Text

Regional Library TRM Rev. 21
	ML12121A687
Person / Time
Site:	Duane Arnold
Issue date:	04/30/2012
From:	Browning T; BWR Owners Group, Duane Arnold
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML12121A687 (330)
	v • d • e

TRM REVISION UPDATE INSTRUCTIONS Manual Holder REGIONAL LIBRARY TRM Copy # 14 NRC REGION III TRM Rev. # 021 Responsible Licensing Engineer/Specialist Tony Browning TRMCR-035 implements License Amendment # 280 (Surveillance Frequency Control Program) by adding the new Chapter 4 with the Tables of Surveillance Frequencies that have been relocated from the Technical Specifications (TS). In addition, the TRM Definitions are updated to contain the definition for Staggered Test Basis. The Surveillance Frequency Control Program description is also being added to App. A.

This revision becomes effective on the following date: 4/30/12 Please update your TRM manual as indicated below:

REMOVE INSERT List of Effective Pages List of Effective Pages Pg 1.1-4 Pgs 4.0-1 thru 4.0-40 App. A - TS 5.5.14 Surveillance Frequency Control Program NOTICE OF RECEIPT OF TECHNICAL REQUIREMENTS MANUAL REVISION This acknowledges receipt of this TRM revision. Please sign and return this form, along with the sheets removed from the TRM, to the responsible Licensing Engineer/Specialist within 10 days of the effective date of this TRM revision.

TRM Copy # 14 NRC REGION III TRM Revision # 021 Signature DATE

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Page 1 of 2 LIST OF EFFECTIVE PAGES Technical Requirements Manual Revision Date 04/30/12 Page Date Rev. Pape Date Rev Paue Date. R ev 1.1-1 08/01/98 0 3.3-18 05/16/08 17 4.0-12 04/30/12 21 1.1-2 08/01/98 0 3.3-19 05/16/08 17 4.0-13 04/30/12 21 1.1-3 11/07/01 5 3.3-20 02/08/08 16 4.0-14 04/30/12 21 1.1-4 04/30/12 21 3.4-1 08/01/98 0 4.0-15 04/30/12 21 1.2-1 08/01/98 0 3.4-2 08/01/98 0 4.0-16 04/30/12 21 1.2-2 08/01/98 0 3.4-3 08/01/98 0 4.0-17 04/30/12 21 1.2-3 08/01/98 0 3.4-4 10/20/99 2 4.0-18 04/30/12 21 1.3-1 08/01/98 0 3.4-5 10/20/99 2 4.0-19 04/30/12 21 1.3-2 08/01/98 0 3.5-1 02/08/08 16 4.0-20 04/30/12 21 1.3-3 08/01/98 0 3.5-2 08/01/98 0 4.0-21 04/30/12 21 1.3-4 08/01/98 0 3.5-3 04/18/05 8 4.0-22 04/30/12 21 1.3-5 08/01/98 0 3.5-4 08/01/98 0 4.0-23 04/30/12 21 1.3-6 08/01/98 0 3.7-1 08/01/98 0 4.0-24 04/30/12 21 1.3-7 08/01/98 0 3.7-2 06/12/07 12 4.0-25 04/30/12 21 1.3-8 08/01/98 0 3.7-3 06/12/07 12 4.0-26 04/30/12 21 1.3-9 08/01/98 0 3.7-4 11/30/06 11 4.0-27 04/30/12 21 1.3-10 08/01/98 0 3.7-5 06/12/07 12 4.0-28 04/30/12 21 1.3-11 08/01/98 0 3.7-6 08/01/98 0 4.0-29 04/30/12 21 1.3-12 08/01/98 0 3.7-7 06/12/07 12 4.0-30 04/30/12 21 1.3-13 08/01/98 0 3.7-8 06/12/07 12 4.0-31 04/30/12 21 1.4-1 07/01/05 9 3.7-9 05/16/01 4 4.0-32 04/30/12 21 1.4-2 07/01/05 9 3.7-10 11/30/06 11 4.0-33 04/30/12 21 1.4-3 07/01/05 9 3.7-11 08/01/98 0 4.0-34 04/30/12 21 1.4-4 07/01/05 9 3.7-12 08/01/98 0 4.0-35 04/30/12 21 1.4-5 07/01/05 9 3.7-13 04/18/05 8 4.0-36 04/30/12 21 1.4-6 07/01/05 9 3.8-1 08/01/98 0 4.0-37 04/30/12 21 1.4-7 07/01/05 9 3.8-2 08/01/98 0 4.0-38 04/30/12 21 1.4-8 07/01/05 9 3.8-3 08/01/98 0 4.0-39 04/30/12 21 3.0-1 04/18/05 8 3.8-4 08/01/98 0 4.0-40 04/30/12 21 3.0-2 04/18/05 8 3.8-5 08/01/98 0 3.0-3 04/29/11 20 3.8-6 08/01/98 0 TB 3.0-1 04/29/11 20 3.0-4 07/01/05 9 3.8-7 03/20/00 3 TB 3.0-2 10/01/09 19 3.0-5 07/01/05 9 3.8-8 08/01/98 0 TB 3.0-3 08/01/98 0 3.3-1 08/01/98 0 3.8-9 08/01/98 0 TB 3.0-4 04/18/05 8 3.3-2 08/01/98 0 3.8-10 08/01/98 0 TB 3.0-5 04/18/05 8 3.3-3 08/01/98 0 3.9-1 07/01/05 9 TB 3.0-6 04/18/05 8 3.3-4 11/07/01 5 3.9-2 08/01/98 0 TB 3.0-7 04/18/05 8 3.3-5 08/01/98 0 3.9-3 08/01/98 0 TB 3.0-8 05/09/08 9 3.3-6 11/07/01 5 3.10-1 08/01/98 0 TB 3.0-9 04/18/05 8 3.3-7 08/01/98 0 4.0-1 04/30/12 21 TB 3.09a 04/29/11 20 3.3-8 02/08/08 16 4.0-2 04/30/12 21 TB 3.09b 04/29/11 20 3.3-9 02/08/08 16 4.0-3 04/30/12 21 TB 3.09c 04/29/11 20 3.3-10 09/26/08 18 4.0-4 04/30/12 21 TB 3.0-10 04/18/05 8 3.3-11 09/26/08 18 4.0-5 04/30/12 21 TB 3.0-11 04/18/05 8 3.3-12 02/08/08 16 4.0-6 04/30/12 21 TB 3.0-12 07/01/05 9 3.3-13 02/08/08 16 4.0-7 04/30/12 21 TB 3.0-13 07/01/05 9 3.3-14 02/08/08 16 4.0-8 04/30/12 21 TB 3.0-14 07/01/05 9 3.3-15 02/08/08 16 4.0-9 04/30/12 21 TB 3.0-15 07/01/05 9 3.3-16 02/08/08 16 4.0-10 04/30/12 21 TB 3.0-16 07/01/05 9 3.3-17 02/08/08 16 4.0-11 04/30/12 21 TB 3.3-1 08/01/98 0

Page 2 of 2 LIST OF EFFECTIVE PAGES Technical Requirements Manual Revision Date 04/30/12 Page Date Rev. Paae Date Rev. Paae Date Rev.

TB 3.3-2 11/07/01 5 TB 3.3-3 07/01/05 9 TB 3.3-3A 07/01/05 9 TB 3.3-4 03/15/99 1 TB 3.3-5 09/20/05 10 TB 3.3-6 05/16/08 17 TB 3.4-1 08/01/98 0 TB 3.4-2 10/20/99 2 TB 3.5-1 10/20/99 2 TB 3.5-2 04/18/05 8 TB 3.7-1 08/01/98 0 TB 3.7-2 06/12/07 12 TB 3.7-3 06/12/07 12 TB 3.7-4 06/12/07 12 TB 3.7-5 06/12/07 12 TB 3.7-6 05/16/01 4 TB 3.7-7 10/01/09 19 TB 3.8-1 10/25/07 14 TB 3.8-2 10/25/07 14 TB 3.8-3 08/01/98 0 TB 3.8-4 03/20/00 3 TB 3.8-5 08/01/98 0 TB 3.8-6 08/01/98 0 TB 3.9-1 07/01/05 9 TB 3.10-1 08/01/98 0

Definitions T1.1 T 1.1 Definitions (continued)

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

DAEC 1.1-4 Rev. 21 TRMCR-035

0 DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-1 (Reactivity Control)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.1.3.1 Control Rod Position Control Rods 3.0.0-01 24 Hours No 3.1.3.2 Control Rod Exercises Control Rods 3.1.3-01 31 Days Yes WK 1, 2,3,&4 3.1.5.1 Control Rod Accumulator Pressure Control Rod 3.0.0-04 7 Days No Accumulators 3.1.6.1 Rod Pattern matches BPWS Control Rod Patterns 3.0.0-01 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months No 3.1.7.1 SLCS Tank Volumne Standby Liquid Control 3.0.0-01 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months No 3.1.7.2 SLCS Tank Temperature Standby Liquid Control 3.0.0-01 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months No 3.1.7.3 SLCS Suction Pipe Temperature Standby Liquid Control 3.0.0-01 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months No 3.1.7.4 Squib Valve Continuity Check Standby Liquid Control 3.0.0-02 31 Days No 3.1.7.5 SLCS Tank Boron Concentration Standby Liquid Control 3.1.7-03 31 Days No 3.1.7.7 SLCS Pump Flow to RPV Standby Liquid Control 3.1.7-02 24 Months No Staggered Test Basis 3.1.7.8 SLCS Heat Traced Pipe Blockage Standby Liquid Control 3.1.7-02 24 Months No 3.1.8.1 SDV Vent/Drain Valve Position Scram Discharge 3.0.0-02 31 Days Yes Volume Vent/Drain Valves 3.1.8.3 SDV Vent/Drain Valve Actuation Scram Discharge 3.6.1.3-06 24 Months No

& Timing Volume Vent/Drain Valves DAEC 4.0-1 TRMCR-035 Rev. 21

DAEC 9

Technical Requirements Manual Chapter 4.0 (Techmical Specification Surveillance Frequency Control Program)

Table 4.0-2 (Thermal Limits)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.2.1.1 APLHGR COLR Limits Check APLHGR 3.0.0-01 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months No 3.2.2.1 MCPR COLR Limits Check MCPR 3.0.0-01 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months No DAEC 4.0-2 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3a (RPS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.1.1.1 RPS CHANNEL CHECK RPS Functions: la, 2a, 2b, & 4 3.0.0-01 12 Hours No 3.0.0-03 3.3.1.1.2 APRM Gain Adjustments RPS Functions: 2b & 2c 3.0.0-01 24 Hours Yes 3.3.1.1.3 Scram Contactor Functional Test RPS Functions: 2b, 2c, 2d, 3, 3.3.1.1-22 7 Days No 4, 5, 6, 7a, 7b, 8, & 9 3.3.1.1.4 CHANNEL FUNCTIONAL TEST RPS Functions: la, 1b, & 2a 3.3.1.1-06 7 Days Yes 3.3.1.1-07 3.3.1.1-25 3.3.1.1-26 3.3.1.1-31 3.3.1.1-35 3.3.1.1-38 3.3.1.1.5 CHANNEL FUNCTIONAL TEST RPS Functions: la* & lb* 3.3.1.1-06 7 Days No 3.3.1.1-07 3.3.1.1-31 3.3.1.1.7 Verify IRM/APRM channel overlap RPS Functions: la & 2a 3.3.1.1-30 7 Days Yes 3.3.1.1.8 LPRM Calibration RPS Functions: 2a, 2b & 2c 3.3.1.1-24 1000 No 3.3.1.1-37 MWD/T DAEC 4.0-3 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3a (RPS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.1.1.9 CHANNEL FUNCTIONAL TEST RPS Functions: 2b, 2c, 2d, 3, 3.3.1.1-01 92 Days No 4, 5, 6, 7b, 8, 9, & 11 3.3.1.1-02 3.3.1.1-03 3.3.1.1-04 3.3.1.1-05 3.3.1.1-09 3.3.1.1-10 3.3.1.1-13 3.3.1.1-15 3.3.1.1-16 3.3.1.1-17 3.3.1.1-19 3.3.1.1-21 3.3.1.1-26 3.3.1.1-32 3.3.1.1-33 3.3.1.1-38 3.3.1.1.10 Trip Unit Calibrations RPS Function: 7a 3.3.1.1-11 92 Days No 3.3.1.1.11 CHANNEL CALIBRATION RPS Function: 3 3.3.1.1-01 92 Days No 3.3.1.1.12 CHANNEL CALIBRATION RPS Functions: 2a, 2b & 2c 3.3.1.1-26 184 Days Yes 3.3.1.1-32 3.3.1.1-33 3.3.1.1-34 3.3.1.1-38 3.3.1.1.13 CHANNEL FUNCTIONAL TEST RPS Functions: 7a & 10 3.3.1.1-11 24 Months No 3.3.1.1-23 DAEC 4.0-4 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3a (RPS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.1.1.14 CHANNEL CALIBRATION RPS Functions: la, 4, 5, 6, 7a, 3.3.1.1-03 24 Months Yes 7b, 8, & 9 3.3.1.1-05 3.3.1.1-07 3.3.1.1-10 3.3.1.1-12 3.3.1.1-14 3.3.1.1-18 3.3.1.1-31 DAEC 4.0-5 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Teclnical Specification Surveillance Frequency Control Program)

Table 4.0-3a (RPS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.1.1.15 LOGIC SYSTEM FUNCTIONAL RPS Functions: la, lb, 2a, 2b, 3.3.1.1-01 24 Months No TEST 2c, 2d, 3, 4, 5, 6, 7a, 7b, 8, 9, 3.3.1.1-02 10 & 11 3.3.1.1-03 3.3.1.1-04 3.3.1.1-05 3.3.1.1-06 3.3.1.1-07 3.3.1.1-09 3.3.1.1-10 3.3.1.1-11 3.3.1.1-13 3.3.1.1-15 3.3.1.1-16 3.3.1.1-17 3.3.1.1-19 3.3.1.1-21 3.3.1.1-23 3.3.1.1-25 3.3.1.1-26 3.3.1.1-32 3.3.1.1-33 3.3.1.1-36 3.3.1.1-38 3.3.1.1.16 Low Power Bypass Cutoff Check RPS Functions: 8 & 9 3.3.1.1-16 24 Month No 3.3.1.1.17 Flow Signal Conformance Check RPS Function: 2b 3.3.1.1-27 24 Month No DAEC 4.0-6 TRMCR-035 Rev. 21

DAEC 0 0 Technical Requirements Manual Chapter 4.0 (Techmical Specification Surveillance Frequency Control Program)

Table 4.0-3a (RPS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.1.1.18 RPS RESPONSE TIME Check RPS Functions: 3 & 4 3.3.1.1-08 24 Months No 3.3.1.1-28 Staggered 3.3.1.1-29 Test Basis 3.3.1.1.19 RPS Logic System Response Time RPS Functions: la, lb, 2a, 2b, 3.3.1.1-08 24 Months No Check 2c, 2d, 3, 4, 5, 6, 7a, 7b, 8 & 9 3.3.1.1-36 Staggered I_ I Test Basis

MODE 5, with any control rod withdrawn from a core cell containing one or more fuel assemblies.

DAEC 4.0-7 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3b (SRM Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.1.2.1 CHANNEL CHECK SRM (MODES 2 & 5) 3.0.0-01 12 Hours No 3.0.0-03 3.3.1.2.2 Operable SRM Location Check SRM (MODE 5) 3.0.0-03 12 Hours No 3.10.3-03 3.3.1.2.3 CHANNEL CHECK SRM (MODES 3 & 4) 3.0.0-01 24 Hours No 3.0.0-03 3.3.1.2.4 Detector Count Rate Check SRM (MODES 2, 3, 4 3.0.0-01 12 Hours No

& 5) 3.0.0-03 (CORE ALTS) 24 Hours 3.3.1.2.5 CHANNEL FUNCTIONAL TEST SRM (MODE 5) 3.3.1.2-01 7 Days No 3.3.1.2-02 3.3.1.2-03 3.3.1.2.6 CHANNEL FUNCTIONAL TEST SRM (MODES 2,3 & 3.3.1.2-01 31 Days Yes

4) 3.3.1.2-02 3.3.1.2-03 3.3.1.2-04 3.3.1.2.7 CHANNEL CALIBRATION SRM (MODES 2, 3, 4 3.3.1.2-02 24 Months Yes

& 5) 3.3.1.2-03 DAEC 4.0-8 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3c (Rod Block Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.2.1.1 CHANNEL FUNCTIONAL TEST Rod Block Functions: 3.3.2.1-01 92 Days No la, lb, lc, 1d, le & if 3.3.2.1-02 3.3.2.1.2 CHANNEL FUNCTIONAL TEST Rod Block Function 2 3.3.2.1-03 92 Days Yes (MODE 2) 3.3.2.1.3 CHANNEL FUNCTIONAL TEST Rod Block Function 2 3.3.2.1-03 92 Days Yes (MODE 1) 3.3.2.1.4 Power Range Bypass Checks Rod Block Functions: 3.3.2.1-02 184 Days No la, lb & lc 3.3.2.1.5 CHANNEL CALIBRATION Rod Block Functions: 3.3.2.1-02 184 Days No la, 1b, lc, le & If 3.3.2.1.6 CHANNEL FUNCTIONAL TEST Rod Block Function 3 3.3.1.1-23 24 Months Yes DAEC 4.0-9 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3d (PAM Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.3.1.1 CHANNEL CHECK PAM Functions: 1, 2a, 3.0.0-02 31 Days No 2b, 3, 4a, 4b, 5a, 5b, 6 3.0.0-04 3.3.3.1.2 CHANNEL CALIBRATION PAM Functions: 1, 2a, 3.3.3.1-01 24 Months No 2b, 3, 4a, 4b, 5a, 5b, 6 3.3.3.1-02 3.3.3.1-03 3.3.3.1-05 3.3.3.1-06 3.3.3.1-07 3.3.3.1-08 3.3.3.1-09 3.3.3.1-09PASS 3.3.3.1-10 3.3.3.1-11 3.3.3.1-12 DAEC 4.0-10 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3 e (Remote Shutdown Panel Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.3.2.1 Verify control circuit and transfer Remote Shutdown 3.3.3.2-02 24 Months No switches perform their intended Panel 3.3.3.2-03 functions. 3.3.3.2-04 3.3.3.2-05 3.3.3.2-06 3.3.3.2-07 3.3.3.2-08 3.3.3.2-04 3.3.3.2.2 CHANNEL CALIBRATION Remote Shutdown 3.3.3.2-01 24 Months No Panel 3.3.3.2-09 3.3.3.2-10 3.3.3.2-11 3.3.3.2-12 DAEC 4.0-11 TRMCR-035 Rev. 21

