML20083H317; ML20083H328;
References
	7869N, NUDOCS 8401090145
	Download: ML20083H328 (9)
	v • d • e

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' /*r ) Pac REACTIVITY CONTROL SYSTEM Cif 8W d d ON THl$ F/X6 1/4.1.3 CONTROL RODS .

ONTROL ROD OPERABILITY

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LIMITING CONDITION FOR OPERATION

~3.1.3.1 All control rods shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2. ,

ACTION:

a. With one control rod inoperable due to being immovable, as a result of excessive friction or mechanical interference, or known to be untrippable:

1. Within one hour:

a) Verify that the inoperable control red, if withdrawn, is separated from all other inoperable control rods by at least two control cells in 211 directions.

b) Disarm the associated directional control valves ** either:

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust. water isolation valves.

c) Comply with Surveillance Requirement 4.1.1.c.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. Restore the inoperable control rod to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With one or more control rods trippable but inoperable for causes other than addressed ir. ACTION a, above:

1. If the inoperable control rod (s) is withdrawn:

a) Immediately verify:

1) That the inoperable withdrawn control rod (s) is separated from all other inoperable control rod (s) by at least two control cells in all directions, and

2) The insertion capability of the inoperable withdrawn control rod (s) by inserting the control rod (s) at least one notch by drive water pressure within the normal operating range *.

b) Otherwise, insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves ** either:

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves "The inoperable control rod may then be withdrawn to a position no further withdrawn than its position when found to be inoperable.

May be rearmed intermittently, under administrative control, to permit testing

( associated with restoring the control rod to OPERABLE status.

LA SALLE - UNIT 1 3/4 1-3

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QMITINGCONDITIONFOROPERATION(Continued) J ACTION (Continued)

'2. If the inoperable control rod (s) is inserted:

a) Within one hour disarm the associated directional control valves ** either:

i

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves.

i Otherwise, be in at least HOT SHUTDOWN within the next b) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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c. With more than 8 control rods inoperable, be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS l

4.1.3.1.1 The scram discharge volume drain and vent valves'shall be demonstrated OPERABLE by:

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a. At least once per 31 days verifying each valve to be open*, and l

i

b. At least once pec 92 days cycling each valve through at least one complete cycle of full travel.

4.1.3.1.2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERA 8LE by moving ear'-

control rod at least one notch:

a. At least once per 7 days, and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any control rod is immovable as a result of excessive friction or mechanical interference.

4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 4.1.3.2, 4.1.3.4, 4.1.3.5, 4.1.3.6 and 4.1.3.7.

i "These valves may be closed intermittently for testing under administrative l control.

- May be rearmed intermittently, under administrative control, to permit testing

\ associated with restoring the control rod to OPERABLE status. -

LA SALLE - UNIT 1 3/4 1-4 l

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U ~,r l Puc REACTIVITY CONTROL SYSTEM gg g g CONTROL ROD DRIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 5*.

ACTION:

a. In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to its associated drive mechanism:

1. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , either:

a) If permitted by the RWM and RSCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

1) Observing any indicated response of the nuclear instrumentation, and

2) Demonstrating that the control rod will not go to the overtravel position.

b) If recoupling is not accomplished on the first attempt or, if not permitted by the RWM or RSC3 then until permitted by the RWM and RSCS, declare the control rod inoperable

/

and insert the control rod and disarm the associated directional control valves ** either:

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves.

2. Otherwise, be in at 1, east HOT. SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism,'within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , either:

j

1. Insert the control rod to accomplish recoupling' and verify recoupling by withdrawing the control rod and demonstrating that the control rod will not go to the overtravel position, or

2. If recoupling is not accomplished, insert the control rod and disarm the associated directional control valves ** either:

a) Electrically, or l

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b) Hydraulically by closing the drive water and exhaust water l

isolation valves.

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"At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- May be rearmed intermittently, under administrative control, to permit testing l

l' associated with restoring the control rod to OPERABLE status.

l LA SALLE - UNIT 1 3/4 1-11 l

AJ 6 T hf4tG REACTIVITY CONTROL SYSTEM

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SURVEILLANCE REQUIREMENTS , 4.1.3.6 A control rod shall be demonstrated' to be coupled to its drive mechanism by observing any indicated response of the nuclear instrumentation while withdrawing the control rod to the fully withdrawn position and then verifying that the control rod drive does not go to the overtravel position:

a. Prior to reactor criticality after completing CORE ALTERATIONS that could have affected the control rod drive coupling integrity,

b. Anytime the' control rod is withdrawn to the " Full out" position in subsequent'. operation, and

c. Following maintenance on or modification to the control rod or control rod drive system which could have affected the control rod drive coupling integrity.

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LASALLE-UN{T1 ]/41-12

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RAPC7EEh/W b^A7 REACTIVITY CONTROL SYSTEM 3/4.1.3 CONTROL RODS CONTROL ROD OPERABILITY LIMITING CONDITION FOR OPERATION 3.1.3.1 All control rods shall be OPERABLE.-

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a .- With one control rod inoperable due to being immovable, as a result i of excessive friction or mechanical interference, or known to be untrippable: '

1. Within 1 hour:

a) Verify that the inoperable control rod, if withdrawn, is separated from all other inoperable control rods by at least two control calls in all directions.

b) Disarm the associated directional control valves

either:

1) Electrically, or.

