ML062960294: Difference between revisions

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| number = ML062960294
| number = ML062960294
| issue date = 10/23/2006
| issue date = 10/23/2006
| title = Cooper Nuclear Station, Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities
| title = Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities
| author name = Benney B J
| author name = Benney B
| author affiliation = NRC/NRR/ADRO/DORL/LPLIV
| author affiliation = NRC/NRR/ADRO/DORL/LPLIV
| addressee name =  
| addressee name =  
Line 9: Line 9:
| docket = 05000298
| docket = 05000298
| license number = DPR-046
| license number = DPR-046
| contact person = Benney B J, NRR/DORL, 415-3764
| contact person = Benney B, NRR/DORL, 415-3764
| case reference number = TAC MD2418
| case reference number = TAC MD2418
| package number = ML062790319
| package number = ML062790319
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=Text=
=Text=
{{#Wiki_filter:Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown," may be suspended, to allow reactor coolant temperature  
{{#Wiki_filter:Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1         The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown," may be suspended, to allow reactor coolant temperature >212°F:
>212°F: For performance of an inservice or hyrs 2ur. orhdrostaticteust, As a consequence of maintaining adequate pressure for an inservice leak or hydrostatic test, or As a consequence of maintaining adequate pressure for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, provided the following MODE 3 LCOs are met: a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1 and 3 of Table 3.3.6.2-1;
For performance of an inservice lea* or hyrs 2ur.orhdrostaticteust, As a consequence of maintaining adequate pressure for an inservice leak or hydrostatic test, or As a consequence of maintaining adequate pressure for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, provided the following MODE 3 LCOs are met:
: a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation,"
Functions 1 and 3 of Table 3.3.6.2-1;
: b. LCO 3.6.4.1, "Secondary Containment";
: b. LCO 3.6.4.1, "Secondary Containment";
: c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)";and d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System." APPLICABILITY:
: c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)";
MODE 4 with average reactor coolant temperature  
and
> 212 0 F.Cooper 3.10-1 Amendment No. 225}}
: d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."
APPLICABILITY:     MODE 4 with average reactor coolant temperature > 212 0 F.
Cooper                                     3.10-1                         Amendment No. 225}}

Latest revision as of 13:52, 23 November 2019

Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities
ML062960294
Person / Time
Site: Cooper Entergy icon.png
Issue date: 10/23/2006
From: Brian Benney
NRC/NRR/ADRO/DORL/LPLIV
To:
Benney B, NRR/DORL, 415-3764
Shared Package
ML062790319 List:
References
TAC MD2418
Download: ML062960294 (1)


Text

Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown," may be suspended, to allow reactor coolant temperature >212°F:

For performance of an inservice lea* or hyrs 2ur.orhdrostaticteust, As a consequence of maintaining adequate pressure for an inservice leak or hydrostatic test, or As a consequence of maintaining adequate pressure for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, provided the following MODE 3 LCOs are met:

a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation,"

Functions 1 and 3 of Table 3.3.6.2-1;

b. LCO 3.6.4.1, "Secondary Containment";
c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)";

and

d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."

APPLICABILITY: MODE 4 with average reactor coolant temperature > 212 0 F.

Cooper 3.10-1 Amendment No. 225