DAEC 0 e Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3f (EOC-RPT Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.4.1.1 CHANNEL FUNCTIONAL TEST EOC-RPT Function: 3.3.1.1-13 92 Days No TSV - Closure 3.3.1.1-15 EOC-RPT Function: 3.3.1.1-16 TCV Fast Closure 3.3.1.1-19 3.7.7-03 3.3.4.1.2 CHANNEL CALIBRATION EOC-RPT Function: 3.3.1.1-14 24 Months No TSV - Closure 3.3.1.1-20 EOC-RPT Function:

TCV Fast Closure 3.3.4.1.3 LOGIC SYSTEM FUNCTIONAL EOC-RPT Function: 3.3.1.1-13 24 Months No TEST, including breaker actuation TSV - Closure 3.3.1.1-19 EOC-RPT Function: 3.3.4.1-02 TCV Fast Closure 3.3.4.1.4 Verify trips are not bypassed above EOC-RPT Function: 3.3.1.1-16 24 Months No 26% RTP TSV - Closure EOC-RPT Function:

TCV Fast Closure 3.3.4.1.5 Verify EOC-RPT SYSTEM EOC-RPT Function: 3.3.4.1-01 24 Months No RESPONSE TIME TSV - Closure 3.3.4.1-02 Staggered EOC-RPT Function: Test Basis TCV Fast Closure I I _I DAEC 4.0-12 TRMCR-035 Rev. 21

DAEC e

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3g (ATWS-RPT Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.4.2.1 CHANNEL CHECK ATWS-RPT Function: 3.0.0-01 12 Hours No RPV Water Level -

Low Low 3.3.4.2.2 CHANNEL FUNCTIONAL TEST ATWS-RPT Function: 3.3.4.2-01 12 Months No RPV Water Level - 3.3.6.1-10 Low Low 3.3.6.1-11 ATWS-RPT Function:

RPV Pressure - High 3.3.4.2.3 CHANNEL CALIBRATION ATWS-RPT Function: 3.3.4.2-01 12 Months No RPV Water Level - 3.3.6.1-10 Low Low ATWS-RPT Function:

RPV Pressure - High 3.3.4.2.4 LOGIC SYSTEM FUNCTIONAL ATWS-RPT Function: 3.3.4.2-01 24 Months No TEST, including breaker actuation RPV Water Level - 3.3.4.2-02 Low Low 3.3.6.1-10 ATWS-RPT Function:

RPV Pressure - High DAEC 4.0-13 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3h (ECCS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.5.5.1 CHANNEL CHECK ECCS Functions: la, 3.0.0-01 24 Hours No 2a, 2d, 2g, 2i, 2.j, 3a, 3.0.0-03 3c, 4a, 4c, 5a, 5c 3.3.5.1.2 CHANNEL FUNCTIONAL TEST ECCS Functions: 2d, 3.3.5.1-01 31 Days No 2g, 2h, 2i, 2j 3.3.5.1-02 3.3.5.1-03 3.3.5.1-04 3.3.5.1-05 3.3.5.1-12 3.3.5.1-13 3.3.5.1-19 3.3.5.1-20 3.3.5.1-21 3.3.5.1-22 DAEC 4.0-14 TRMCR-035 Rev. 21

DAEC 0 0 Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3h (ECCS Instrumentation) 3.3.5.1.3 CHANNEL FUNCTIONAL TEST ECCS Functions: la, 3.3.5.1-01 92 Days No lb, Ic, Id, 2a, 2b, 2c, 3.3.5.1-02 2f, 3a, 3b, 3c, 3d, 3e, 3.3.5.1-04 3f, 4a, 4b, 4c, 4d, 4e, 3.3.5.1-05 5a, 5b, 5c, 5d, 5e 3.3.5.1-06 3.3.5.1-07 3.3.5.1-08 3.3.5.1-09 3.3.5.1-10 3.3.5.1-11 3.3.5.1-12 3.3.5.1-13 3.3.5.1-17 3.3.5.1-18 3.3.5.1-23 3.3.5.1-24 3.3.5.1-25 3.3.5.1-26 3.3.5.1-27 3.3.5.1-34 3.3.5.1-35 3.3.5.1-36 3.5.1-01 3.5.1-02 3.5.1-05 3.5.1-10 3.5.1-11 3.5.1-12 DAEC 4.0-15 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3h (ECCS Instrumentation) 3.3.5.1.4 CHANNEL CALIBRATION ECCS Functions: 2d, 3.3.5.1-05 92 Days No 2h, 2j 3.3.5.1-13 3.3.5.1-22 3.3.5.1.5 CHANNEL FUNCTIONAL TEST ECCS Functions: lf, 2k 3.3.5.1-28 12 Months No 3.3.5.1.6 CHANNEL CALIBRATION ECCS Functions: lf, 3.3.1.1-05 12 Months No 2g, 2k, 3a, 3c 3.3.5.1-02 3.3.5.1-28 3.3.5.1.7 CHANNEL CALIBRATION ECCS Functions: None None 18 Months No 3.3.5.1.8 CHANNEL CALIBRATION ECCS Functions: la, 3.3.5.1-02 24 Months No lb, Ic, Id, le, 2a, 2b, 3.3.5.1-06 2c, 2e, 2f, 2i, 3b, 3d, 3e, 3.3.5.1-08 3f, 4a, 4b, 4c, 4d, 4e, 3.3.5.1-11 5a, 5b, 5c, 5d, 5e 3.3.5.1-16 3.3.5.1-18 3.3.5.1-20 3.3.5.1-24 3.3.5.1-26 3.3.5.1-27 3.3.5.1-32 3.3.5.1-33 3.3.5.1-35 3.3.5.1-36 DAEC 4.0-16 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3h (ECCS Instrumentation) 3.3.5.1.9 LOGIC SYSTEM FUNCTIONAL ECCS Functions: la, 3.3.5.1-02 24 Months No TEST lb, ic, Id, le, If, 2a, 3.3.5.1-05 2b, 2c, 2d, 2e, 2f, 2g, 3.3.5.1-06 2h, 2i, 2j, 2k, 3a, 3b, 3c, 3.3.5.1-08 3d, 3e, 3f, 4a, 4b, 4c, 3.3.5.1-11 4d, 4e, 5a, 5b, 5c, 5d, 3.3.5.1-13 5e 3.3.5.1-14 3.3.5.1-15 3.3.5.1-16 3.3.5.1-18 3.3.5.1-20 3.3.5.1-22 3.3.5.1-28 3.3.5.1-29 3.3.5.1-30 3.3.5.1-32 3.3.5.1-33 3.3.5.1-37 3.5.1-01 3.5.1-03 3.5.1-04 3.5.1-05 3.5.1-07 3.5.1-10 3.5.1-12 3.5.3-05 3.8.1-07 DAEC 4.0-17 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3i (RCIC Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.5.2.1 CHANNEL CHECK RCIC Function: 1, 2 3.0.0-01 24 Hours No 3.3.5.2.2 CHANNEL FUNCTIONAL TEST RCIC Function: 1, 2, 3 3.3.1.1-04 92 Days No 3.3.1.1-05 3.3.5.1-01 3.3.5.1-02 3.3.5.1-23 3.3.5.1-24 3.3.5.2.3 CHANNEL CALIBRATION RCIC Function: 1, 2 3.3.1.1-05 12 Months No 3.3.5.1-02 3.3.5.2.4 CHANNEL CALIBRATION RCIC Function: 4 3.3.5.1-24 24 Months No 3.3.5.2.5 LOGIC SYSTEM FUNCTIONAL RCIC Function: 1, 2, 3 3.3.1.1-05 24 Months No TEST 3.3.5.1-02 3.3.5.1-24 3.3.5.1-37 3.5.3-04 3.5.3-05 DAEC 4.0-18 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3j (PCIS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.6.1.1 CHANNEL CHECK PCIS Function: la, Ic, 3.0.0-01 12 Hours No 2a, 2b, 5e, 6b 3.0.0-03 3.3.6.1.2 CHANNEL CHECK PCIS Function: le, If, 3.0.0-01 24 Hours No 2c, 2d, 2e, 3e, 3g, 3h, 3.3.6.1-38 3i, 4e, 4g, 4h, 4i, 5a, 5b, 5c, 5f 3.3.6.1.3 CHANNEL FUNCTIONAL TEST PCIS Function: 7a 3.3.6.1-07 31 Days No 3.3.6.1-08 DAEC 4.0-19 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3j (PCIS Instrumentation)

T I 3.3.6.1.4 I CHANNEL FUNCTIONAL TEST PCIS Function: la, lb, 3.3.1.1-02 92 Days No 3.3.1.1-03 1c, Id, le, If, 2a, 2b, 3.3.1.1-04 2c, 2d, 2e, 3a, 3b, 3c, 3.3.1.1-05 3d, 3e, 3f, 3g, 3h, 3i, 3.3.5.1-08 3.3.5.1-09 4a, 4b, 4c, 4d, 4e, 4f, 3.3.6.1-01 4g, 4h, 4i, 5a, 5b, 5c, 3.3.6.1-02 5e, 5f, 6a, 6c 3.3.6.1-03 3.3.6.1-04 3.3.6.1-05 3.3.6.1-10 3.3.6.1-11 3.3.6.1-12 3.3.6.1-13 3.3.6.1-15 3.3.6.1-16 3.3.6.1-17 3.3.6.1-18 3.3.6.1-19 3.3.6.1-20 3.3.6.1-21 3.3.6.1-22 3.3.6.1-23 3.3.6. 1-24 3.3.6.1-25 3.3.6.1-26 3.3.6.1-27 3.3.6.1-28 3.3.6.1-29 3.3.6.1-30 3.3.6.1-31 3.3.6.1-32 3.3.6.1-33 3.3.6.1-34 3.3.6.1-40 3.3.6.1-41 3.3.6.1-43 3.3.6.1-44 3.3.6.1-45 3.3.6.1-46 3.3.6.1-47 3.3.6.1-48 DA1C 4.U-2U IRKevIU -U2 Rev. 21

DAEC 0

Teclnical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3j (PCIS Instrumentation) 3.3.6.1.5 CHANNEL CALIBRATION PCIS Function: Ib, Ic, 3.3.6.1-01 92 Days No 6a 3.3.6.1-02 3.3.6.1-03 3.3.6.1.6 CHANNEL CALIBRATION PCIS Function: 4c 3.3.6.1-31 184 Days No 3.3.6.1.7 CHANNEL CALIBRATION PCIS Function: le, lf, 3.3.6.1-04 12 Months No 5e 3.3.6.1-10 3.3.6.1-15 3.3.6.1.8 CHANNEL CALIBRATION PCIS Function: la, Id, 3.3.1.1-03 24 Months No 2a, 2b, 2c, 2d, 2e, 3a, 3.3.1.1-05 3b, 3c, 3d, 3e, 3f, 3g, 3.3.5.1-08 3h, 3i,4a, 4b, 4d, 4e, 4f, 3.3.6.1-08 4g, 4h, 4i, 5a, 5b, 5c, 3.3.6.1-10 5f, 6b, 6c, 7a 3.3.6.1-13 3.3.6.1-17 3.3.6.1-19 3.3.6.1-21 3.3.6.1-23 3.3.6.1-25 3.3.6.1-27 3.3.6.1-29 3.3.6.1-34 3.3.6.1-40 3.3.6.1-44 3.3.6.1-46 DAEC 4.0-21 TRMCR-035 Rev. 21

DAEC Teclmical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3j (PCIS Instrumentation) 3.3.6.1.9 LOGIC SYSTEM FUNCTIONAL PCIS Function: la, 1b, 3.1.7-02 24 Months No TEST ic, Id, le, If, 2a, 2b, 3.3.1.1-03 2c, 2d, 2e, 3a, 3b, 3c, 3.3.1.1-05 3d, 3e, 3f, 3g, 3h, 3i, 3,3,5.1-08 4a, 4b, 4c, 4d, 4e, 4f, 3.3.5.1-29 3.3.6.1-01 4g, 4h, 4i, 5a, 5b, 5c, 3.3.6.1-02 5d, 5e, 5f, 6a, 6b, 6c, 7a 3.3.6.1-03 3.3.6.1-04 3.3.6.1-06 3.3.6.1-08 3.3.6.1-09 3.3.6.1-10 3.3.6.1-13 3.3.6.1-14 3.3.6.1-15 3.3.6.1-17 3.3.6.1-19 3.3.6.1-21 3.3.6.1-23 3.3.6.1-25 3.3.6.1-27 3.3.6.1-29 3.3.6.1-31 3.3.6.1-34 3.3.6.1-40 3.3.6.1-42 3.3.6.1-44 3.3.6.1-46 3.3.6.1-48 3.3.6.1-49 3.3.6.1-50 3.3.6.1-51

___________ J I __________________________ I 3.6.1.3-06 DAEC 4.0-22 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3j (PCIS Instrumentation)

DAEC 4.0-23 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3k (SCIS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.6.2.1 CHANNEL CHECK SCIS Function: 1 3.0.0-01 12 Hours No 3.0.0-03 3.3.6.2.2 CHANNEL CHECK SCIS Function: 3, 4 3.0.0-01 24 Hours No 3.0.0-03 3.3.6.1-38 3.3.6.2.3 CHANNEL FUNCTIONAL TEST SCIS Function: 1, 2, 3, 3.3.1.1-02 92 Days No 4 3.3.1.1-03 3.3.1.1-04 3.3.1.1-05 3.3.6.1-21 3.3.6.1-22 3.3.6.1-23 3.3.6.1-24 3.3.6.2.4 CHANNEL CALIBRATION SCIS Function: 1, 2, 3, 3.3.1.1-03 24 Months No 4 3.3.1.1-05 3.3.6.1-21 3.3.6.1-23 3.3.6.2.5 LOGIC SYSTEM FUNCTIONAL SCIS Function: 1, 2, 3, 3.3.1.1-03 24 Months No TEST 4 3.3.1.1-05 3.3.6.1-21 3.3.6.1-23 3.3.6.1-50 3.3.6.1-51 DAEC 4.0-24 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-31 (LLS Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.6.3.1 CHANNEL FUNCTIONAL TEST LLS Function: 3 3.3.6.3-01 92 Days No (outside DW) 3.3.6.3-02 3.3.6.3.2 CHANNEL FUNCTIONAL TEST LLS Function: 1, 2 3.3.1.1-01 92 Days No 3.3.6.3-03 3.3.6.3-04 3.3.6.3.3 CHANNEL CALIBRATION LLS Function: 1 3.3.1.1-01 92 Days No 3.3.6.3.4 CHANNEL CALIBRATION LLS Function: 2 3.3.6.3-04 184 Days No 3.3.6.3.5 CHANNEL CALIBRATION LLS Function: 3 3.3.6.3-02 24 Months No 3.3.6.3.6 LOGIC SYSTEM FUNCTIONAL LLS Function: 1, 2, 3 3.3.1.1-01 24 Months No TEST 3.3.6.3-02 3.3.6.3-04 3.3.6.3-05 DAEC 4.0-25 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3m (SFU Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.7.1.1 CHANNELCHECK SFU Rad Monitors 3.3.6.1-38 24 Hours No 3.3.7.1.2 CHANNEL FUNCTIONAL TEST SFU Rad Monitors 3.3.7.1-01 92 Days No 3.3.7.1-02 3.3.7.1.3 CHANNEL CALIBRATION SFU Rad Monitors 3.3.7.1-02 24 Months No 3.3.7.1.4 LOGIC SYSTEM FUNCTIONAL SFU Rad Monitors 3.3.7.1-02 24 Months No TEST 3.7.4-01 DAEC 4.0-26 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-3n (LOP Instrumentation)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.3.8.1.1 CHANNEL FUNCTIONAL TEST LOP Function: 2a, 2b 3.3.8.1-01 31 Days No 3.3.8.1-02 3.3.8.1.2 CHANNEL FUNCTIONAL TEST LOP Function: la, 3 3.3.8.1-03 12 Months No 3.3.8.1-04 3.3.8.1-05 3.3.8.1.3 CHANNEL CALIBRATION LOP Function: 2a, 2b, 3 3.3.8.1-02 12 Months No 3.3.8.1-05 3.3.8.1.4 CHANNEL CALIBRATION LOP Function: la 3.3.8.1-04 24 Months No 3.3.8.1.5 LOGIC SYSTEM FUNCTIONAL LOP Function: la, 2a, 3.3.8.1-04 24 Months No TEST 2b,3 3.3.8.1-05 3.3.8.1-06 3.7.2-01 3.8.1-07 DAEC 4.0-27 TRMCR-035 Rev. 21

DAEC 0

Teclhical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-4 (Reactor Coolant System)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.4.1.1 Recirculation Pump Speed Recirculation Loops 3.4.2-01 24 Hours Yes Mismatch 3.4.1.2 Power/Flow Map Exclusion Zone Recirculation Loops 3.0.0-01 24 Hours No Check 3.4.2.1 Jet Pump Flow/Pump Speed/dP Jet Pump 3.4.2-01 24 Hours Yes Checks 3.4.2-02 3.4.2-03 3.4.3.2 S/RV Manual Actuation S/RVs 3.4.3-03 24 Months Yes 3.4.4.1 RCS Leakage Checks RCS Leakage 3.0.0-01 12 Hours No 3.4.5.1 RSC Leakage Instrumentation Primary Containment 3.0.0-01 12 Hours No CHANNEL CHECK Air Sampling System 3.4.5.2 RSC Leakage Instrumentation a) Primary Containment 3.0.0-01 31 Days No CHANNEL FUNCTIONAL TEST Air Sampling System 3.4.5-01 b) Equipment Drain 3.4.5-02 Sump Flow Integrator 3.4.5-03 c) Floor Drain Sump Flow Integrator 3.4.5.3 RSC Leakage Instrumentation a) Equipment Drain 3.4.5-04 92 Days No CHANNEL FUNCTIONAL TEST Sump Flow Timer 3.4.5-05 b) Floor Drain Sump 3.4.5-06 Flow Timer I I I I _I DAEC 4.0-28 TRMCR-035 Rev. 21

0 DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-4 (Reactor Coolant System)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.4.5.4 RSC Leakage Instrumentation a) Primary Containment 3.4.5-01 92 Days No CHANNEL CALIBRATION Air Sampling System 3.4.5-03 b) Equipment Drain Sump Flow Integrator c) Floor Drain Sump Flow Integrator 3.4.5.5 RSC Leakage Instrumentation a) Equipment Drain 3.4.5-05 12 Months No CHANNEL CALIBRATION Sump Flow Timer 3.4.5-06 b) Floor Drain Sump Flow Timer 3.4.6.1 DOSE EQUIVALENT 1-131 Check RCS Specific Activity 3.4.6-01 7 Days Yes 3.4.7.1 Verify Forced Circulation RHR Shutdown 3.0.0-01 12 Hours No Cooling - MODE 3 3.4.8.1 Verify Forced Circulation RHR Shutdown 3.0.0-01 12 Hours No Cooling - MODE 4 3.0.0-03 3.4.9.1 RCS Heat-up/Cooldown Log RCS P/T Limits 3.4.9-01 30 Minutes Yes 3.4.9.5 RPV Flange Temperature Check- RCS P/T Limits 3.4.9-02 30 Minutes Yes Bolt-up 3.4.9.6 RPV Flange Temperature Check- RCS P/T Limits 3.4.9-02 30 Minutes Yes

