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{{#Wiki_filter: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.
{{#Wiki_filter: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
APPLICABILITY:
: b.     No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.
MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION TIME A. Requirements of the LCO A.1 Be in MODE 3. 12 hours not met.SURVEILLANCE REQUIREMENTS
APPLICABILITY:             MODES 1 and 2.
-------------------------------------
ACTIONS CONDITION                               REQUIRED ACTION                     TIME A. Requirements of the LCO             A.1 Be in MODE 3.                     12 hours not met.
NOTE--------------------------  
SURVEILLANCE REQUIREMENTS
.During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
------------------------------------- NOTE-------------------------- .
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.
During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
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)
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
: 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)
                          > 800 psig.                                               each reactor shutdown
: b. Drywell Pressure -High 1,2,3 4 B SR 3.3.5.1.2  
                                                                                    > 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
< 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  
                          > 800 psig.                                               MODE 1 Cooper                                                 3.1 -12             Amendment No. 218
> 291 psig (Injection Permissive)
 
SR 3.3.5.1.4 and SR 3.3.5.1.5  
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 -13                Amendment No. 218
< 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  
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)
< 436 psig d. Reactor Pressure -Low 1 (c).2 (c), 4 C SR 3.3.5.1.2  
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
> 199 psig (Recirculation Discharge SR 3.3.5.1.4 and Valve Permissive) 3 (c) SR 3.3.5.1.5  
: 1. Core Spray System
<221 psig e. Reactor Vessel Shroud 1.2.3 2 8 SR 3.3.5.1.1  
: a. Reactor Vessel Water               1,2,3.            4 (b)            B      SR  3.3.5.1.1  > -113 inches Level - Low Low Low                                                          SR  3.3.5.1.2 (Level 1)                       4 (a), 5 (a)                                 SR  3.3.5.1.4 SR  3.3.5.1.5
>-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)
: b. Drywell Pressure- High                  1.2.3           4 (b)           B      SR 3.3.5.1.2    < 1.84 psig SR 3.3.5.1.4 SR 3.3.5.1.5
: 9. Low Pressure 1.2,3. 1 per E SR 3.3.5.1.2  
: 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   c 436 psig
> 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  
: d. Core Spray Pump                                  1 per pump          E      SR 3.3.5.1.2   >1370 gpm Discharge Flow - Low                                                          SR 3.3.5.1.4 (Bypass)                        4(a) s5(a)                                    SR 3.3.5.1.5
>-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  
: e. Core Spray Pump                                  1 per pump          C      SR 3.3.5.1.2   > 9 seconds Start-Time Delay Relay                                                        SR 3.3.5.1.4   and 4(a), 5(a)                                    SR 3.3.5.1.5   < 11 seconds
<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  
: 2. Low Pressure Coolant Injection (LPCI) System
<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  
: a. Reactor Vessel Water                  1.2.3,            4              8      SR 3.3.5.1.1    > -113 inches Level - Low Low Low                                                            SR 3.3.5.1.2 (Level 1)                        4 (a)  5 (a)                                SR 3.3.5.1.4 SR 3.3.5.1.5 (continued)
> 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  
(a)  When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.                       I (b)   Also required to initiate the associated diesel generator (DG).
< 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)
Cooper                                                          3.3-37                                Amendment 218
CONDITION REQUIRED ACTION COMPLETION TIME B. One required DG B.1 Suspend CORE Immediately inoperable.
 
ALTERATIONS.
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)
AND B.2 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.
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
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:
: 2. LPCI System (continued)
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.
: 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
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.
: 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
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:
: 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
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.
: 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
associated with the inoperable interlocks(s).
: 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
OR A.2.1 Insert a control rod Immediately withdrawal block AND A.2.2 Verify all control rods Immediately are fully inserted I I I I I I I I I Cooper 3.9-1 Amendment No. 218}}
                                                                                                          > 4.5 seconds and
                                                                                                          < 5.5 seconds Pumps AD
                                                                                                          < 0.5 second (continued)
(a)   When associated ECCS subsystems) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.
(c)  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     < 4inches 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 I
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 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             The refueling equipment interlocks associated with the reactor mode switch refuel position shall be OPERABLE.
APPLICABILITY:        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                                                  I I
A.2.1      Insert a control rod            Immediately          I withdrawal block                                    I I
AND                                                              I I
A.2.2        Verify all control rods        Immediately          I are fully inserted                                   I Cooper                                           3.9-1                             Amendment No. 218}}

Latest revision as of 21:34, 23 November 2019

Technical Specification Pages, Change Request for Various Sections
ML060900441
Person / Time
Site: Cooper Entergy icon.png
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
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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 -13 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 1,2,3. 4 (b) B SR 3.3.5.1.1 > -113 inches Level - Low Low Low SR 3.3.5.1.2 (Level 1) 4 (a), 5 (a) SR 3.3.5.1.4 SR 3.3.5.1.5
b. Drywell Pressure- High 1.2.3 4 (b) 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 c 436 psig
d. Core Spray Pump 1 per pump E SR 3.3.5.1.2 >1370 gpm Discharge Flow - Low SR 3.3.5.1.4 (Bypass) 4(a) s5(a) SR 3.3.5.1.5
e. Core Spray Pump 1 per pump C SR 3.3.5.1.2 > 9 seconds Start-Time Delay Relay SR 3.3.5.1.4 and 4(a), 5(a) SR 3.3.5.1.5 < 11 seconds
2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel Water 1.2.3, 4 8 SR 3.3.5.1.1 > -113 inches Level - Low Low Low SR 3.3.5.1.2 (Level 1) 4 (a) 5 (a) SR 3.3.5.1.4 SR 3.3.5.1.5 (continued)

(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown. I (b) Also required to initiate the associated diesel generator (DG).

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

(c) 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 < 4inches 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 I

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

APPLICABILITY: 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 I I

A.2.1 Insert a control rod Immediately I withdrawal block I I

AND I I

A.2.2 Verify all control rods Immediately I are fully inserted I Cooper 3.9-1 Amendment No. 218

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