ML20084J219

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Revised Pages 3/4.1-14 & B3/4.1-4 to Proposed Tech Spec 3.1.3.1 Re Rod Control Sys
ML20084J219
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 05/03/1984
From:
ALABAMA POWER CO.
To:
Shared Package
ML20084J214 List:
References
NUDOCS 8405090036
Download: ML20084J219 (5)


Text

,.

Attachment Proposed Changes to Technical Specification Pages Unit 1 3/4.1-14 B3/4.1-4 Unit 2 3/4.1-14 B3/4.1-4 3

8405090036 840503 PDR ADOCK 05000348 PDR p

REACTIVITY CONTROL SYSTEMS 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 + 12 steps (indicated position) of their group step counter demand posTtion.

APPLICABILITY:

MODES 1* and 2*

ACTION:

a.

With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine 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 />.

b.

With more than one full length rod misaligned from the group step counter demand position by more than + 12 steps (indicated position),

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 />.

c.

With more than one full length rod inoperable due to a rod control urgent failure alarm or obvious electrical problem in the rod control system for greater than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

d.

With one full length rod inoperable due to causes other than l

addressed by ACTION a, above, or misaligned from its group step counter demand height by more than + 12 steps (indicated position),

POWER OPERATION may continue provideT that within one hour either:

1.

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

The remainder of the rods in the group with the inoperable rod are aligned to within + 12 steps of the inoperable rod within one hour while maintaining'~the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; 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:

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.

  • 5ee Special Test Exceptions 3.10.2 and 3.10.3.

FARLEY-UNIT 1 3/4 1-14 AMENDMENT NO.

REACTIVITY CONTROL SYSTEMS BASES For purposes of determining compliance with Technical Specification 3.1.3.1, any inoperability of full length control rod (s), due to being immovable, invokes ACTION statement "a".

The intent of Technical Specification 3.1.3.1 ACTION statement "a" is to ensure that before leaving ACTION statement "a" and utilizing ACTION statement "c"

that the rod urgent failure alarm is illuminated or that an obvious electrical problem is detected in the rod control system by minimal electrical troubleshooting techniques. Expeditious action will be taken to determine if rod imovability is due to an electrical problem in the rod control system.

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 or a restriction in THERMAL POWER; either of 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 Tavg greater than or equal to 541 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 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 inoperabl e.

These verification frequencies are adequate for assuring that the applicable LC0's are satisfied.

FARLEY-UNIT 1 B 3/4 1-4 AMENDMENT NO.

, REACTIVITY CONTROL SYSTEMS 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 + 12 steps (indicated position) of their group step counter demand posTtion.

APPLICABILITY:

MODES 1* and 2*

ACTION:

a.

With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine 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 />.

b.

With more than one full length rod misaligned from the group step l

counter demand position by more tnan + 12 steps (indicated position),

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 />.

c.

With more than one full length rod inoperable due to a rod control urgent failure alarm nr obvious electrical problem in the rod control system for greater than 36 hoars, be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

d.

With one full length rod inoperable due to causes other than l

addressed by ACTION a, above, or misaligned from its group step counter demand height by more than + 12 steps (indicated position),

POWER OPERATION may continue providiid that within one hour either:

1.

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

The remainder of the rods in the group with the inoperable rod are aligned to within + 12 steps of the inoperable rod within one hour while maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; 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:

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

  • 5ee Special Test Exceptions 3.10.2 and 3.10.3.

FARLEY-UNIT 2 3/4 1-14 AMENDMENT NO.

e-REACTIVITY CONTROL SYSTEMS BASES For purposes of determining compliance with Technical Specification 3.1.3.1, any inoperability of full length control rod (s), due to being immovable, invokes ACTION statement "a".

The intent of Technical Specification 3.1.3.1 ACTION statement "a" is to ensure that before leaving ACTION statement "a" and utilizing ACTION statement "c" that the rod urgent failure alarm is illuminated or that an obvious electrical problem is detected in the rod control system by minimal electrical troubleshooting techniques. Expeditious action will be taken to determine if rod inmovability is due to an electrical problem in the rod control system.

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 or a restriction in THERMAL POWER; either of these restrictions provide assurance of fuel rod integrity during continued o peration.

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 Tavg greater than or equal to 541*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 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 LC0's are satisfied.

l l

l I

I FARLEY-UNIT 2 B 3/4 1-4 AMENDMENT NO.

i l

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