_<80°F 3.4.9.7 RPV Flange Temperature Check - RCS P/T Limits 3.0.0-01 12 Hours Yes

<_100°F 3.0.0-03 3.4.10.1 Steam Dome Pressure Check Reactor Steam Dome 3.0.0-01 12 Hours No Pressure DAEC 4.0-29 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-5 (ECCS & RCIC)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.5.1.1 Discharge Piping Filled with Water HPCI, Core Spray, 3.5.1-13 31 Days No Check LPCI 3.5.1-14 3.5.1-15 3.5.1.2 Valve Position Checks HPCI, Core Spray, 3.0.0-02 31 Days No LPCI 3.5.1.3 Accumulator Supply Check ADS 3.0.0-04 31 Days No 3.5.1.6 Pump Flowrate Check - Low HPCI 3.5.1-06 24 Months Yes Pressure 3.5.1.7 Simulated Auto Actuation Test HPCI, Core Spray, 3.3.5.1-15 24 Months LPCI 3.3.5.1-29 3.3.5.1-30 3.3.5.1-37 3.5.1-03 3.5.1-04 3.5.1-05 3.5.1-07 3.5.1-10 3.5.3-05 3.6.1.3-06 3.8.1-07 3.8.7-01 3.5.1.8 Simulated Auto Actuation Test ADS 3.3.5.1-16 24 Months No 3.5.1.9 Valves Manually Open Check ADS 3.4.3-03 24 Months Yes 3.5.2.1 Suppression Pool Level Check LPCI 3.0.0-01 12 Hours No 3.0.0-03 3.5.2.2 CST & Suppression Pool Level Core Spray 3.0.0-01 12 Hours No Check[ 3.0.0-03 DAEC 4.0-30 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-5 (ECCS & RCIC)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.5.2.3 Discharge Piping Filled with Water Core Spray, LPCI 3.0.0-01 31 Days No Check 3.5.1-13 3.5.2.4 Valve Position Checks Core Spray, LPCI 3.0.0-02 31 Days No 3.5.2.6 Simulated Auto Actuation Test Core Spray, LPCI 3.3.5.1-15 24 Months No 3.3.5.1-29 3.3.5.1-37 3.5.1-03 3.5.1-04 3.6.1.3-06 3.8.1-07 3.8.7-01 3.5.3.1 Discharge Piping Filled with Water RCIC 3.5.3-08 31 Days No Check 3.5.3.2 Valve Position Checks RCIC 3.0.0-02 31 Days No 3.5.3.4 Pump Flowrate Check - Low RCIC 3.5.3-08 24 Months Yes Pressure 3.5.3.5 Simulated Auto Actuation Test RCIC 3.5.3-02 24 Months No 3.5.3-03 3.5.3-04 3.5.3-05 3.5.3-07 DAEC 4.0-31 TRMCR-035 Rev. 21

DAEC Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-6 (Containment)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.6.1.1.2 Suppression Chamber Leak Check Primary Containment 3.6.1.1-05 24 Months No 3.6.1.2.2 Air Lock Door Interlock Check Primary Containment 3.6.1.2-02 24 Months No 3.6.1.3.1 Verify Valves are Closed Purge Valves 3.0.0-02 31 Days No 3.6.1.3.2 Explosive Valve Continuity Check TIP Shear Valve 3.0.0-02 31 Days No 3.6.1.3.4 T-seal Leakage Check Purge Valves 3.6.1.3-01 184 Days No 3.6.1.3.6 Simulated Auto Actuation Test PCIVs 3.3.5.1-29 24 Months No 3.3.5.1-30 3.3.6.1-06 3.3.6.1-09 3.3.6.1-14 3.3.6.1-42 3.3.6.1-49 3.3.6.1-50 3.3.6.1-51 3.6.1.3-06 3.6.1.3.7 Simulated Auto Actuation Test EFCVs 3.6.1.3-04 24 Months No 3.6.1.3-07 3.6.1.3-08 3.6.1.3-09 3.6.1.3-10 3.6.1.4.1 Drywell Air Temperature Check Primary Containment 3.0.0-01 24 Hours No 3.6.1.5.1 Valves Manually Open Check LLS Valves 3.4.3-03 24 Months Yes 3.6.1.5.2 Simulated Auto Actuation Test LLS Valves 3.3.6.3-05 24 Months No 3.6.1.6.1 Verify Valves are Closed Rx Bldg - Suppression 3.0.0-04 14 Days No Chamber VBs 3.6.1.6.2 Valve Assembly Functional Test Rx Bldg - Suppression 3.6.1.6-01 92 Days No Chamber VBs DAEC 4.0-32 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-6 (Containment)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.6.1.6.3 Verify Opening Setpoint Rx Bldg- Suppression 3.6.1.6-01 12 Months No Chamber VBs 3.6.1.7.1 Verify Valves are Closed DW - Suppression 3.0.0-04 14 Days No Chamber VBs 3.6.1.7.2 Valve Assembly Functional Test DW - Suppression 3.6.1.7-01 31 Days No Chamber VBs 3.6.1.7-02 3.6.1.7.3 Verify Opening Setpoint DW - Suppression 3.6.1.7-02 24 Months No Chamber VBs 3.6.2.1.1 Suppression Pool Temperature Primary Containment 3.0.0-01 24 Hours No Check 3.6.2.1-01 3.6.2.2.1 Suppression Pool Level Check Primary Containment 3.0.0-01 24 Hours No 3.6.2.3.1 Valve Position Checks RHR- Suppression 3.0.0-02 31 Days No Pool Cooling 3.6.2.4.1 Nozzle Blockage Air Test RHR - Suppression 3.6.2.4-01 60 Months No Pool Spray 3.6.3.2.1 Oxygen Concentration Check Primary Containment 3.0.0-04 7 Days No 3.6.4.1.1 Verify Equipment Hatch Closure Secondary Containment 3.6.4.1-02 31 Days No 3.6.4.1.2 Verify Door Closure Secondary Containment 3.6.4.1-02 31 Days No 3.6.4.1.3 Verify SGTS Draws 0.25" Vacuum Secondary Containment 3.6.4.1-03 24 Months No Staggered Test Basis 3.6.4.2.1 Verify Isolation Times of Valves & SCIV/Ds 3.6.4.2-01 92 Days No Dampers 3.6.4.2.2 Simulated Auto Actuation Test SCIV/Ds 3.3.6.1-51 24 Months No 3.6.4.3.1 10 Hour Operational Heater Run SGTS 3.6.4.3-01 31 Days No 3.6.4.3.3 Simulated Auto Actuation Test SGTS 3.3.6.1-51 24 Months No DAEC 4.0-33 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-6 (Containment)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.6.4.3.4 Verify Bypass Damper & Fan SGTS 3.6.4.3-03 24 Months No Operation DAEC 4.0-34 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-7 (Plant Systems)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.7.1.1 Verify Valve Positions RHRSW 3.0.0-02 31 Days No 3.7.2.1 Verify River Water Level UHS 3.0.0-01 24 Hours No 3.7.2.2 Verify River Water Temperature UHS 3.0.0-01 24 Hours No 3.7.2.3 Verify River Water Depth UHS 3.0.0-02 7 Days Yes 3.7.2.4 Verify Valve Positions RWS 3.0.0-02(?) 31 Days No 3.7.2.5 Verify River Water Depth UHS 3.7.2-05 92 Days No 3.7.2.6 Simulated Auto Actuation Test RWS 3.7.2-01 24 Months No 3.8.1-07 3.7.3.1 Verify Valve Positions ESW 3.0.0-04 91 Days No 3.7.3.2 Simulated Auto Actuation Test ESW NS540002 24 Months No 3.8.1-07 3.7.4.1 15 Minute Operational Run SFU 3.7.4-05 31 Days No 3.7.4.3 Simulated Auto Actuation Test SFU 3.7.4-01 24 Months No 3.7.5.1 Verify Heat Removal Capability Chillers 3.7.5-01 92 Days No 3.7.5-03 3.7.6.1 Verify Gross Gamma Activity Offgas 3.7.6-01 31 Days Yes 3.7.7.1 Fully Cycle Each Valve Turbine Bypass Valves 3.7.7-01 92 Days No 3.7.7.2 Perform System Functional Test Turbine Bypass Valves 3.7.7-02 24 Months No 3.7.7.3 Verify System Response Time Turbine Bypass Valves 3.7.7-02 24 Months No 3.7.8.1 Verify Pool Water Level Spent Fuel Pool 3.0.0-04 7 Days No 3.7.9.1 20 Minute Operational Test Instrument Air System 3.7.9-01 31 Days No 3.7.9.2 Simulated Auto Actuation Test Instrument Air System 3.7.9-02 92 Days No 3.7.9-03 DAEC 4.0-35 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-8 (Electrical Systems)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.8.1.1 Verify Breaker Alignment & Power Offsite AC Sources 3.8.1-01 7 Days No Availability 3.8.1.2 Verify Start (Slow) - Output EDGs 3.8.1-04 31 Days No Voltage & Frequency 3.8.1-05 3.8.1-06 3.8.1.3 60 Minute Load Test EDGs 3.8.1-04 31 Days Yes 3.8.1-05 3.8.1-06 3.8.1.4 Verify Day Tank Volume EDGs 3.8.1-04 31 Days No 3.8.1-05 3.8.1-06 3.8.1.5 Day Tank Presence of Water Check EDGs 3.8.1-08 31 Days No 3.8.1-09 3.8.1.6 Fuel Oil Transfer Operational Test EDGs 3.8.1-04 31 Days No 3.8.1-05 3.8.1-06 3.8.1.7 Timed (Fast) Start - Voltage & EDGs 3.8.1-06 Frequency Check 3.8.1.8 Verify Slow Transfer Between Offsite AC Sources 3.8.1-07 24 Months Yes Start-up & Stand-by Transformers 3.8.1.9 Load Reject Test EDGs 3.8.1-07 24 Months Yes 3.8.1.10 Verify Automatic Trip Bypass EDGs 3.8.1-07 24 Months Yes 3.8.1.11 Verify Manual Control for EDGs 3.8.1-07 24 Months Yes Transferring Loads to Offsite Power 3.8.1.12 Verify Load Sequence Separation EDGs 3.8.1-07 24 Months Yes DAEC 4.0-36 TRMCR-035 Rev. 21

DAEC 0

Teclnical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-8 (Electrical Systems)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.8.1.13 LOOP-LOCA Test EDGs 3.7.5-03 24 Months Yes 3.8.1-07 3.8.3.1 Verify Volume Fuel Oil 3.0.0-03 31 Days No 3.0.0-04 3.8.1-04 3.8.1-05 3.8.1-06 3.8.3.2 Verify Lube Oil Volume LubeOil 3.0.0-03 31 Days No 3.0.0-04 3.8.1-04 3.8.1-05 3.8.1-06 3.8.3.4 Verify Receiver Air Pressure Starting Air 3.8.1-04 31 Days No 3.8.1-05 3.8.1-06 3.8.1-11 3.8.3.5 Underground Fuel Oil Tank Fuel Oil 3.8.1-08 31 Days No Presence of Water Check 3.8.1-09 3.8.4.1 Verify Terminal Voltage DC Sources 3.8.4-01 7 Days No 3.8.4.2 Battery Terminals Corrosion Check DC Sources 3.8.4-02 92 Days No 3.8.4.3 Battery Condition Visual Checks DC Sources 3.8.4-05 12 Months No 3.8.4.4 Corrosion Removal & Connection DC Sources 3.8.4-05 12 Months No Coating Checks 3.8.4.5 Verify Connection Resistance DC Sources 3.8.4-05 12 Months No 3.8.4.6 Verify Charger Output Voltage & DC Source 3.8.4-06 24 Months Yes Amperage 3.8.4-09 DAEC 4.0-37 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-8 (Electrical Systems)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.8.4.7 Battery Service Test DC Sources 3.8.4-03 24 Months Yes 3.8.4-07 3.8.4.8. Battery Modified Performance DC Sources 3.8.4-04 24 Months Yes Discharge Test 3.8.4-08 3.8.6.1 Verify Category A Limits Batteries 3.8.4-01 7 Days No 3.8.6.2 Verify Category B Limits Batteries 3.8.4-02 92 Days No 3.8.6.3 Verify Electrolyte Temperature Batteries 3.8.4-02 92 Days No 3.8.7.1 Verify Breaker Alignment & Power AC & DC Distribution 3.8.4-02 7 Days No Availability Panels 3.8.7.2 Verify Breaker Coordination- LPCI Swing Bus 3.8.4-01 24 Months No LPCI Swing Bus 3.8.8.1 Verify Breaker Alignment & Power AC & DC Distribution 3.8.4-02 7 Days No Availability Panels DAEC 4.0-38 TRMCR-035 Rev. 21

DAEC 0

Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-10 (Special Operations)

TS SR # Subject TS SSC/Function STP # Frequency SR AR#

Frequency Note?

3.9.1.1 CHANNEL FUNCTION TEST Refueling Interlocks 3.9.1-01 7 Days No 3.9.2.1 Verify Mode Switch Locked in One-Rod-Out Interlock 3.9.1-01 12 Hours No Refuel 3.10.3-02 3.10.3-03 3.10.4-01 3.9.2.2 CHANNEL FUNCTION TEST One-Rod-Out Interlock 3.9.1-01 7 Days Yes 3.10.3-02 3.10.3-03 3.10.4-01 3.9.3.1 Verify Control Rod Position- Full Control Rods 3.0.0-03 12 Hours No In 3.9.5.1 Control Rod Exercise Control Rods 3.10.3-02 7 Days Yes 3.10.3-03 3.10.4-01 3.9.5.2 Verify Accumulator Pressure Control Rods 3.0.0-03 7 Days No 3.9.1-01 3.10.3-02 3.10.3-03 3.10.4-01 3.9.6.1 Verify RPV Water Level RPV Water Level 3.0.0-03 24 Hours No 3.9.7.1 Verify System in Service RHR - Shutdown 3.0.0-03 12 Hours No Cooling (High Water Level) 3.9.8.1 Verify System in Service RHR - Shutdown 3.0.0-03 12 Hours No Cooling (Low Water Level)

DAEC 4.0-39 TRMCR-035 Rev. 21

DAt Technical Requirements Manual Chapter 4.0 (Technical Specification Surveillance Frequency Control Program)

Table 4.0-10 (Special Operations)

TS SR # Subject TS SSC/Function STP 4 Frequency SR AR#

Frequency Note?

3.10.2.1 Verify All Control Rods Inserted Reactor Mode Switch 3.0.0-01 12 Hours No 3.9.1-01 3.10.2.2 Verify No CORE ALTERATIONS Reactor Mode Switch 3.9.1-01 24 Hours No 3.10.3.2 Verify 5x5 Control Rod Array Control Rods 3.10.3-02 24 Hours No Disarmed 3.10.3.3 Verify All Control Rods Inserted Control Rods 3.10.3-02 24 Hours No 3.10.4.2 Verify 5x5 Control Rod Array Control Rods 3.10.4-01 24 Hours No Disarmed 3.10.4.3 Verify All Control Rods Inserted Control Rods 3.10.4-01 24 Hours No 3.10.4.4 Verify Control Block Inserted Control Rods 3.10.4-01 24 Hours No 3.10.5.1 Verify All Control Rods Inserted Control Rods 3.10.5-01 24 Hours No 3.10.5.2 Verify 5x5 Control Rod Array Control Rods 3.10.5-01 24 Hours No Disarmed 3.10.5.3 Verify Control Block Inserted Control Rods 3.10.5-01 24 Hours No 3.10.5.5 Verify No CORE ALTERATIONS Control Rods 3.10.5-01 24 Hours No 3.10.6.1 Verify No Fuel In Core Cell Control Rods 3.0.0-03 24 Hours No 3.10.6.2 Verify All Control Rods Inserted Control Rods 3.0.0-03 24 Hours No 3.10.6.3 Verify Fuel Loading Sequence Control Rods 3.0.0-03 24 Hours No 3.10.8.4 Verify No CORE ALTERATIONS Control Rods ??? 12 Hours No 3.10.8.6 Verify CRD Charging Water Control Rods ??? 7 Days No Header Pressure I II DAEC 4.0-40 TRMCR-035 Rev. 21

Programs and Manuals TR 5.5 Page 1 of 1 TS 5.5.14: Surveillance Frequency Control Pro2ram

Purpose:

This program fully satisfies section 5.5.14 of Technical Specifications Owner: Surveillance Coordinator This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

This will be accomplished by the following procedures:

ACP 1407.6 - SURVEILLANCE FREQUENCY CONTROL PROGRAM ACP 1407.7 - CANDIDATE SELECTION FOR SURVEILLANCE TEST INTERVAL (STI) CHANGE ACP 1407.8 - SURVEILLANCE TEST INTERVAL (STI) EVALUATION FORM INSTRUCTIONS ACP 1407.9 - ENGINEERING EVALUATION OF PROPOSED SURVEILLANCE TEST INTERVAL CHANGES EN-AA- 105-1006 - SURVEILLANCE FREQUENCY CONTROL PRA EVALUATIONS ACP 1407.10 - IMPLEMENTING AND MONITORING OF APPROVED SURVEILLANCE FREQUENCY CHANGE ACP 1407.11 - INDEPENDENT DECISION-MAKING PANEL - ROLES AND RESPONSIBILITIES The process is supported by the following procedures:

ACP 102.19 - PREPARATION, REVIEW AND PROCESSING OF TECHNICAL REQUIREMENTS MANUAL CHANGE REQUESTS References

1) TSCR-120, "Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425, Rev. 3).

2) DAEC License Amendment No. 280.

3) NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

Approvals Preparer Licensing Manager Scheduling Manager Program Engineering Manager

April 25, 2012 TO: TECHNICAL SPECIFICATION DISTRIBUTION Attached is Amendment No. 280 to the Duane Arnold Energy Center Technical Specifications.

Amendment No. 280 {TSCR No. 120} relocates many Surveillance Frequencies to a new TS Program (TS 5.5.14 - Surveillance Frequency Control Program). The actual Frequencies will be in new Tables in the Technical Requirements Manual (TRM). The TRM Change (TRMCR-035) will be distributed separately.

Please update your copy of the Technical Specifications as indicated in the attached Update Instructions.

THIS AMENDMENT BECOME EFFECTIVE 4/27/2012.

