ML060900441

Technical Specification Pages, Change Request for Various Sections

ML060900441
Person / Time
Site:	Cooper
Issue date:	03/30/2006
From:	Brian Benney Plant Licensing Branch III-2
To:	Edington R Nebraska Public Power District (NPPD)
Benney B, NRR/DLPM, 415-3764
Shared Package
ML060730084	List: ML060730019 ML060900441
References
TAC MC6760
Download: ML060900441 (7)

Text

Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4

a.

No more than 10 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and

b.

No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION TIME A.

Requirements of the LCO A.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> not met.

SURVEILLANCE REQUIREMENTS

---

NOTE--------------------------

During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the limits Prior to exceeding of Table 3.1.4-1 with reactor steam dome pressure 40% RTP after

> 800 psig.

each reactor shutdown

> 120 days SR 3.1.4.2 Verify, for a representative sample, each tested 200 days control rod scram time is within the limits of cumulative Table 3.1.4-1 with reactor steam dome pressure operation in

> 800 psig.

MODE 1 Cooper 3.1 -12 Amendment No. 218

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.3 Verify each affected control rod scram time is within Prior to declaring the limits of Table 3.1.4-1 with any reactor steam control rod dome pressure.

OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after pressure > 800 psig.

fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Cooper 3.1 -1 3 Amendment No. 218

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1.

Core Spray System

a.

Reactor Vessel Water Level - Low Low Low (Level 1)

b. Drywell Pressure-High

c. Reactor Pressure-Low (Injection Permissive)

d.

Core Spray Pump Discharge Flow - Low (Bypass)

e.

Core Spray Pump Start-Time Delay Relay

2.

Low Pressure Coolant Injection (LPCI) System 1,2,3.

4 (a), 5(a) 1.2.3 1,2,3 4(a) 5(a) 4(a) s5(a) 4(a), 5(a) 4(b) 4(b) 4 4

1 per pump 1 per pump B

B C-B E

C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

> -113 inches

< 1.84 psig

> 291 psig and

< 436 psig

> 291 psig and c 436 psig

>1370 gpm

> 9 seconds and

< 11 seconds

a. Reactor Vessel Water Level - Low Low Low (Level 1) 1.2.3, 4 (a) 5(a) 4 8

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

> -113 inches (continued)

(a)

When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.

(b)

Also required to initiate the associated diesel generator (DG).

I Cooper 3.3-37 Amendment 218

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2.

LPCI System (continued)

b.

Drywell Pressure -High 1,2,3 4

B SR 3.3.5.1.2

< 1.84 psig SR 3.3.5.1.4 SR 3.3.5.1.5

c.

Reactor Pressure - Low 1,2,3 4

C SR 3.3.5.1.2

> 291 psig (Injection Permissive)

SR 3.3.5.1.4 and SR 3.3.5.1.5

< 436 psig 4(a), 5 (a) 4 B

SR 3.3.5.1.2

> 291 psig SR 3.3.5.1.4 and SR 3.3.5.1.5

< 436 psig

d.

Reactor Pressure - Low 1(c). 2(c),

4 C

SR 3.3.5.1.2

> 199 psig (Recirculation Discharge SR 3.3.5.1.4 and Valve Permissive) 3(c)

SR 3.3.5.1.5

<221 psig

e.

Reactor Vessel Shroud 1.2.3 2

8 SR 3.3.5.1.1

>-193.19 Level - Level 0 SR 3.3.5.1.2 inches SR 3.3.5.1.4 SR 3.3.5.1.5

f.

Low Pressure Coolant 1.2.3, 1 per pump C

SR 3.3.5.1.2 Injection Pump Start -

SR 3.3.5.1.4 Time Delay Relay 4(a). 5(a)

SR 3.3.5.1.5 Pumps BC

> 4.5 seconds and

< 5.5 seconds Pumps AD

< 0.5 second (continued)

(a)

(c)

When associated ECCS subsystems) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.

With associated recirculation pump discharge valve open.

Cooper 3.3-38 Amendment 218

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2.

LPCI System (continued)

9.

Low Pressure 1.2,3.

1 per E

SR 3.3.5.1.2

> 2107 gpm Coolant Injection Pump subsystem SR 3.3.5.1.4 Discharge Flow - Low 4(a). 5(a)

SR 3.3.5.1.5 (Bypass)

3.

High Pressure Coolant Injection (HPCI) System

a.

ReactorVesselWater 1,

4 B

SR 3.3.5.1.1

>-42 inches Level - Low Low SR 3.3.5.1.2 (Level 2) 2(d) 3(d)

SR 3.3.5.1.4 SR 3.3.5.1.5

b.

Drywell Pressure - High 1,

4 B

SR 3.3.5.1.2

<1.84 psig SR 3.3.5.1.4 2(d) 3(d)

SR 3.3.5.1.5

c.

ReactorVesselWater 1,

2 C

SR 3.3.5.1.1

<54inches Level - High (Level 8) d d

SR 3.3.5.1.2 2(d), 3 d)

SR 3.3.5.1.4 SR 3.3.5.1.5

d.

Emergency Condensate 1,

2 D

SR 3.3.5.1.2

> 23inches Storage Tank (ECST)

SR 3.3.5.1.3 Level - Low 2(d), 3(d)

SR 3.3.5.1.5

e.

Suppression Pool Water 1,

2 D

SR 3.3.5.1.2

< 4 inches Level - High SR 3.3.5.1.4 2(d) 3(d)

SR 3.3.5.1.5 (continued)

(a)

When the associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.

(d)

With reactor steam dome pressure > 150 psig.

Cooper 3.3-39 Amendment 218

AC Sources -

Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One required DG B.1 Suspend CORE Immediately inoperable.

ALTERATIONS.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND B.3 Initiate action to suspend OPDRVs.

Immediately AND B.4 Initiate action to restore required DG to OPERABLE status.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 NOTES-

1.

The following SRs are not required to be performed: SR 3.8.1.3, and SR 3.8.1.9 through SR 3.8.1.11.

2.

SR 3.8.1.11 is considered to be met without the ECCS initiation signals OPERABLE when the ECCS initiation signals are not required to be OPERABLE per Table 3.3.5.1-1.

For AC sources required to be OPERABLE the In accordance SRs of Specification 3.8.1, except with applicable SR 3.8.1.8, are applicable.

SRs I

Cooper 3.8-1 2 Amendment No. 21 8

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 APPLICABILITY:

The refueling equipment interlocks associated with the reactor mode switch refuel position shall be OPERABLE.

During in-vessel fuel movement with equipment associated with the interlocks when the reactor mode switch is in the refuel position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION A.

One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable.

associated with the inoperable interlocks(s).

OR A.2.1 Insert a control rod Immediately withdrawal block AND A.2.2 Verify all control rods Immediately are fully inserted I

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Cooper 3.9-1 Amendment No. 218