2) Hydraulically by closing the drive water and exhaust water isolation valves.

. c) Comply with Surveillance Requirement 4.1.1.c.

2. Otherwise, be in at least HOT SHL. '0WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . ,

3. Restore the inoperable control rod to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With one or more control rods trippable but inoperable for causes other than addressed in ACTION a, above:

1. If the inoperable control rod (s) is withdrawn:

a) Immediately verify:

1) That the inoperable withdrawn control rod (s) is I

separated from all other. inoperable withdrawn control rod (s) by at least two control cells in all directions, and

2) The insertion capability of the inoperable withdrawn control rod (s) by inserting the control rod (s) at least one notch by drive water pressure within the normal

- operating range **.

b) Otherwise, insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves

either:

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status. ,

- The inoperable control rod may then be withdrawn to a position no further withdrawn than its position when found to be inoperable.

3/4 1-3 LA SALLE - UNIT 2

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r}W MCvDQj SGPML1Nc6 Onm REACTIVITY CONTROL SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

2. If the inoperable control rod (s) is inserted:

a) Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months disarm the associated directional control valves

either:

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves.

b) Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification 3.0.4 are not applicable.

3.

c. With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

a. At least once per 31 days verifying each valve to be open**, and

b. At least once per 92 days cycling each valve through at least one complete cycle of full travel.

4.1.3.1.2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required to have their directional c'ontrol valves disarmed electrically or hydraulically shall be demonstrated OPERABLE Ly moving each control rod at least one notch:

a. At least once per 7 days, and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any control rod is immovable as a result of excessive friction or mechanical interference.

4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 4.1. 3. 2, 4.1. 3. 4, 4.1. 3. 5, 4.1. 3. 6, and 4.1. 3. 7.

May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

- These valves may be closed intermittently far testing under administrative control.

LA SALLE - UNIT 2 . 3/4 1-4

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, , b rJ IT 3 OME J rVc w OCD FOR-- R S t= LM o v C Z cn cy REACTIVITY CONTROL SYSTEM CONTROL ROD ORIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*.

ACTION:

a. In OPERATIONAL CCNDITIONS 1 and 2 with one control rod not coupled to its associated drive mechanism:

1. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , either:

a) If permitted by the RWM and RSCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

1) Observing any indicated response of the nuclear instrumentation, and

2) Demonstrating that the control rod will not go to the overtravel position.

b) If recoupling is not accomplished on the first attempt or, if not permitted by the RWM or RSCS then until permitted by the RWM and RSCS, declare the control rod inoperable and insert the control rod and disarm the associated directional control valves ** either:

, 1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , either:

1. Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the control rod and demonstrating that the control rod will not go to the overtravel position, or

2. If recoupling is not accomplished, insert the control rod and disarm the associated directional control valves ** either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water l isolation valves.

c. The provisions of Specification 3.0.4 are not applicable.

"At least each withdrawn control rod. Not applicable to control rods removed l per Specification 3.9.10.1 or 3.9.10.2.

- May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

LA SALLE - UNIT 2 3/4 1-11

,' NIT - &CG l h] C L G O i! D Fe <3- R.ct=te2 cm c.e o a c y REACTIVITY CONTROL SYSTEM SURVEILLANCE REQUIREMENTS 4.1.3.6 A control rod shall be demonstrated ~to be coupled to its drive mechanism by observing any indicated response of the nuclear instrumentation while withdrawing the control rod to the fully withdrawn position and then verifying that the control rod drive does not go to the overtravel position:

a. Prior to reactor criticality after completing CORE ALTERATIONS that could have affected the control rod drive coupling integrity,

b. Anytime the control rod is withdrawn to the " Full out" position in subsequent operation, and

c. Following maintenance on or modification to the control rod or control rod drive system which could have affected the control rod drive coupling integrity.

4 LA SALLE - UNIT 2 3/4 1-12

ATTACHMENT B l

SIGNIFICANT HAZARDS CONSIDERATION l

Commonwealth Edison has evaluated the proposed Technical ,

Specification amendment and determined that it does not represent a l significant hazards consideration. Based on the criteria for defining a l significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Unit 1 in accordance with the proposed amendment will not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated because the control rod which may be uncoupled during mode changes will be f.ully inserted into the core and disarmed to prevent withdrawal. In this condition the control rod cannot drop and therefore the probability is not increased. This change has been reviewed and approved by the NRC as part of the Unit 2 Technical Specifications as issued.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated because the change to the Technical Specification is only to allow mode changes with the control rod fully inserted in accordance with action a. of Specification 3.1.3.6 and in accordance with 3.1.3.1.

3) Involve a signficant reduction in the margin of safety because the control rod will be in its most conservative position. The margin of safety was evaluated as part of the licensing process for LaSalle Unit 2 and found to be acceptable.

Based on the preceding discussion, it is concluded that the proposed change clearly falls within ell acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(e), the proposed change does not constitute a significant hazards consideration.

7867N

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ML20083H328

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