IMPORTANT: Holders of Technical Specification Copies are required to sign and date the Notice of Receipt Form below, detach it at the dotted line and:

RETURN IT TO THE ADDRESSEE ALONG WITH THE SHEETS REMOVED FROM THE TECHNICAL SPECIFICATIONS.

Steve Catron Regulatory Affairs Manager Copy No: 14 NRC REGION III Issued To: REGIONAL LIBRARY NOTICE OF RECEIPT OF TECHNICAL SPECIFICATION REVISION To: Pat Vandersee, Licensing Department Duane Arnold Energy Center, 3277 DAEC Road, Palo, IA 52324 This acknowledges receipt of Amendment #280 (TSCR-120) to the Duane Arnold Energy Center Technical Specifications.

Signature: DATE DATE Signature:

April 25, 2012 Page lof 5 DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS UPDATE INSTRUCTIONS TECHNICAL SPECIFICATIONS REMOVE INSERT REMOVE INSERT Operating License Operating License Pg 3.3-56 Pg 3.3-56 Page 3 Page 3 List of Effective List of Effective Pg 3.3-64 Pg 3.3-64 Pages 1-3 Pages 1-3 Pg 1.1-6 Pg 1.1-6 Pg 3.3-67 Pg 3.3-67 Pg 3.1-10 Pg 3.1-10 Pg 3.3-68 Pg 3.3-68 Pg 3.1-17 Pg 3.1-17 Pg 3.3-71 Pg 3.3-71 Pg 3.1-19 Pg 3.1-19 Pg 3.3-74 Pg 3.3-74 Pg 3.1-21 Pg 3.1-21 Pg 3.3-77 Pg 3.3-77 Pg 3.1-22 Pg 3.1-22 Pg 3.4-3 Pg 3.4-3 Pg 3.1-26 Pg 3.1-26 Pg 3.4-5 Pg 3.4-5 Pg 3.2-1 Pg 3.2-1 Pg 3.4-7 Pg 3.4-7 Pg 3.2-2 Pg 3.2-2 Pg 3.4-9 Pg 3.4-9 Pg 3.3-3 Pg 3.3-3 Pg 3.4-12 Pg 3.4-12 Pg 3.3-4 Pg 3.3-4 Pg 3.4-14 Pg 3.4-14 Pg 3.3-5 Pg 3.3-5 Pg 3.4-17 Pg 3.4-17 Pg 3.3-6 Pg 3.3-6 Pg 3.4-19 Pg 3.4-19 Pg 3.3-12 Pg 3.3-12 Pg 3.4-21 Pg 3.4-21 Pg 3.3-13 Pg 3.3-13 Pg 3.4-23 Pg 3.4-23 Pg 3.3-17 Pg 3.3-17 Pg 3.4-25 Pg 3.4-25 Pg 3.3-18 Pg 3.3-18 Pg 3.5-4 Pg 3.5-4 Pg 3.3-19 Pg 3.3-19 Pg 3.5-5 Pg 3.5-5 Pg 3.3-23 Pg 3.3-23 Pg 3.5-6 Pg 3.5-6 Pg 3.3-25 Pg 3.3-25 Pg 3.5-7 Pg 3.5-7 Pg 3.3-26 Pg 3.3-26 Pg 3.5-9 Pg 3.5-9 Pg 3.3-28 Pg 3.3-28 Pg 3.5-10 Pg 3.5-10 Pg 3.3-29 Pg 3.3-29 Pg 3.5-11 Pg 3.5-11 Pg 3.3-31 Pg 3.3-31 Pg 3.5-13 Pg 3.5-13 Pg 3.3-39 Pg 3.3-39 Pg 3.5-14 Pg 3.5-14 Pg 3.3-40 Pg 3.3-40 Pg 3.6-2 Pg 3.6-2 Pg 3.3-48 Pg 3.3-48 Pg 3.6-7 Pg 3.6-7 Pg 3.3-55 Pg 3.3-55 Pg 3.6-13 Pg 3.6-13

April 25, 2012 Page 2of 5 DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS UPDATE INSTRUCTIONS TECHNICAL SPECIFICATIONS (continued)

REMOVE INSERT REMOVE INSERT Pg 3.6-14 Pg 3.6-14 Pg 3.8-16 Pg 3.8-16 Pg 3.6-16 Pg 3.6-16 Pg 3.8-18 Pg 3.8-18 Pg 3.6-18 Pg 3.6-18 Pg 3.8-19 Pg 3.8-19 Pg 3.6-20 Pg 3.6-20 Pg 3.8-20 Pg 3.8-20 Pg 3.6-21 Pg 3.6-21 Pg 3.8-29 Pg 3.8-29 Pg 3.6-23 Pg 3.6-23 Pg 3.8-31 Pg 3.8-31 Pg 3.6-26 Pg 3.6-26 Pg 3.9-2 Pg 3.9-2 Pg 3.6-27 Pg 3.6-27 Pg 3.9-3 Pg 3.9-3 Pg 3.6-29 Pg 3.6-29 Pg 3.9-4 Pg 3.9-4 Pg 3.6-31 Pg 3.6-31 Pg 3.9-5 Pg 3.9-5 Pg 3.6-34 Pg 3.6-34 Pg 3.9-8 Pg 3.9-8 Pg 3.6-36 Pg 3.6-36 Pg 3.9-9 Pg 3.9-9 Pg 3.6-40 Pg 3.6-40 Pg 3.9-12 Pg 3.9-12 Pg 3.6-43 Pg 3.6-43 Pg 3.9-15 Pg 3.9-15 Pg 3.7-2 Pg 3.7-2 Pg 3.10-5 Pg 3.10-5 Pg 3.7-4 Pg 3.7-4 Pg 3.10-8 Pg 3.10-8 Pg 3.7-6 Pg 3.7-6 Pg 3.10-11 Pg 3.10-11 Pg 3.7-9 Pg 3.7-9 Pg 3.10-12 Pg 3.10-12 Pg 3.7-10 Pg 3.7-10 Pg 3.10-14 Pg 3.10-14 Pg 3.7-13 Pg 3.7-13 Pg 3.10-15 Pg 3.10-15 Pg 3.7-15 Pg 3.7-15 Pg 3.10-17 Pg 3.10-17 Pg 3.7-17 Pg 3.7-17 Pg 3.10-22 Pg 3.10-22 Pg 3.7-18 Pg 3.7-18 Pg 3.10-23 Pg 3.10-23 Pg 3.7-20 Pg 3.7-20 Pg 5.0-18a Pg 5.0-18a Pg 3.8-5 Pg 3.8-5 Pg 5.8-18b Pg 3.8-6 Pg 3.8-6 Pg 3.8-7 Pg 3.8-7 Pg 3.8-8 Pg 3.8-8 Pg 3.8-9 Pg 3.8-9 Pg 3.8-10 Pg 3.8-10

April 25, 2012 Page 3of 5 DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS UPDATE INSTRUCTIONS BASES (Vol. 1)

REMOVE INSERT REMOVE INSERT List of Effective List of Effective Pg B 3.3-67 Pg B 3.3-67 Pages 1-5 Pages 1-5 Pg B 3.1-20 Pg B 3.1-20 Pg B 3.3-68 Pg B 3.3-68 Pg B 3.1-21 Pg B 3.1-21 Pg B 3.3-73 Pg B 3.3-73 Pg B 3.1-32 Pg B 3.1-32 Pg B 3.3-74 Pg B 3.3-74 Pg B 3.1-38 Pg B 3.1-38 Pg B 3.3-84 Pg B 3.3-84 Pg B 3.1-42 Pg B 3.1-42 Pg B 3.3-85 Pg B 3.3-85 Pg B 3.1-43 Pg B 3.1-43 Pg B 3.3-86 Pg B 3.3-86 Pg B 3.1-44 Pg B 3.1-44 Pg B 3.3-94 Pg B 3.3-94 Pg B 3.1-48 Pg B 3.1-48 Pg B 3.3-95 Pg B 3.3-95 Pg B 3.1-49 Pg B 3.1-49 Pg B 3.3-137 Pg B 3.3-137 Pg B 3.2-4 Pg B 3.2-4 Pg B 3.3-138 Pg B 3.3-138 Pg B 3.2-10 Pg B 3.2-10 Pg B 3.3-139 Pg B 3.3-139 Pg B 3.3-26 Pg B 3.3-26 Pg B 3.3-148 Pg B 3.3-148 Pg B 3.3-27 Pg B 3.3-27 Pg B 3.3-149 Pg B 3.3-149 Pg B 3.3-28 Pg B 3.3-28 Pg B 3.3-150 Pg B 3.3-150 Pg B 3.3-29 Pg B 3.3-29 Pg B 3.3-186 Pg B 3.3-186 Pg B 3.3-30 Pg B 3.3-30 Pg B 3.3-187 Pg B 3.3-187 Pg B 3.3-31 Pg B 3.3-31 Pg B 3.3-188 Pg B 3.3-188 Pg B 3.3-32 Pg B 3.3-32 Pg B 3.3-198 Pg B 3.3-198 Pg B 3.3-33 Pg B 3.3-33 Pg B 3.3-199 Pg B 3.3-199 Pg B 3.3-34 Pg B 3.3-34 Pg B 3.3-200 Pg B 3.3-200 Pg B 3.3-35 Pg B 3.3-35 Pg B 3.3-207 Pg B 3.3-207 Pg B 3.3-42 Pg B 3.3-42 Pg B 3.3-208 Pg B 3.3-208 Pg B 3.3-43 Pg B 3.3-43 Pg B 3.3-212 Pg B 3.3-212 Pg B 3.3-44 Pg B 3.3-44 Pg B 3.3-213 Pg B 3.3-213 Pg B 3.3-45 Pg B 3.3-45 Pg B 3.3-214 Pg B 3.3-214 Pg B 3.3-54 Pg B 3.3-54 Pg B 3.3-222 Pg B 3.3-222 Pg B 3.3-55 Pg B 3.3-55 Pg B 3.3-223 Pg B 3.3-223 Pg B 3.3-56 Pg B 3.3-56 Pg B 3.3-229 Pg B 3.3-229 Pg B 3.3-57 Pg B 3.3-57 Pg B 3.3-230 Pg B 3.3-230

April 25, 2012 Page 4of 5 DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS UPDATE INSTRUCTIONS BASES (Vol 2)

REMOVE INSERT REMOVE INSERT Pg B 3.4-8 Pg B 3.4-8 Pg B 3.6-28 Pg B 3.6-28 Pg B 3.4-13 Pg B 3.4-13 Pg B 3.6-32 Pg B 3.6-32 Pg B 3.4-19 Pg B 3.4-19 Pg B 3.6-35 Pg B 3.6-35 Pg B 3.4-20 Pg B 3.4-20 Pg B 3.6-36 Pg B 3.6-36 Pg B 3.4-25 Pg B 3.4-25 Pg B 3.6-42 Pg B 3.6-42 Pg B 3.4-32 Pg B 3.4-32 Pg B 3.6-47 Pg B 3.6-47 Pg B 3.4-32a Pg B 3.4-32a Pg B 3.6-48 Pg B 3.6-48 Pg B 3.4-36 Pg B 3.4-36 Pg B 3.6-53 Pg B 3.6-53 Pg B 3.4-41 Pg B 3.4-41 Pg B 3.6-57 Pg B 3.6-57 Pg B 3.4-47 Pg B 3.4-47 Pg B 3.6-63 Pg B 3.6-63 Pg B 3.4-54 Pg B 3.4-54 Pg B 3.6-68 Pg B 3.6-68 Pg B 3.4-56 Pg B 3.4-56 Pg B 3.6-76 Pg B 3.6-76 Pg B 3.4-57 Pg B 3.4-57 Pg B 3.6-81 Pg B 3.6-81 Pg B 3.4-60 Pg B 3.4-60 Pg B 3.6-88 Pg B 3.6-88 Pg B 3.5-13 Pg B 3.5-13 Pg B 3.6-89 Pg B 3.6-89 Pg B 3.5-14 Pg B 3.5-14 Pg B 3.6-94 Pg B 3.6-94 Pg B 3.5-15 Pg B 3.5-15 Pg B 3.6-95 Pg B 3.6-95 Pg B 3.5-16 Pg B 3.5-16 Pg B 3.7-6 Pg B 3.7-6 Pg B 3.5-17 Pg B 3.5-17 Pg B 3.7-10 Pg B 3.7-10 Pg B 3.5-18 Pg B 3.5-18 Pg B 3.7-11 Pg B 3.7-11 Pg B 3.5-19 Pg B 3.5-19 Pg B 3.7-12 Pg B 3.7-12 Pg B 3.5-25 Pg B 3.5-25 Pg B 3.7-17 Pg B 3.7-17 Pg B 3.5-26 Pg B 3.5-26 Pg B 3.7-24B Pg B 3.7-24B Pg B 3.5-30 Pg B 3.5-30 Pg B 3.7-24C Pg B 3.7-24C Pg B 3.5-31 Pg B 3.5-31 Pg B 3.7-29 Pg B 3.7-29 Pg B 3.5-32 Pg B 3.5-32 Pg B 3.7-32 Pg B 3.7-32 Pg B 3.6-5 Pg B 3.6-5 Pg B 3.7-35 Pg B 3.7-35 Pg B 3.6-13 Pg B 3.6-13 Pg B 3.7-36 Pg B 3.7-36 Pg B 3.6-26 Pg B 3.6-26 Pg B 3.7-38 Pg B 3.7-38 Pg B 3.6-27 Pg B 3.6-27 Pg B 3.7-44 Pg B 3.7-44

April 25, 2012 Page 5of 5 DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS UPDATE INSTRUCTIONS BASES (Vol 2) - continued REMOVE INSERT REMOVE INSERT Pg B 3.8-15 Pg B 3.8-15 Pg B 3.9-4 Pg B 3.9-4 Pg B 3.8-16 Pg B 3.8-16 Pg B 3.9-7 Pg B 3.9-7 Pg B 3.8-17 Pg B 3.8-17 Pg B 3.9-8 Pg B 3.9-8 Pg B 3.8-18 Pg B 3.8-18 Pg B 3.9-10 Pg B 3.9-10 Pg B 3.8-19 Pg B 3.8-19 Pg B 3.9-18 Pg B 3.9-18 Pg B 3.8-20 Pg B 3.8-20 Pg B 3.9-21 Pg B 3.9-21 Pg B 3.8-21 Pg B 3.8-21 Pg B 3.9-26 Pg B 3.9-26 Pg B 3.8-22 Pg B 3.8-22 Pg B 3.9-31 Pg B 3.9-31 Pg B 3.8-24 Pg B 3.8-24 Pg B 3.10-10 Pg B 3.10-10 Pg B 3.8-37 Pg B 3.8-37 Pg B 3.10-15 Pg B 3.10-15 Pg B 3.8-39 Pg B 3.8-39 Pg B 3.10-20 Pg B 3.10-20 Pg B 3.8-40 Pg B 3.8-40 Pg B 3.10-25 Pg B 3.10-25 Pg B 3.8-47 Pg B 3.8-47 Pg B 3.10-28 Pg B 3.10-28 Pg B 3.8-48 Pg B 3.8-48 Pg B 3.10-37 Pg B 3.10-37 Pg B 3.8-49 Pg B 3.8-49 Pg B 3.10-38 Pg B 3.10-38 Pg B 3.8-51 Pg B 3.8-51 Pg B 3.8-59 Pg B 3.8-59 Pg B 3.8-71 Pg B 3.8-71 Pg B 3.8-72 Pg B 3.8-72 Pg B 3.8-78 Pg B 3.8-78

- 3rý C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level NextEra Energy Duane Arnold, LLC is authorized to operate the Duane Arnold Energy Center at steady state reactor core power levels not in excess of 1912 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 280, are hereby incorporated in the license. NextEra Energy Duane Arnold, LLC shall operate the facility in accordance with the Technical Specifications.

(a) For Surveillance Requirements (SRs) whose acceptance criteria are modified, either directly or indirectly, by the increase in authorized maximum power level in 2.C.(1) above, in accordance with Amendment No. 243 to Facility Operating License DPR-49, those SRs are not required to be performed until their next scheduled performance, which is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment No. 243.

(b) Deleted.

(3) Fire Protection NextEra Energy Duane Arnold, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the Duane Arnold Energy Center and as approved in the SER dated June 1, 1978, and Supplement dated February 10, 1981, subject to the following provision:

NextEra Energy Duane Arnold, LLC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(4) The licensee is authorized to operate the Duane Arnold Energy Center following installation of modified safe-ends on the eight primary recirculation system inlet lines which are described in the licensee letter dated July 31, 1978, and supplemented by letter dated December 8, 1978.

(5) Physical Protection NextEra Energy Duane Arnold, LLC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, Renewed License No. DPR-49 Amendment 280

Page 1 of 3 LIST OF EFFECTIVE PAGES Appendix A to DPR-49 Technical Specifications Revision Date 4/27/12 Page Date Rev. Page Date Rev. Page Date Rev.

1.1-1 10/30/00 234 3.1-10 04/27/12 280 3.3-29 04/27/12 280 1.1-2 10/30/00 234 3.1-11 11/20/08 271 3.3-30 08/01/98 223 1.1-3 08/21/01 240 3.1-12 08/01/98 223 3.3-31 04/27/12 280 1.1-4 10/30/00 234 3.1-13 08/01/98 223 3.3-32 08/01/98 223 1.1-5 11/07/01 243 3.1-14 11/20/08 271 3.3-33 08/01/98 223 1.1-6 04/27/12 280 3.1-15 08/01/98 223 3.3-34 08/01/98 223 1.1-7 08/01/98 223 3.1-16 08/01/98 223 3.3-35 08/01/98 223 1.1-8 08/01/98 223 3-1-17 04/27/12 280 3.3-36 08/01/98 223 1.2-1 08/01/98 223 3.1-18 08/01/98 223 3.3-37 09/30/09 243 1.2-2 08/01/98 223 3.1-19 04/27/12 280 3.3-38 08/01/98 223 1.2-3 08/01/98 223 3.1-20 08/01/98 223 3.3-39 04/27/12 280 1.3-1 08/01/98 223 3.1-21 04/27/12 280 3.3-40 04/27/12 280 1.3-2 08/01/98 223 3.1-22 04/27/12 280 3.3-41 08/01/98 223 1.3-3 08/01/98 223 3.1-23 04/11/01 236 3.3-42 08/01/98 223 1.3-4 08/01/98 223 3.1-24 08/01/98 223 3.3-43 08/01/98 223 1.3-5 08/01/98 223 3.1-25 09/20/05 259 3.3-44 03/27/02 245 1.3-6 08/01/98 223 3.1-26 04/27/12 280 3.3-45 03/27/02 245 1.3-7 08/01/98 223 3.2-1 04/27/12 280 3.3-46 08/01/98 223 1.3-8 08/01/98 223 3.2-2 04/27/12 280 3.3-47 08/01/98 223 1.3-9 08/01/98 223 3.2-3 08/01/98 223 3.3-48 04/27/12 280 1.3-10 08/01/98 223 3.3-1 08/01/98 223 3.3-49 08/01/98 223 1.3-11 08/01/98 223 3.3-2 11/07/01 243 3.3-50 08/01/98 223 1.3-12 08/01/98 223 3.3-3 04/27/12 280 3.3-51 08/01/98 223 1.3-13 08/01/98 223 3.3-4 04/27/12 280 3.3-52 06/29/00 231 1.4-1 07/11/05 258 3.3-5 04/27/12 280 3.3-53 08/01/98 223 1.4-2 07/11/05 258 3.3-6 04/27/12 280 3.3-54 08/01/98 223 1.4-3 07/11/05 258 3.3-7 11/07/01 243 3.3-55 04/27/12 280 1.4-4 07/11/05 258 3.3-8 08/01/98 223 3.3-56 04/27/12 280 1.4-5 11/20/08 271 3.3-9 11/07/01 243 3.3-57 02/09/07 261 1.4-6 07/11/05 258 3.3-10 08/01/98 223 3.3-58 08/01/98 223 1.4-7 07/11/05 258 3.3-11 08/01/98 223 3.3-59 06/29/00 231 1.4-8 07/11/05 258 3.3-12 04/27/12 280 3.3-60 06/29/00 231 2.0-1 11/07/01 243 3.3-13 04/27/12 280 3.3-61 08/01/98 223 3.0-1 04/29/11 277 3.3-14 08/01/98 223 3.3-62 08/01/98 223 3.0-2 04/18/05 255 3.3-15 08/01/98 223 3.3-63 08/01/98 223 3.0-3 04/29/11 277 3.3-16 08/01/98 223 3.3-64 04/27/12 280 3.0-3a 04/29/11 277 3.3-17 04/27/12 280 3.3-65 05/16/01 237 3.0-4 07/30/02 246 3.3-18 04/27/12 280 3.3-66 04/18/05 255 3.0-5 04/18/05 255 3.3-19 04/27/12 280 3.3-67 04/27/12 280 3.1-1 08/01/98 223 3.3-20 04/18/08 268 3.3-68 04/27/12 280 3.1-2 08/01/98 223 3.3-21 04/18/05 255 3.3-69 08/01/98 223 3.1-3 08/01/98 223 3.3-22 08/01/98 223 3.3-70 08/01/98 223 3.1-4 08/01/98 223 3.3-23 04/27/12 280 3.3-71 04/27/12 280 3.1-5 08/01/98 223 3.3-24 07/06/04 254 3.3-72 08/01/98 223 3.1-6 08/01/98 223 3.3-25 04/27/12 280 3.3-73 08/01/98 223 3.1-7 08/01/98 223 3.3-26 04/27/12 280 3.3-74 04/27/12 280 3.1-8 11/20/08 271 3.3-27 10/01/09 243 3.3-75 06/12/09 273 3.1-9 08/01/98 223 3.3-28 04/27/12 280 3.3-76 08/01/98 223

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3.3-77 04/27/12 280 3.6-9 10/30/00 234 3.7-14 08/01/98 223 3.4-1 08/01/98 223 3.6-10 10/30/00 234 3.7-15 04/27/12 280 3.4-2 08/01/98 223 3.6-11 10/30/00 234 3.7-16 11/07/01 243 3.4-3 04/27/12 280 3.6-12 10/30/00 234 3.7-17 04/27/12 280 3.4-4 08/01/98 223 3.6-13 04/27/12 280 3.7-18 04/27/12 280 3.4-5 04/27/12 280 3.6-14 04/27/12 280 3.7-19 07/02/99 227 3.4-6 08/01/98 223 3.6-15 4/16/10 276 3.7-20 04/27/12 280 3.4-7 04/27/12 280 3.6-16 04/27/12 280 3.8-1 04/18/05 255 3.4-8 08/01/98 223 3.6-17 08/01/98 223 3.8-2 08/01/98 223 3.4-9 04/27/12 280, 3.6-18 04/27/12 280 3.8-3 09/26/08 270 3.4-10 04/18/05 255 3.6-19 08/01/98 223 3.8-4 09/26/08 270 3.4-11 04/18/05 255 3.6-20 04/27/12 280 3.8-5 04/27/12 280 3.4-12 04/27/12 280 3.6-21 04/27/12 280 3.8-6 04/27/12 280 3.4-13 04/16/10 255 3.6-22 08/01/98 223 3.8-7 04/27/12 280 3.4-14 04/27/12 280 3.6-23 04/27/12 280 3.8-8 04/27/12 280 3.4-15 04/18/05 255 3.6-24 08/01/98 223 3.8-9 04/27/12 280 3.4-16 08/01/98 223 3.6-25 08/01/98 223 3.8-10 04/27/12 280 3.4-17 04/27/12 280 3.6-26 04/27/12 280 3.8-11 08/01/98 223 3.4-18 10/30/00 234 3.6-27 04/27/12 280 3.8-12 08/01/98 223 3.4-19 04/27/12 280 3.6-28 08/01/98 223 3.8-13 10/30/00 234 3.4-20 08/01/98 223 3.6-29 04/27/12 280 3.8-14 08/01/98 223 3.4-21 04/27/12 280 3.6-30 08/01/98 223 3.8-15 08/01/98 223 3.4-22 08/01/98 223 3.6-31 04/27/12 280 3.8-16 04/27/12 280 3.4-23 04/27/12 280 3.6-32 07/27/07 265 3.8-17 11/22/02 247 3.4-24 08/31/03 253 3.6-33 07/27/07 265 3.8-18 04/27/12 280 3.4-25 04/27/12 280 3.6-34 04/27/12 280 3.8-19 04/27/12 280 3.5-1 04/18/05 255 3.6-35 05/16/01 237 3.8-20 04/27/12 280 3.5-2 08/01/98 223 3.6-36 04/27/12 280 3.8-21 08/01/98 223 3.5-3 08/01/98 223 3.6-37 05/16/01 237 3.8-22 08/01/98 223 3.5-4 04/27/12 280 3.6-38 10/30/00 234 3.8-23 10/30/00 234 3.5-5 04/27/12 280 3.6-39 05/16/01 237 3.8-24 10/30/00 234 3.5-6 04/27/12 280 3.6-40 04/27/12 280 3.8-25 04/27/12 280 3.5-7 04/27/12 280 3.6-41 05/16/01 237 3.8-26 08/01/98 223 3.5-8 08/01/98 223 3.6-42 05/16/01 237 3.8-27 08/01/98 223 3.5-9 04/27/12 280 3.6-43 04/27/12 280 3.8-28 08/01/98 223 3.5-10 04/27/12 280 3.7-1 04/18/05 255 3.8-29 04/27/12 280 3.5-11 04/27/12 280 3.7-2 04/27/12 280 3.8-30 08/01/98 223 3.5-12 04/18/05 255 3.7-3 08/01/98 223 3.8-31 04/27/12 280 3.5-13 04/27/12 280 3.7-4 04/27/12 280 3.9-1 08/01/98 223 3.5-14 04/27/12 280 3.7-5 08/01/98 223 3.9-2 04/27/12 280 3.6-1 08/01/98 223 3.7-6 04/27/12 280 3.9-3 04/27/12 280 3.6-2 04/27/12 280 3.7-7 12/18/08 269 3.9-4 04/27/12 280 3.6-3 08/01/98 223 3.7-8 12/18/08 269 3.9-5 04/27/12 280 3.6-4 08/01/98 223 3.7-9 04/27/12 280 3.9-6 08/01/98 223 3.6-5 08/01/98 223 3.7-10 04/27/12 280 3.9-7 08/01/98 223 3.6-6 08/01/98 223 3.7-11 01/18/08 267 3.9-8 04/27/12 280 3.6-7 04/27/12 280 3.7-12 01/18/08 267 3.9-9 04/27/12 280 3.6-8 08/01/98 223 3.7-13 04/27/12 280 3.9-10 10/30/00 234

Page 3 of 3 LIST OF EFFECTIVE PAGES Appendix A to DPR-49 Technical Specifications Revision Date 4/27/12 Papfe Date Rev. Page Date Rev. Paae Date Rev.

3.9-11 08/01/98 223 5.0-18 4/16/10 276 3.9-12 04/27/12 280 5.0-18a 04/27/12 280 3.9-13 10/30/00 234 5.0-18b 04/27/12 280 3.9-14 08/01/98 223 5.0-19 03/11/05 256 3.9-15 04/27/12 280 5.0-20 03/11/05 256 3.10-1 07/27/07 264 5.0-21 08/01/98 223 3.10-2 08/01/98 223 5.0-22 11/22/02 248 3.10-3 08/01/98 223 5.0-23 11/22/02 248 3.10-4 08/01/98 223 5.0-24 11/22/02 248 3.10-5 04/27/12 280 5.0-25 11/22/02 248 3.10-6 08/01/98 223 3.10-7 08/01/98 223 3.10-8 04/27/12 280 3.10-9 08/01/98 223 3.10-10 08/01/98 223 3.10-11 04/27/12 280 3.10-12 04/27/12 280 3.10-13 08/01/98 223 3.10-14 04/27/12 280 3.10-15 04/27/12 280 3.10-16 08/01/98 223 3.10-17 04/27/12 280 3.10-18 08/01/98 223 3.10-19 08/01/98 223 3.10-20 08/01/98 223 3.10-21 08/01/98 223 3.10-22 04/27/12 280 3.10-23 04/27/12 280 4.0-1 08/01/98 223 4.0-2 07/16/99 226 4.0-3 08/01/98 223 5.0-1 08/01/98 223 5.0-2 08/01/98 223 5.0-3 10/01/09 274 5.0-4 11/22/02 248 5.0-5 08/01/98 223 5.0-6 08/01/98 223 5.0-7 10/30/00 234 5.0-8 07/11/05 258 5.0-9 08/01/98 223 5.0-10 11/22/02 248 5.0-11 10/30/00 234 5.0-12 08/01/98 223 5.0-13 01/26/01 235 5.0-14 08/01/98 223 5.0-15 10/30/00 234 5.0-16 10/12/01 241 5.0-17 4/16/10 276

Definitions 1.1 1.1 Definitions (continued)

SHUTDOWN MARGIN SDM shall be the amount of reactivity by which the (SDM) reactor is subcritical or would be subcritical assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68°F (200C); and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn with the core in its most reactive state during the operating cycle.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

(continued)

DAEC 1.1-6 Amendment 280

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. In accordance with the Surveillance Frequency Control Program SR 3.1.3.2 ------------------- NOTE ---------------

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than 20% RTP.

Insert each withdrawn control rod at least one In accordance with notch. the Surveillance Frequency Control Program SR 3.1.3.3 Verify each control rod scram time from fully In accordance withdrawn to notch position 04 is with SR 3.1.4.1

< 7 seconds. and SR 3.1.4.2 SR 3.1.3.4 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling (continued)

DAEC 3.1-10 Amendment 280

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control rod C.1 Verify all control rods Immediately upon scram accumulators associated with discovery of charging inoperable with reactor inoperable water header steam dome pressure accumulators are pressure

< 900 psig. fully inserted. < 940 psig AND C.2 Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod inoperable.

D. Required Action and D.1 --------- NOTE------

associated Not applicable if all Completion Time of inoperable control Required Action B.1 rod scram or C.1 not met. accumulators are associated with fully inserted control rods.

Place the reactor Immediately mode switch in the Shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator In accordance with pressure is >_940 psig. the Surveillance Frequency Control Program DAEC 3.1-17 Amendment 280

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Nine or more OPERABLE B.1 --------- NOTE-------

control rods not in Rod Worth Minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1.

Suspend withdrawal of Immediately control rods.

AND B.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the Shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply In accordance with with BPWS. the Surveillance Frequency Control Program DAEC 3.1-19 Amendment 280

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate In accordance with solution is within the limits of Figure 3.1.7-1. the Surveillance Frequency Control Program SR 3.1.7.2 Verify temperature of sodium pentaborate solution In accordance with is within the limits of Figure 3.1.7-2. the Surveillance Frequency Control Program SR 3.1.7.3 Verify temperature of pump suction piping is within In accordance with the limits of Figure 3.1.7-2. the Surveillance Frequency Control Program SR 3.1.7.4 Verify continuity of explosive charge. In accordance with the Surveillance Frequency Control Program SR 3.1.7.5 Verify the concentration of boron in solution In accordance with is within the limits of Figure 3.1.7-1. the Surveillance Frequency Control Program AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or boron is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 (continued)

DAEC 3.1-21 Amendment 280

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each pump develops a flow rate In accordance with

_>26.2 gpm at a discharge pressure Ž_ 1150 the Inservice psig. Testing Program SR 3.1.7.7 Verify flow through one SLC subsystem from In accordance with pump into reactor pressure vessel, the Surveillance Frequency Control Program SR 3.1.7.8 Verify all heat traced piping between storage In accordance with tank and pump suction is unblocked, the Surveillance Frequency Control Program AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 DAEC 3.1-22 Amendment 280

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 - ------------------NOTE -------------

Not required to be met on vent and drain valves closed during the performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is In accordance with open. the Surveillance Frequency Control Program SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully In accordance closed and fully open position. with the Inservice Testing Program SR 3.1.8.3 Verify each SDV vent and drain valve: In accordance with the Surveillance

a. Closes in < 30 seconds after receipt Frequency Control of an actual or simulated scram Program signal; and

b. Opens when the actual or simulated scram signal is reset.

DAEC 3.1-26 Amendment 280

APLHGR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER Ž21.7% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. within limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 21.7%

Time not met. RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal to Once within the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

Ž21.7% RTP AND In accordance with the Surveillance Frequency Control Program DAEC 3.2-1 Amendment 280

MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY: THERMAL POWER >_21.7% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits, within limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 21.7%

Time not met. RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to Once within the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

_21.7% RTP AND In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.2-2 Amendment 280

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

NOTES --------------------------

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.2 --------------------- NOTE----------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER Ž 21.7% RTP.

Verify the absolute difference between the In accordance with the Average Power Range Monitor (APRM) Surveillance Frequency channels and the calculated power is Control Program

< 2% RTP plus any gain adjustment required by LCO 3.4.1, "Recirculation Loops Operating," while operating at _> 21.7% RTP.

SR 3.3.1.1.3 Perform a functional test of each In accordance with the automatic scram contactor. Surveillance Frequency Control Program SR 3.3.1.1.4 -- --------------- NOTE --------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.3-3 Amendment 280

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 Verify the Source Range Monitor (SRM) and Prior to withdrawing Intermediate Range Monitor (IRM) channels SRMs from the fully overlap, inserted position SR 3.3.1.1.7 --------------------- NOTE -------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10 Calibrate the trip units. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.3-4 Amendment 280

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.12 ---------------- NOTES--------------

1. Neutron detectors are excluded.

2. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

In accordance with the Perform CHANNEL CALIBRATION.

Surveillance Frequency Control Program SR 3.3.1.1.13 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.14 ------------------ NOTES --------------

1. Neutron detectors are excluded.

2. For Function 1, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

In accordance with the Perform CHANNEL CALIBRATION. Surveillance Frequency Control Program SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.16 Verify Turbine Stop Valve-Closure and In accordance with the Turbine Control Valve Fast Closure, Trip Oil Surveillance Frequency Pressure - Low Functions are not Control Program bypassed when THERMAL POWER is

Ž 26% RTP. I (continued)

DAEC 3.3-5 Amendment 280

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.17 Adjust the channel to conform to a calibrated In accordance with the flow signal. Surveillance Frequency Control Program SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within In accordance with the limits. Surveillance Frequency Control Program SR 3.3.1.1.19 Verify the RPS logic system response time is In accordance with the within limits. Surveillance Frequency Control Program DAEC 3.3-6 Amendment 280

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS

NOTE Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.2 ----------------- NOTES --------------

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is In accordance with located in the Surveillance Frequency Control

a. The fueled region; Program

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.3-12 Amendment 280

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.4 ------------- NOTE----------------

Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

In accordance with Verify count rate is > 3.0 cps. the Surveillance Frequency Control Program SR 3.3.1.2.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.6 --------------- NOTE ----------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.7 --------------- NOTES---------------

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

In accordance with Perform CHANNEL CALIBRATION. the Surveillance Frequency Control Program DAEC, 3.3-13 Amendment 280

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more Reactor E.1 Suspend control rod Immediately Mode Switch - withdrawal.

Shutdown Position channels inoperable. AND E.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS

NOTES- ---------------------------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.3-17 Amendment 280

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued) I SURVEILLANCE FREQUENCY SR 3.3.2.1.2 ---------------

NOTE ----------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at

_<10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program i

SR 3.3.2.1.3 -NOTE

---

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is < 10 % RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.1.4 --------------

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

Neutron detectors are excluded.

Verify the RBM: In accordance with the Surveillance

a. Low Power Range - Upscale Function is Frequency Control not bypassed when THERMAL POWER is Program

_>29% and < 64% RTP.

b. Intermediate Power Range - Upscale Function is not bypassed when THERMAL POWER is >_64% and < 84% RTP.

c. High Power Range - Upscale Function is not bypassed when THERMAL POWER is

_>84% RTP.

(continued)

DAEC 3.3-18 Amendment 280

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.5 ----------------- NOTE -------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.2.1.6 ----------------- NOTE -------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.1.7 Verify control rod sequences input to the RWM Prior to declaring are in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM DAEC 3.3-19 Amendment 280

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS

GTE These SRs apply to each Function in Table 3.3.3.1-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.3.1.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance, Frequency Control Program DAEC 3.3-23 Amendment 280

Remote Shutdown System 3.3.3.2 3.3 INSTRUMENTATION 3.3.3.2 Remote Shutdown System LCO 3.3.3.2 The Remote Shutdown System Functions shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

NOTE--

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable. Function to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Verify each required control circuit and In accordance with transfer switch is capable of performing the the Surveillance intended function. Frequency Control Program (continued)

DAEC 3.3-25 Amendment 280

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.3.2.2 Perform CHANNEL CALIBRATION for each In accordance with required instrumentation channel. the Surveillance Frequency Control Program DAEC 3.3-26 Amendment 280

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with EOC-RPT trip capability.

capability not maintained. OR AND B.2 Apply the MCPR limit 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for inoperable MCPR limit for EOC-RPT as inoperable EOC-RPT specified in the COLR.

not made applicable.

C. Required Action and C.1 Remove the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion associated Time not met. recircluation pump from service.

OR C.2 Reduce THERMAL POWER to < 26% 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months RTP.

SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.3-28 Amendment 280

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.2 Perform CHANNEL CALIBRATION. The In accordance with Allowable Values shall be: the Surveillance Frequency Control TSV - Closure: _<10% closed; and Program TCV Fast Closure, Trip Oil Pressure - Low:

> 465 psig.

SR 3.3.4.1.3 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST including breaker actuation. the Surveillance Frequency Control Program SR 3.3.4.1.4 Verify TSV - Closure and TCV Fast Closure, In accordance with Trip Oil Pressure - Low Functions are not the Surveillance bypassed when THERMAL POWER is Ž> 26 % Frequency Control RTP. Program SR 3.3.4.1.5 Verify the EOC-RPT SYSTEM RESPONSE In accordance with TIME is within limits, the Surveillance Frequency Control Program DAEC 3.3-29 Amendment 280

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK on the Reactor In accordance with Vessel Water Level - Low Low Function. the Surveillance Frequency Control Program SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The In accordance with Allowable Values shall be: the Surveillance Frequency Control

a. Reactor Vessel Water Level - Low Low Program

>_112.65 inches; and

b. Reactor Steam Dome Pressure - High:

< 1154.2 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST including breaker actuation. the Surveillance Frequency Control Program DAEC 3.3-31 Amendment 280

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

NOTES ----------------------------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1.d, 2.f, 3.c, 3.d, 3.e, and 3.f; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 1.d, 2.f, 3.c, 3.d, 3.e, and 3.f provided the associated Function (or the redundant Function for Functions 4 and 5) maintains ECCS initiation or loop selection capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform CHANNEL FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program (continued)

DAEC 3.3-39 Amendment 280

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.1.6 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.7 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.8 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.9 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program DAEC 3.3-40 Amendment 280

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

NOTES ---------------------------

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2 and 3; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Function 1 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program DAEC 3.3-48 Amendment 280

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

NOTES -----------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Function 5.a; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 5.a provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.4 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)

DAEC. 3.3-55 Amendment 280

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.6 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.8 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.9 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program DAEC 3.3-56 Amendment 280

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

NOTES- ----------------------------

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains secondary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.2 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.3 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program DAEC 3.3-64 Amendment 280

LLS Instrumentation 3.3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare the Immediately associated Completion associated LLS Time of Condition A, B, valve(s) inoperable.

or C not met.

OR Both LLS valves inoperable due to inoperable channels.

SURVEILLANCE REQUIREMENTS

NOTES----------------------------

1. Refer to Table 3.3.6.3-1 to determine which SRs apply for each Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains LLS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL FUNCTIONAL TEST for In accordance with portion of the channel outside primary the Surveillance containment. Frequency Control Program SR 3.3.6.3.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.3-67 Amendment 280

LLS Instrumentation 3.3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.3.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.3.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.3.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.3.6 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program DAEC 3.3-68 Amendment 280

SFU System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the other channel is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. The In accordance with Allowable Value shall be < 5 mR/hr. the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program DAEC 3.3-71 Amendment 280

LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS

N-NOTES ----------------------------

1. Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided the associated Function maintains DG initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.5 Perform LOGIC SYSTEM FUNCTIONAL In accordance with TEST. the Surveillance Frequency Control Program DAEC 3.3-74 Amendment 280

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully Immediately associated Completion Time insert all insertable of Condition A or B not met control rods in core in MODE 3, 4 or 5 with any cells containing one control rod withdrawn from a or more fuel core cell containing one or assemblies.

more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 ----------------- NOTE . ----- -------

Only required to be performed prior to entering MODE 2 or 3 from MODE 4, when in MODE 4 for _>24 hours.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The In accordance with Allowable Values shall be: the Surveillance Frequency Control

a. Overvoltage___ 132 V. Program

b. Undervoltage _ 108 V.

c. Underfrequency > 57 Hz.

SR 3.3.8.2.3 Perform a system functional test. In accordance with the Surveillance Frequency Control Program DAEC 3.3-77 Amendment 280

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 -------------------- NOTE --------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

.................................................................

Verify recirculation pump speed mismatch with In accordance with both recirculation pumps at steady state the Surveillance operation is as follows: Frequency Control Program

a. The speed of the faster pump shall be <

135% of the speed of the slower pump when operating at < 69.4 % RTP.

b. The speed of the faster pump shall be <

122% of the speed of the slower pump when operating at Ž 69.4 % RTP.

SR 3.4.1.2 Verify core flow as a function of core THERMAL In accordance with POWER is outside the Exclusion Region shown the Surveillance in the COLR. Frequency Control Program DAEC 3.4-3 Amendment 280

Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 NOTES ----------------

1. Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the associated recirculation loop is in operation.

2. Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 21.7% RTP.

3. Criterion c is only applicable when pump speed is < 60% rated speed.

Verify at least one of the following criteria (a, b In accordance with or c, as applicable) is satisfied for each the Surveillance operating recirculation loop: Frequency Control Program

a. Recirculation pump flow to speed ratio differs by < 5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by < 5% from established patterns.

b. Each jet pump diffuser to lower plenum differential pressure differs by _ 20% from established patterns.

c. The recirculation pump flow to speed ratio, jet pump loop flow to recirculation pump speed ratio, and jet pump diffuser to lower plenum differential pressure ratios are evaluated as being acceptable.

DAEC 3.4-5 Amendment 280

SRVs and SVs 3.4.3 SURVEILLANCE REQUIREMENTS I

SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the SRVs In accordance and SVs are as follows: with the Inservice Number of Setpoint Testing SRVs (psig) Program 1 1110 +/- 33.0 1 1120 +/- 33.0 2 1130 +/- 33.0 2 1140 +/- 33.0 Number of Setpoint SVs (psig) 2 1240 +/- 36.0 Following testing, lift settings shall be within +

1%.

SR 3.4.3.2 -NOTE

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each SRV opens when manually In accordance with actuated. the Surveillance Frequency Control Program DAEC 3.4-7 Amendment 280

RCS Operational LEAKAGE 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify source of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of AND Condition A or B not met. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE and In accordance with the unidentified LEAKAGE increase are within limits. Surveillance Frequency Control Program DAEC 3.4-9 Amendment 280

RCS Leakage Detection Instrumentation 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform a CHANNEL CHECK of required In accordance with Primary Containment Air Sampling System. the Surveillance Frequency Control Program SR 3.4.5.2 Perform a CHANNEL FUNCTIONAL TEST of In accordance with required Primary Containment Air Sampling, the Surveillance System instrumentation, equipment drain sump Frequency Control flow integrator, and floor drain sump flow Program integrator.

SR 3.4.5.3 Perform a CHANNEL FUNCTIONAL TEST of In accordance with required equipment drain sump flow timer and the Surveillance floor drain sump flow timer. Frequency Control Program SR 3.4.5.4 Perform a CHANNEL CALIBRATION of required In accordance with Primary Containment Air Sampling System the Surveillance instrumentation, equipment drain sump flow Frequency Control integrator, and floor drain sump flow integrator. Program SR 3.4.5.5 Perform a CHANNEL CALIBRATION of required In accordance with equipment drain sump flow timer and floor drain the Surveillance sump flow timer. Frequency Control Program DAEC 3.4-12 Amendment 280

RCS Specific Activity 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 -------------------- NOTE -------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT In accordance with 1-131 specific activity is _*0.2 p.Ci/gm. the Surveillance Frequency Control Program DAEC 3.4-14 Amendment 280

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 NOTE--------------

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is < the RCIC Steam Supply Line Pressure - Low isolation pressure.

Verify one required RHR shutdown cooling In accordance with subsystem or recirculation pump is operating. the Surveillance Frequency Control Program DAEC 3.4-17 Amendment 280

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in circulation by an discovery of no operation. alternate method. reactor coolant circulation AND AND No recirculation pump in operation. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Monitor reactor Once per hour coolant temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one required RHR shutdown cooling In accordance with subsystem or one recirculation pump is the Surveillance operating. Frequency Control Program DAEC 3.4-19 Amendment 280

RCS P/T Limits 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. NOTE -------- C1 Initiate action to restore Immediately Required Action C.2 parameter(s) to within shall be completed if this limits.

Condition is entered.

AND Requirements of the C.2 Determine RCS is Prior to entering LCO not met in other acceptable for MODE 2 or 3.

than MODES 1, 2, operation.

and 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -NOTE--------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify: In accordance with

a. RCS pressure and RCS temperature are the Surveillance within the applicable limits in Figure Frequency Control 3.4.9-1. Program

b. RCS heatup and cooldown rates are

< 20°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period during inservice leak and hydrostatic testing (Curve A).

c. RCS heatup and cooldown rates are

2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period during non-nuclear heating (Curve B) and nuclear heating (Curve C).

(continued)

DAEC 3.4-21 Amendment 280

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5 --------------

NOTE ---------

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify temperatures at the reactor vessel head In accordance with flange and the shell adjacent to the head flange the Surveillance are _>74 0 F. Frequency Control Program SR 3.4.9.6 NOTE ------------------------

Not required to be performed until 30 minutes after RCS temperature __80'F in MODE 4.

Verify temperatures at the reactor vessel head flange and the shell adjacent to the head In accordance with flange are >_74 0 F. the Surveillance Frequency Control Program SR 3.4.9.7 -------------

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature < 1001F in MODE 4.

Verify temperatures at the reactor vessel head In accordance with flange and the shell adjacent to the head the Surveillance flange are >_74 0 F. Frequency Control Program DAEC 3.4-23 Amendment 280

Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be _ 1025 psig.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within limit, dome pressure to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is < 1025 In accordance with psig. the Surveillance Frequency Control Program DAEC 3.4-25 Amendment 280

ECCS- Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. Two or more low N.1 Enter LCO 3.0.3. Immediately pressure ECCS subsystems inoperable for reasons other than Condition C or D.

OR HPCI System and two or more ADS valves inoperable.

OR HPCI System and two or more low pressure ECCS subsystems inoperable.

OR One ADS valve and two or more low pressure ECCS subsystems inoperable.

OR One ADS valve and HPCI System and one low pressure ECCS subsystem inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray In accordance with subsystem, the piping is filled with water the Surveillance from the pump discharge valve to the Frequency Control injection valve. Program (continued)

DAEC 3.5-4 Amendment 280

ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) I SURVEILLANCE FREQUENCY I

SR 3.5.1.2 --------------------- NOTE -------------------

The low pressure coolant injection (LPCI) system may be considered OPERABLE during alignment and operation for decay heat removal in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem power In accordance with operated and automatic valve in the flow path, that is not the Surveillance locked, sealed, or otherwise secured in position, is in the Frequency Control correct position. Program SR 3.5.1.3 Verify a 100 day supply of nitrogen exists for each ADS In accordance with accumulator. the Surveillance Frequency Control Program SR 3.5.1.4 Verify the following ECCS pumps develop the specified In accordance with flow rate against a system head corresponding to the the Inservice specified reactor pressure. Testing Program SYSTEM HEAD NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray > 2718 gpm 1 > 113 psig LPCI > 4320 gpm 1 > 20 psig (continued)

DAEC 3.5-5 Amendment 280

ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.5 -NOTE

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 1025 and > 940 In accordance with psig, the HPCI pump can develop a flow rate the Inservice

> 2700 gpm against a system head Testing Program corresponding to reactor pressure.

+

SR 3.5.1.6 -NOTE

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 160 psig, the In accordance with HPCI pump can develop a flow rate > 2700 the Surveillance gpm against a system head corresponding to Frequency Control reactor pressure. Program SR 3.5.1.7 ------------ -NOTES --------------

1. Vessel injection /spray may be excluded.

2. For the LPCI System, the Surveillance may be met by any series of sequential and/or overlapping steps, such that the LPCI Loop Select function is tested.

Verify each ECCS injection/spray subsystem In accordance with actuates on an actual or simulated automatic the Surveillance initiation signal. Frequency Control Program (continued)

DAEC 3.5-6 Amendment 280

ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.8 ------------------ NOTE ----------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or In accordance with simulated automatic initiation signal. the Surveillance Frequency Control Program SR 3.5.1.9 ----------------

O-------------------NTE Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each ADS valve opens when manually In accordance with actuated. the Surveillance Frequency Control Program DAEC 3.5-7 Amendment 280

ECCS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore Secondary Completion Time not Containment to met. OPERABLE status.

AND D.2 Initiate action to Immediately restore one Standby Gas Treatment subsystem to OPERABLE status.

AND D.3 Initiate action to Immediately restore isolation capability in each required Secondary Containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required Low Pressure In accordance with Coolant Injection (LPCI) subsystem, the the Surveillance suppression pool water level is _>7.0 ft. Frequency Control Program (continued)

DAEC 3.5-9 Amendment 280

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required Core Spray (CS) In accordance with subsystem, the: the Surveillance Frequency Control

a. Suppression pool water level is _>8.0 ft; or Program

b. -------------- NOTE -------------

Only one required CS subsystem may take credit for this option during OPDRVs.

Condensate storage tank water level in one CST is _11 ft or > 7 ft in both CSTs.

SR 3.5.2.3 Verify, for each required ECCS subsystem, the In accordance with piping is filled with water from the pump the Surveillance discharge valve to the injection valve. Frequency Control Program SR 3.5.2.4 ------------------- NOTE ---------------

One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS subsystem In accordance with power operated and automatic valve in the the Surveillance flow path, that is not locked, sealed, or Frequency Control otherwise secured in position, is in the Program correct position.

(continued)

DAEC 3.5-10 Amendment 280

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each required ECCS pump develops the specified In flow rate against a system head corresponding to the accordance specified reactor pressure.

with the Inservice SYSTEM HEAD Testing NO. CORRESPONDING Program OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF CS > 2718 gpm 1 Ž> 113 psig LPCI > 4320 gpm 1 > 20 psig SR 3.5.2.6 - - - -- - - - - -NOTES --------

1. Vessel injection/spray may be excluded.

2. For the LPCI System, the surveillance may be met by any series of sequential and/or overlapping steps, such that the LPCI Loop Select function is tested.

Verify each required ECCS subsystem actuates on an In accordance actual or simulated automatic initiation signal. with the Surveillance Frequency Control Program DAEC 3.5-11 Amendment 280

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with In accordance with water from the pump discharge valve to the the Surveillance injection valve. Frequency Control Program SR 3.5.3.2 Verify each RCIC System power operated and In accordance with automatic valve in the flow path, that is not the Surveillance locked, sealed, or otherwise secured in position, Frequency Control is in the correct position. Program SR 3.5.3.3 -------------------- NOTE --------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure _<1025 psig and In accordance with

>_ 940 psig, the RCIC pump can develop a flow the Inservice rate > 400 gpm against a system head Testing Program corresponding to reactor pressure.

SR 3.5.3.4 ------------------- NOTE---------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 160 psig, the In accordance with RCIC pump can develop a flow rate >_400 the Surveillance gpm against a system head corresponding to Frequency Control reactor pressure. Program (continued)

DAEC 3.5-13 Amendment 280

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5 ------------------- NOTE ---------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual In accordance with or simulated automatic initiation signal. the Surveillance Frequency Control Program DAEC 3.5-14 Amendment 280

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance leakage rate testing except for primary with the Primary containment air lock testing, in accordance Containment with the Primary Containment Leakage Rate Leakage Rate Program. Program.

SR 3.6.1.1.2 Verify suppression chamber pressure does In accordance with not increase at a rate > 0.009 psi per minute the Surveillance tested over a 10 minute period at a Frequency Control differential pressure of > 1.0 psid. Program DAEC 3.6-2 Amendment 280

Primary Containment Air Lock 3.6.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ---------------- NOTES -------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria Applicable to SR 3.6.1.1.1.

Perform required primary containment air lock In accordance with leakage rate testing in accordance with the the Primary Primary Containment Leakage Rate Testing Containment Program. Leakage Rate The acceptance criterion for air lock testing Testing Program.

is overall air lock leakage rate _<0.05 La when tested at Ž_Pa.

SR 3.6.1.2.2 Verify only one door in the primary In accordance with containment air lock can be opened at a time. the Surveillance Frequency Control Program DAEC 3.6-7 Amendment 280

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 ---------------------- NOTE ---------------

Not required to be met when the 18 inch primary containment purge valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 18 inch primary containment purge In accordance with valve is closed. the Surveillance Frequency Control Program SR 3.6.1.3.2 Verify continuity of the traversing incore In accordance with probe (TIP) shear isolation valve explosive the Surveillance charge. Frequency Control Program SR 3.6.1.3.3 Verify the isolation time of each power In accordance operated automatic PCIV, except for with the MSIVs, is within limits. Inservice Testing Program SR 3.6.1.3.4 Perform leakage rate testing for each primary In accordance with containment purge valve with resilient seals. the Surveillance Frequency Control Program AND Once within 92 days after opening the valve (continued)

DAEC 3.6-13 Amendment 280

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.5 Verify the isolation time of each MSIV is In accordance

> 3 seconds and < 5 seconds, with the Inservice Testing Program SR 3.6.1.3.6 ------------------ NOTE ---------------

For the MSIVs, this SR may be met by any series of sequential, overlapping, or total system steps, such that proper operation is verified.

Verify each automatic PCIV actuates to the In accordance with isolation position on an actual or simulated the Surveillance isolation signal. Frequency Control Program SR 3.6.1.3.7 Verify a representative sample of reactor In accordance with instrumentation line EFCVs actuate on a the Surveillance simulated instrument line break to restrict Frequency Control flow. Program SR 3.6.1.3.8 Remove and test the explosive squib from each In accordance with shear isolation valve of the TIP System. the Inservice Testing Program (continued)

DAEC 3.6-14 Amendment 280

Drywell Air Temperature 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Drywell Air Temperature LCO 3.6.1.4 Drywell average air temperature shall be < 135 0 F.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell average 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within air temperature to within lim it, lim it.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.4.1 Verify drywell average air temperature is In accordance with within limit, the Surveillance Frequency Control Program DAEC 3.6-16 Amendment 280

LLS Valves 3.6.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 ---------------- NOTE--- ----------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each LLS valve opens when manually In accordance with actuated. the Surveillance Frequency Control Program SR 3.6.1.5.2 ------------------ NOTE --------------

Valve actuation may be excluded.

Verify the LLS System actuates on an actual In accordance with or simulated automatic initiation signal. the Surveillance Frequency Control Program DAEC 3.6-18 Amendment 280

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two reactor building-to- D.1 Restore both valves in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months suppression chamber one vacuum breaker vacuum breaker assembly to assemblies with one or OPERABLE status.

two valves inoperable for opening.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 ------------------ NOTES -------------

1. Not required to be met for vacuum breaker assembly valves that are open during Surveillances.

2. Not required to be met for vacuum breaker assembly valves open when performing their intended function.

Verify each vacuum breaker assembly valve In accordance with is closed, the Surveillance Frequency Control Program SR 3.6.1.6.2 Perform a functional test of each vacuum In accordance with breaker assembly valve, the Surveillance Frequency Control Program (continued)

DAEC 3.6-20 Amendment 280

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.6.3 Verify the opening setpoint of each In accordance with vacuum breaker assembly valve is the Surveillance

_ 0.614 psid. Frequency Control Program DAEC 3.6-21 Amendment 280

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 SURVEILLANCE REQUIREMENTS

~1*

SURVEILLANCE FREQUENCY

+

SR 3.6.1.7.1 - NOTE ---------------

Not required to be met for vacuum breakers that are open during Surveillances.

Verify each vacuum breaker is closed. In accordance with the Surveillance Frequency Control Program SR 3.6.1.7.2 Perform a functional test of each required In accordance with vacuum breaker. the Surveillance Frequency Control Program SR 3.6.1.7.3 Verify the opening setting of each required In accordance with vacuum breaker is < 0.5 psid. the Surveillance Frequency Control Program DAEC 3.6-23 Amendment 280

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool E. 1 Depressurize the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months average temperature reactor vessel to

> 120 0 F. < 200 psig.

AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature In accordance with is within the applicable limits, the Surveillance Frequency Control Program AND 5 minutes when performing testing that adds heat to the suppression pool DAEC 3.6-26 Amendment 280

Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be __10.11 ft and

< 10.43 ft.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within limits, pool water level to within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is In accordance with within limits. the Surveillance Frequency Control Program DAEC 3.6-27 Amendment 280

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify by administrative means each RHR In accordance with suppression pool cooling subsystem the Surveillance manual, power operated and automatic Frequency Control valve in the flow path that is not locked, Program sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each RHR pump develops a flow rate In accordance

> 4800 gpm through the associated heat with the exchanger while operating in the suppression Inservice pool cooling mode. Testing Program DAEC 3.6-29 Amendment 280

RHR Suppression Pool Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify by an air test that the suppression In accordance with pool spray header and nozzles are the Surveillance unobstructed. Frequency Control Program DAEC 3.6-31 Amendment 280

Primary Containment Oxygen Concentration 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Primary Containment Oxygen Concentration LCO 3.6.3.2 The primary containment oxygen concentration shall be

< 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15%

RTP prior to reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months oxygen concentration not concentration to within within limit, limit.

B. Required Action and B.1 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion POWER to < 15%

Time not met. RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Verify primary containment oxygen In accordance with concentration is within limits, the Surveillance Frequency Control Program DAEC 3.6-34 Amendment 280

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance with hatches are closed, the Surveillance Frequency Control Program SR 3.6.4.1.2 ---------------- NOTE---------------

Doors in high radiation areas may be verified by administrative means.

Verify that either the outer door(s) or the In accordance with inner door(s) in each secondary containment the Surveillance access opening are closed. Frequency Control Program SR 3.6.4.1.3 Verify each SBGT subsystem can maintain In accordance with

>_0.25 inch of vacuum water gauge in the the Surveillance secondary containment at a flow rate *<4000 Frequency Control cfm. Program DAEC 3.6-36 Amendment 280

SCIV/Ds 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 Verify the isolation time of each power In accordance with operated automatic SCIV/D is within limits, the Surveillance Frequency Control Program SR 3.6.4.2.2 Verify each automatic SCIV/D actuates to In accordance with the isolation position on an actual or the Surveillance simulated actuation signal. Frequency Control Program DAEC 3.6-40 Amendment 280

SBGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SBGT subsystem for >_ 10 In accordance with continuous hours with heaters operating. the Surveillance Frequency Control Program SR 3.6.4.3.2 ------------------- NOTE --------------

When a SBGT subsystem is placed in an inoperable status solely for the performance of VFTP testing required by this Surveillance on the other subsystem, entry into associated Conditions and Required Actions may be delayed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Perform required SBGT filter testing in accordance with the Ventilation Filter Testing In accordance with Program (VFTP). the VFTP SR 3.6.4.3.3 Verify each SBGT subsystem actuates on an In accordance with actual or simulated initiation signal. the Surveillance Frequency Control Program SR 3.6.4.3.4 Verify each SBGT filter cooler bypass In accordance with damper can be opened and the fan started. the Surveillance Frequency Control Program DAEC 3.6-43 Amendment 280

RHRSW System 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Both RHRSW NOTE ----------------

subsystems inoperable Enter applicable Conditions for reasons other than and Required Actions of Condition B. LCO 3.4.7 for RHR shutdown cooling made inoperable by RHRSW System.

D.1 Restore one RHRSW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months subsystem to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each RHRSW subsystem power operated In accordance with and automatic valve in the flow path, that is not the Surveillance locked, sealed, or otherwise secured in position, Frequency Control is in the correct position or can be aligned to the Program correct position.

DAEC 3.7-2 Amendment 280

RWS System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the river water level is _> 725.2 ft mean In accordance with sea level, the Surveillance Frequency Control Program SR 3.7.2.2 Verify the average river water temperature is In accordance with

< 95 0 F. the Surveillance Frequency Control Program SR 3.7.2.3 ------------------ NOTE --------------

Not required to be performed until river depth

< 2 feet at the intake structure.

Verify the river water depth is > 12 inches. In accordance with the Surveillance Frequency Control Program SR 3.7.2.4 Verify each RWS subsystem power operated In accordance with and automatic valve in the flow paths servicing the Surveillance safety related systems or components, that is Frequency Control not locked, sealed, or otherwise secured in Program position, is in the correct position.

SR 3.7.2.5 Verify the river water depth > 12 inches. In accordance with the Surveillance Frequency Control Program SR 3.7.2.6 Verify each RWS subsystem actuates on an In accordance with actual or simulated initiation signal. the Surveillance Frequency Control Program DAEC 3.7-4 Amendment 280

ESW System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 ---------------

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

Isolation of flow to individual components does not render ESW System inoperable.

Verify each ESW subsystem power operated In accordance with and automatic valve in the flow paths the Surveillance servicing safety related systems or Frequency Control components, that is not locked, sealed, or Program otherwise secured in position, is in the correct position.

SR 3.7.3.2 Verify each ESW subsystem actuates on an In accordance with actual or simulated initiation signal. the Surveillance Frequency Control Program DAEC 3.7-6 Amendment 280

SFU System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Both SFU subsystems ----------- NOTE--------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assembles in the secondary F.1 Suspend movement of Immediately containment, during irradiated fuel assemblies CORE ALTERATIONS, in the secondary or during OPDRVs. containment.

OR AND One or more SFU F.2 Suspend CORE Immediately subsystems inoperable ALTERATIONS.

due to an inoperable CBE boundary during AND movement of irradiated fuel assemblies in the F.3 Initiate action to suspend Immediately secondary OPDRVs.

containment, during CORE ALTERATIONS, or during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each SFU subsystem for In accordance with

> 15 minutes. the Surveillance Frequency Control Program SR 3.7.4.2 Perform required SFU filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).

(continued)

DAEC 3.7-9 Amendment 280

SFU System 3.7.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.734.3 Verify each SFU subsystem actuates on an In accordance actual or simulated initiation signal, with the Surveillance Frequency Control Program SR 3.7.4.4 Perform required CBE unfiltered air inleakage In accordance testing in accordance with the Control Building with the Envelope Habitability Program. Control Building Envelope Habitability Program DAEC 3.7-10 Amendment 280

CBC System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and------------------ NOTE ---------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition B not met during movement E.1 Suspend movement Immediately of irradiated fuel of irradiated fuel assemblies in the assemblies in the secondary containment, secondary during CORE containment.

ALTERATIONS, or during OPDRVs. AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each CBC subsystem has the In accordance with capability to remove the available heat load. the Surveillance Frequency Control Program DAEC 3.7-13 Amendment 280

Main Condenser Offgas 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 -NOTE

Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.

Verify the gross gamma activity rate of the In accordance with noble gases is < 1.0 Ci/second after decay of the Surveillance 30 minutes. Frequency Control Program AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a

_>50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level DAEC 3.7-15 Amendment 280

Main Turbine Bypass System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify one complete cycle of each main In accordance with turbine bypass valve. the Surveillance Frequency Control Program SR 3.7.7.2 Perform a system functional test. In accordance with the Surveillance Frequency Control Program SR 3.7.7.3 Verify the TURBINE BYPASS SYSTEM In accordance with RESPONSE TIME is within limits, the Surveillance Frequency Control Program DAEC 3.7-117 Amendment 280

Spent Fuel Storage Pool Water Level 3.7.8 3,7 PLANT SYSTEMS 3.7.8 Spent Fuel Storage Pool Water Level LCO 3.7.8 The spent fuel storage pool water level shall be > 36 ft.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage A.1 -------- NOTE -----

pool water level not LCO 3.0.3 is not within limit. applicable.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify the spent fuel storage pool water In accordance with level is _>36 ft. the Surveillance Frequency Control Program DAEC 3.7-18 Amendment 280

CB/SBGT Instrument Air System 3.7.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Operates each CB/SBGT Instrument Air In accordance with compressor for Ž_20 minutes. the Surveillance Frequency Control Program SR 3.7.9.2 Verify each CB/SBGT Instrument Air In accordance with subsystem actuates on an actual or the Surveillance simulated initiation signal and maintains Frequency Control air pressure > 75 psig in the receiver. Program DAEC 3.7-20 Amendment 280

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated In accordance with power availability for each offsite circuit, the Surveillance Frequency Control Program SR 3.8.1.2 ------------------ NOTES---------------

1. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

3. When a DG is placed in an inoperable status solely for the performance of testing required by Required Actions B.3 or B.4, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Verify each DG starts from standby conditions In accordance with and achieves steady state voltage Ž_3744v the Surveillance and < 4576v and frequency > 59.5Hz and Frequency Control

60.5Hz. Program (continued)

DAEC 3.8-5 Amendment 280

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.3 ------------------- NOTES ---------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded In accordance with and operates for > 60 minutes at a load the Surveillance

> 2750kw and < 2950kw. Frequency Control Program SR 3.8.1.4 Verify each tank contains Ž 220 gal of fuel oil. In accordance with the Surveillance Frequency Control Program SR 3.8.1.5 Check for the presence of water in the fuel oil in In accordance with each day tank and remove water as necessary. the Surveillance Frequency Control Program (continued)

DAEC 3.8-6 Amendment 280

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify the fuel oil transfer system operates to In accordance with transfer fuel oil from storage tank to the day the Surveillance tank. Frequency Control Program SR 3.8.1.7 ------------------- NOTE----------------

All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition In accordance with and achieves: the Surveillance Frequency Control

a. in _<10 seconds, voltage >_3744V and Program frequency >_59.5Hz; and

b. steady state, voltage Ž_ 3744V and _<4576V and frequency > 59.5Hz and < 60.5Hz.

SR 3.8.1.8 -------------------- NOTE ---------------

The Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify automatic slow transfer of AC power In accordance with supply from the Startup Transformer to the the Surveillance Standby Transformer. Frequency Control Program (continued)

DAEC 3.8-7 Amendment 280

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 NOTE --------------

This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DG rejects a load greater than or In accordance with equal to its associated single largest post- the Surveillance accident load, and: Frequency Control

a. Following load rejection, the frequency is Program

___

64.5Hz.

b. Within 1.3 seconds following load rejection, the voltage is >_3744V and

4576V.

c. Within 3.9 seconds following load rejection, the frequency is Ž_59.5Hz and

_<60.5Hz.

SR 3.8.1.10 ------------------- NOTE --------------

This Surveillance shall not be performed in MODE 1, 2 or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DG's automatic trips are bypassed In accordance with on an actual or simulated Loss of Offsite Power the Surveillance (LOOP) signal or on an actual or simulated Frequency Control ECCS initiation signal except: Program

a. Engine overspeed; and

b. Generator lockout.

(continued)

DAEC 3.8-8 Amendment 280

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 -------------------- NOTE -----------------

This Surveillance shall not be performed in MODE 1, 2 or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify under manual control each DG: In accordance with the Surveillance

a. Synchronizes with offsite power source Frequency Control while loaded with emergency loads upon a Program simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

SR 3.8.1.12 ------------------ NOTE ------------------

This Surveillance shall not be performed in MODE 1, 2 or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load In accordance with block is > 2 seconds, the Surveillance Frequency Control Program (continued)

DAEC 3.8-9 Amendment 280

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 4

SR 3.8.1.13 --------- NOTES

--- --------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite In accordance with power signal in conjunction with an actual or the Surveillance simulated ECCS initiation signal: Frequency Control Program

a. De-energization of essential buses;

b. Load shedding from essential buses; and

c. DG auto-start from standby condition and:

1. energizes permanently connected loads in _<10 seconds,

2. energizes auto-connected emergency loads in the proper timed sequence,

3. achieves steady state voltage

>_3744V and _<4576V,

4. achieves steady state frequency

>_59.5Hz and < 60.5Hz, and

5. supplies permanently connected and auto-connected emergency loads for

>_5 minutes.

DAEC 3.8-10 Amendment 280

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify fuel oil storage tank contains In accordance with

>36,317 gal of fuel. the Surveillance Frequency Control Program SR 3.8.3.2 Verify lube oil inventory is > 257 gal for each DG. In accordance with the Surveillance Frequency Control Program SR 3.8.3.3 Verify fuel oil properties of new and stored fuel In accordance with oil are tested in accordance with, and the Diesel Fuel Oil maintained within the limits of, the Diesel Fuel Testing Program Oil Testing Program.

SR 3.8.3.4 Verify required air start receiver pressure is _ In accordance with 150 psig. the Surveillance Frequency Control Program SR 3.8.3.5 Check for the presence of water in the fuel oil in In accordance with the fuel oil storage tank and remove water as the Surveillance necessary. Frequency Control Program DAEC 3.8-16 Amendment 280

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is Ž 126 V on In accordance with float charge for the 125 VDC battery and the Surveillance

_252 V for the 250 VDC battery. Frequency Control Program SR 3.8.4.2 Verify no visible corrosion at battery terminals In accordance with and connectors. the Surveillance Frequency Control OR Program Verify battery connection resistance within limits.

SR 3.8.4.3 Verify battery cells, cell plates, and racks show In accordance with no visual indication of physical damage or the Surveillance abnormal deterioration that could degrade Frequency Control battery performance. Program SR 3.8.4.4 Remove visible corrosion and verify battery cell to In accordance with cell and terminal connections are coated with the Surveillance anti-corrosion material. Frequency Control Program SR 3.8.4.5 Verify battery connection resistance within limits. In accordance with the Surveillance Frequency Control Program (continued)

DAEC 3.8-18 Amendment 280

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

.7

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

This Surveillance shall not be performed on the required battery chargers in MODE 1, 2 or 3.

However, credit may be taken for unplanned events that satisfy this SR.

SR 3.8.4.6 Verify each required battery charger supplies In accordance with

Ž 300 amps at _ 129 V for the 125 VDC the Surveillance subsystem and _ 200 amps at > 258 V for the Frequency Control 250 VDC subsystem. Program SR 3.8.4.7 ---------------

NOTES -------------

1. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7.

2. This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, In accordance with and maintain in OPERABLE status, the Surveillance the required emergency loads for the design Frequency Control duty cycle when subjected to a battery service Program test.

(continued)

DAEC 3.8-19 Amendment 280

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.8 --------------- NOTE ---------------------------

This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is >_80% of the In accordance with manufacturer's rating when subjected to a the Surveillance performance discharge test or a modified Frequency Control performance discharge test. Program AND 12 months when battery shows degradation or has reached 85%

of expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity > 100%

of manufacturer's rating DAEC 3.8-20 Amendment 280

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet Table In accordance with 3.8.6-1 Category A limits, the Surveillance Frequency Control Program SR 3.8.6.2 Verify battery cell parameters meet Table In accordance with 3.8.6-1 Category B limits, the Surveillance Frequency Control Program AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery discharge

< 110 Vfor 125V and < 220 V for 250 V AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery overcharge

> 150 V for 125 V and > 300 V for 250 V SR 3.8.6.3 Verify average electrolyte temperature of In accordance with representative cells is _>651F for each battery. the Surveillance Frequency Control Program DAEC 3.8-25 Amendment 280

Distribution Systems - Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and In accordance with indicated power availability to required AC the Surveillance and DC electrical power distribution Frequency Control subsystems. Program SR 3.8.7.2 Verify proper coordination of the LPCI Swing In accordance with Bus circuit breakers. the Surveillance Frequency Control Program DAEC 3.8-29 Amendment 280

Distribution Systems - Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate actions to Immediately restore required AC and DC electircal power distribution subsytems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and In accordance with indicated power availability to required AC the Surveillance and DC electrical power distribution Frequency Control subsystems. Program DAEC 3.8-31 Amendment 280

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on In accordance with each of the following required refueling the Surveillance equipment interlock inputs: Frequency Control Program

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded,

d. Refuel platform fuel grapple fully retracted position,

e. Refuel platform frame mounted hoist, fuel loaded, and

f. Refuel platform monorail mounted hoist, fuel loaded.

DAEC 3.9-2 Amendment 280

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the Refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one-rod- A.1 Suspend control rod Immediately out interlock inoperable, withdrawal.

AND A.2. Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in Refuel In accordance with position. the Surveillance Frequency Control Program (continued)

DAEC 3.9-3 Amendment 280

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS (continued)

FREQUENCY SURVEILLANCE i

SR 3.9.2.2 ----------------

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

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program DAEC 3.9-4 Amendment 280

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1 Suspend loading fuel Immediately rods not fully inserted, assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. In accordance with the Surveillance Frequency Control Program DAEC 3.9-5 Amendment 280

Control Rod OPERABILITY - Refueling 319.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY - Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to fully Immediately control rods inoperable, insert inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 ------------------- NOTE ---------------

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one In accordance with notch. the Surveillance Frequency Control Program SR 3.9.5.2 Verify each withdrawn control rod scram In accordance with accumulator pressure is > 940 psig. the Surveillance Frequency Control Program DAEC 3.9-8 Amendment 280

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be > 23 ft above the top of the irradiated fuel assemblies seated within the RPV.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of Immediately within limit, fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is Ž_23 ft above the top In accordance with of the irradiated fuel assemblies seated within the Surveillance the RPV. Frequency Control Program DAEC 3.9-9 Amendment 280

RHR-High Water Level 3.9.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. No RHR shutdown C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem circulation by an discovery of no in operation with alternate method, reactor coolant reactor coolant circulation temperature

> 150 0F.

AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is In accordance with operating when reactor coolant temperature is the Surveillance

> 150 OF. Frequency Control Program DAEC 3.9-12 Amendment 280

RHR-Low Water Level 3.9.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem In accordance with is operating. the Surveillance Frequency Control Program DAEC 3.9-15 Amendment 280

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A (continued) A.3.1 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the Shutdown position.

OR A.3.2 ------- NOTE------

Only applicable in MODE 5.

Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the Refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted in core In accordance with cells containing one or more fuel assemblies, the Surveillance Frequency Control Program SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. In accordance with the Surveillance Frequency Control Program DAEC 3.10-5 Amendment 280

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs SR 3.10.3.2 ----------------- NOTE----------------

Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the control rod In accordance with being withdrawn, in a five by five array centered on the Surveillance the control rod being withdrawn, are disarmed. Frequency Control Program SR 3.10.3.3 Verify all control rods, other than the control rod In accordance with being withdrawn, are fully inserted, the Surveillance Frequency Control Program DAEC 3.10-8 Amendment 280

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the B. 1 Suspend withdrawal of Immediately above requirements the control rod and not met with the removal of associated affected control rod not CRD.

insertable.

AND B.2.1 Initiate action to fully Immediately insert all control rods.

OR B.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to the LCOs. applicable SRs SR 3.10.4.2 --------------------- NOTE--- -------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the control In accordance with rod being withdrawn, in a five by five array the Surveillance centered on the control rod being withdrawn, Frequency Control are disarmed. Program (continued)

DAEC 3.10-11 Amendment 280

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the control rod In accordance with being withdrawn, are fully inserted, the Surveillance Frequency Control Program SR 3.10.4.4 ----------------- NOTE -------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is In accordance with inserted, the Surveillance Frequency Control Program DAEC 3.10-12 Amendment 280

Single CRD Removal - Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to fully Immediately insert all control rods.

OR A.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control rod In accordance with withdrawn for the removal of the associated CRD, the Surveillance are fully inserted. Frequency Control Program SR 3.10.5.2 Verify all control rods, other than the control rod In accordance with withdrawn for the removal of the associated CRD, the Surveillance in a five by five array centered on the control rod Frequency Control withdrawn for the removal of the associated CRD, Program are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is inserted. In accordance with the Surveillance Frequency Control Program SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 (continued)

DAEC 3.10-14 Amendment 280

Single CRD Removal - Refueling 3.10.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no other CORE ALTERATIONS are in In accordance with progress. the Surveillance Frequency Control Program DAEC 3.10-15 Amendment 280

Multiple Control Rod Withdrawal - Refueling 3.10.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Initiate action to fully Immediately insert all control rods in core cells containing one or more fuel assemblies.

OR A.3.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed In accordance with from core cells associated with each the Surveillance control rod or CRD removed. Frequency Control Program SR 3.10.6.2 Verify all other control rods in core cells In accordance with containing one or more fuel assemblies are the Surveillance fully inserted. Frequency Control Program SR 3.10.6.3 -------------------- NOTE -------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in In accordance with compliance with an approved reload sequence. the Surveillance Frequency Control Program DAEC 3.10-17 Amendment 280

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for LCO According to the 3.3.1.1, Functions 2.a and 2.d of Table applicable SRs 3.3.1.1-1.

SR 3.10.8.2 -------------------- NOTE --------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for According to the LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1. applicable SRs SR 3.10.8.3 -------------------- NOTE --------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in During control rod compliance with the approved control rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in In accordance with progress. the Surveillance Frequency Control Program (continued)

DAEC 3.10-22 Amendment 280

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure In accordance with

_970 psig. the Surveillance Frequency Control Program DAEC 3.10-23 Amendment 280

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Control Building Envelope Habitability Program (continued)

c. Requirements for (i) determining the unfiltered air inleakage past the CBE boundary into the CBE in accordance with the testing methods and at the Frequencies specified in Sections C. 1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CBE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement, at designated locations, of the CBE pressure relative to all external areas adjacent to the CBE boundary during the pressurization mode of operation by one subsystem of the SFU System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a Staggered Test Basis . The results shall be trended and used as part of the 24 month assessment of the CBE boundary.

e. The quantitative limits on unfiltered air inleakage into the CBE.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air leakage limits for hazardous chemicals must ensure that the exposure of CBE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CBE habitability, determining CBE unfiltered inleakage, and measuring CBE pressure and assessing the CBE boundary as required by paragraphs c and d, respectively.

(continued)

A Staggered Test Basis shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

DAEC 5.0-1 8a Amendment 280

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies,"

Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

DAEC 5.0-18b Amendment 280

BASES VOLUME 1

Page 1 of 5 LIST OF EFFECTIVE PAGES Appendix A to DPR-49 Technical Specifications Bases Revision Date 04/27/12 Page Date Rev. Page Date Rev- Page Date Rev B 2.0-1 08/01/98 223 B 3.1-18 08/01/98 223 B 3.3-7 11/07/01 044 B 2.0-2 08/01/98 223 B 3.1-19 08/01/98 223 B 3.3-8 11/07/01 044 B 2.0-3 11/07/01 044 B 3.1-20 04/27/12 120 B 3.3-9 08/01/98 223 B 2.0-4 08/01/98 223 B 3.1-21 04/27/12 120 B 3.3-10 05/31/02 057 B 2.0-5 04/09/04 044A B 3.1-22 11/20/08 098 B 3.3-11 08/01/98 223 B 2.0-6 04/09/04 044A B 3.1-23 08/01/98 223 B 3.3-12 08/01/98 223 B 2.0-7 08/01/98 223 B 3.1-24 08/01/98 223 B 3.3-13 02/23/09 102 B 2.0-8 04/09/04 044A B 3.1-25 11/20/08 098 B 3.3-14 04/18/08 100 B 2.0-9 04/09/04 044A B 3.1-26 08/01/98 223 B 3.3-15 08/01/98 223 B 3.0-1 04/29/11 122 B 3.1-27 04/09/04 044A B 3.3-16 08/01/98 223 B 3.0-2 10/30/00 026A B 3.1-28 08/01/98 22 B 3.3-17 08/01/98 223 B 3.0-3 08/01/98 223 B 3.1-29 08/01/98 223 B 3.3-18 08/25/10 123 B 3.0-4 08/01/98 223 B 3.1-30 08/01/98 223 B 3.3-19 11/07/01 044 B 3.0-5 04/18/05 064 B 3.1-3 1 08/01/98 223 B 3.3-20 08/25/10 123 B 3.0-6 04/18/05 064 B 3.1-32 04/27/12 120 B 3.3-21 08/01/98 223 B 3.0-7 04/18/05 064 B 3.1-33 04/09/04 044A B 3.3-22 08/01/98 223 B 3.0-8 04/18/05 064 B 3.1-34 08/01/98 223 B 3.3-23 08/01/98 223 B 3.0-9 04/18/05 064 B 3.1-35 04/18/08 093 B 3.3-24 08/01/98 223 B 3.0-10 04/18/05 064 B 3.1-36 03/25/05 070 B 3.3-25 08/01/98 223 B 3.0-11 04/18/05 064 B 3.1-37 03/25/05 070 B 3.3-26 04/27/12 120 B 3.0-12 04/18/05 029 B 3.1-38 04/27/12 120 B 3.3-27 04/27/12 120 B 3.0-13 06/12/07 079 B 3.1-39 04/11/01 236 B 3.3-28 04/27/12 120 B 3.0-13A 04/29/11 122 B 3.1-40 08/01/98 223 B 3.3-29 04/27/12 120 B 3.0-13B 04/29/11 122 B 3.1-41 08/01/98 223 B 3.3-30 04/27/12 120 B 3.0-13C 04/29/11 122 B 3.1-42 04/27/12 120 B 3.3-31 04/12/12 120 B 3.0-13D 04/29/11 122 B 3.1-43 04/27/12 120 B 3.3-32 04/27/12 120 B 3.0-14 07/11/05 029 B 3.1-44 04/27/12 120 B 3.3-33 04/27/12 120 B 3.0-15 07/11/05 029 B 3.1-45 04/09/04 044A B 3.3-34 04/27/12 120 B 3.0-16 07/11/05 029 B 3.1-46 09/20/05 044A B 3.3-35 04/27/12 120 B 3.0-17 07/11/05 029 B 3.1-47 09/20/05 223 B 3.3-36 04/09/04 044A B 3.0-18 07/11/05 029 B 3.1-48 04/27/12 120 B 3.3-37 08/01/98 223 B 3.0-19 07/11/05 029 B 3.1-49 04/27/12 120 B 3.3-38 08/01/98 223 B 3.1-1 08/01/98 223 B 3.2-1 04/09/04 044A B 3.3-39 08/01/98 223 B 3.1-2 08/01/98 223 B 3.2-2 02/23/09 115 B 3.3-40 08/01/98 223 B 3.1-3 08/01/98 223 B 3.2-3 04/09/04 044A B 3.3-41 08/01/98 223 B 3.1-4 08/01/98 223 B 3.2-4 04/27/12 120 B 3.3-42 04/27/12 120 B 3.1-5 08/01/98 223 B 3.2-5 04/09/04 044A B 3.3-43 04/27/12 120 B 3.1-6 08/01/98 223 B 3.2-6 04/09/04 044A B 3.3-44 04/27/12 120 B 3.1-7 04/09/04 044A B 3.2-7 04/09/04 044A B 3.3-45 04/27/12 120 B 3.1-8 04/09/04 044A B 3.2-8 04/09/04 044A B 3.3-46 08/01/98 223 B 3.1-9 08/01/98 223 B 3.2-9 11/07/01 044 B 3.3-47 08/01/98 223 B 3.1-10 08/01/98 223 B 3.2-10 04/27/12 120 B 3.3-48 08/01/98 223 B 3.1-11 08/01/98 223 B 3.2-11 04/09/04 044A B 3.3-49 04/18/08 093 B 3.1-12 08/01/98 223 B 3.3-1 08/01/98 223 B 3.3-50 03/25/05 070 B 3.1-13 04/09/04 044A B 3.3-2 08/01/98 223 B 3.3-51 03/25/05 070 B 3.1-14 08/01/98 223 B 3.3-3 04/09/04 044A B 3.3-52 03/25/05 070 B 3.1-15 08/01/98 223 B 3.3-4 08/01/98 223 B 3.3-53 03/25/05 070 B 3.1-16 08/01/98 223 B 3.3-5 08/01/98 223 B 3.3-54 04/27/12 120 B 3.1-17 11/20/08 098 B 3.3-6 08/01/98 223 B 3.3-55 04/27/12 120

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B 3.3-56 04/27/12 120 B 3.3-104 08/01/98 223 B 3.3-153 08/01/98 223 B 3.3-57 04/27/12 120 B 3.3-105 08/01/98 223 B 3.3-154 08/01/98 223 B 3.3-57A 04/18/08 093 B 3.3-106 04/09/04 044A B 3.3-155 08/01/98 223 B 3.3-58 07/06/04 067A B 3.3-107 04/09/04 044A B 3.3-156 08/01/98 223 B 3.3-59 07/06/04 067A B 3.3-108 04/09/04 044A B 3.3-157 08/01/98 223 B 3.3-60 10/20/03 065 B 3.3-109 08/01/98 223 B 3.3-158 04/09/04 044A B 3.3-61 10/20/03 065 B 3.3-110 08/01/98 223 B 3.3-159 04/09/04 044A B 3.3-62 10/20/03 065 B 3.3-111 08/01/98 223 B 3.3-160 08/01/98 223 B 3.3-63 09/11/06 088 B 3.3-112 08/01/98 223 B 3.3-161 02/09/07 074A B 3.3-64 04/18/05 064 B 3.3-113 08/01/98 223 B 3.3-162 02/09/07 074A B 3.3-65 04/18/05 064 B 3.3-114 08/01/98 223 B 3.3-163 04/09/04 044A B 3.3-66 07/06/04 067A B 3.3-115 08/01/98 223 B 3.3-164 08/01/98 223 B 3.3-67 04/27/12 120 B 3.3-116 08/01/98 223 B 3.3-165 08/01/98 223 B 3.3-68 04/27/12 120 B 3.3-117 04/09/04 044A B 3.3-166 08/01/98 223 B 3.3-69 07/06/04 067A B 3.3-118 08/01/98 223 B 3.3-167 08/01/98 223 B 3.3-70 08/01/98 223 B 3.3-119 08/01/98 223 B 3.3-168 04/09/04 044A B 3.3-71 08/01/98 223 B 3.3-120 04/09/04 044A B 3.3-169 08/01/98 223 B 3.3-72 04/18/05 064 B 3.3-121 08/01/98 223 B 3.3-170 06/29/00 003 B 3.3-73 04/27/12 120 B 3.3-122 08/01/98 223 B 3.3-171 06/29/00 003 B 3.3-74 04/27/12 120 B 3.3-123 08/01/98 223 B 3.3-172 06/29/00 003 B 3.3-75 08/01/98 223 B 3.3-124 08/01/98 223 B 3.3-173 06/29/00 003 B 3.3-76 08/01/98 223 B 3.3-125 08/01/98 223 B 3.3-174 06/29/00 003 B 3.3-77 08/01/98 223 B 3.3-126 08/01/98 223 B 3.3-175 06/29/00 003 B 3.3-78 11/07/01 044 B 3.3-127 08/01/98 223 B 3.3-176 06/29/00 003 B 3.3-79 08/01/98 223 B 3.3-128 08/01/98 223 B 3.3-177 06/29/00 003 B 3.3-80 08/25/10 123 B 3.3-129 08/01/98 223 B 3.3-178 06/29/00 003 B 3.3-81 08/25/10 123 B 3.3-130 08/01/98 223 B 3.3-179 06/29/00 003 B 3.3-82 11/07/01 044 B 3.3-131 08/01/98 223 B 3.3-180 06/29/00 003 B 3.3-83 08/01/98 223 B 3.3-132 08/01/98 223 B 3.3-181 06/29/00 003 B 3.3-84 04/27/12 120 B 3.3-133 08/01/98 223 B 3.3-182 06/29/00 003 B 3.3-85 04/27/12 120 B 3.3-134 08/01/98 223 B 3.3-183 06/29/00 003 B 3.3-86 04/27/12 120 B 3.3-135 08/01/98 223 B 3.3-184 06/29/00 003 B 3.3-87 04/09/04 044A B 3.3-136 08/01/98 223 B 3.3-185 02/09/07 074A B 3.3-88 08/01/98 223 B 3.3-137 04/27/12 120 B 3.3-186 04/27/12 120 B 3.3-89 11/02/98 005 B 3.3-138 04/27/12 120 B 3.3-187 04/27/12 120 B 3.3-90 08/01/98 223 B 3.3-139 04/27/12 120 B 3.3-188 04/27/12 120 B 3.3-91 08/01/98 223 B 3.3-140 08/01/98 223 B 3.3-189 06/29/00 003 B 3.3-92 08/01/98 223 B 3.3-141 08/01/98 223 B 3.3-190 08/01/98 223 B 3.3-93 08/01/98 223 B 3.3-142 11/07/01 044 B 3.3-191 08/01/98 223 B 3.3-94 04/27/12 120 B 3.3-143 11/07/01 044 B 3.3-192 08/01/98 223 B 3.3-95 04/27/12 120 B 3.3-144 08/01/98 223 B 3.3-193 08/01/98 223 B 3.3-96 08/01/98 223 B 3.3-145 08/01/98 223 B 3.3-194 05/16/01 037 B 3.3-97 08/01/98 223 B 3.3-146 08/01/98 223 B 3.3-195 05/16/01 037 B 3.3-98 08/18/06 084 B 3.3-147 08/01/98 223 B 3.3-196 08/01/98 223 B 3.3-99 08/01/98 223 B 3.3-148 04/27/12 120 B 3.3-197 08/01/98 223 B 3.3-100 04/09/04 044A B 3.3-149 04/27/12 120 B 3.3-198 04/27/12 120 B 3.3-101 08/18/06 084 B 3.3-150 04/27/12 120 B 3.3-199 04/27/12 120 B 3.3-102 08/01/98 223 B 3.3-151 02/09/07 074A B 3.3-200 04/27/12 120 B 3.3-103 08/01/98 223 B 3.3-152 08/01/98 223 B 3.3-201 08/01/98 223

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B 3.3-202 08/01/98 223 B 3.4-21 08/01/98 223 B 3.5-8 08/01/98 223 B 3.3-203 04/09/04 044A B 3.4-22 08/01/98 223 B 3.5-9 08/01/98 223 B 3.3-204 08/01/98 223 B 3.4-23 08/01/98 223 B 3.5-10 08/01/98 223 B 3.3-205 04/18/05 064 B 3.4-24 08/01/98 223 B 3.5-11 08/01/98 223 B 3.3-206 08/01/98 223 B 3.4-25 04/27/12 120 B 3.5-12 11/07/01 044 B 3.3-207 04/27/12 120 B 3.4-26 08/01/98 223 B 3.5-13 04/27/12 120 B 3.3-208 04/27/12 120 B 3.4-27 04/30/99 005 B 3.5-14 04/27/12 120 B 3.3-209 04/09/04 044A B 3.4-28 05/16/01 045 B 3.5-15 04/27/12 120 B 3.3-210 04/09/04 044A B 3.4-29 05/16/01 045 B 3.5-16 04/27/12 120 B 3.3-211 08/01/98 223 B 3.4-30 05/16/01 045 B 3.5-17 04/27/12 120 B 3.3-212 04/27/12 120 B 3.4-31 04/18/05 064 B 3.5-18 04/27/12 120 B 3.3-213 04/27/12 120 B 3.4-32 04/27/12 120 B 3.5-19 04/27/12 120 B 3.3-214 04/27/12 120 B.3.4-32a 04/27/12 120 B 3.5-20 04/09/04 044A B 3.3-215 11/02/98 005 B 3.4-33 04/09/04 044A B 3.5-21 08/01/98 223 B 3.3-216 11/02/98 005 B 3.4-34 08/20/01 037 B 3.5-22 08/01/98 223 B 3.3-217 08/01/98 223 B 3.4-35 04/18/05 064 B 3.5-23 08/01/98 223 B 3.3-218 08/01/98 223 B 3.4-36 04/27/12 120 B 3.5-24 08/01/98 223 B 3.3-219 08/01/98 223 B 3.4-37 08/01/98 223 B 3.5-25 04/27/12 120 B 3.3-220 08/01/98 223 B 3.4-38 10/30/00 026A B 3.5-26 04/27/12 120 B 3.3-221 10/20/03 066 B 3.4-39 04/18/05 064 B 3.5-27 08/01/98 223 B 3.3-222 04/27/12 120 B 3.440 08/01/98 223 B 3.5-28 04/09/04 044A B 3.3-223 04/27/12 120 B 3.4-41 04/27/12 120 B 3.5-29 04/18/05 064 B 3.3-224 08/01/98 223 B 3.4-42 08/01/98 223 B 3.5-30 04/27/12 120 B 3.3-225 08/01/98 223 B 3.4-43 08/01/98 223 B 3.1-50 04/27/12 120 B 3.3-226 08/01/98 223 B 3.4-44 10/30/00 026A B 3.5-31 04/27/12 120 B 3.3-227 08/01/98 223 B 3.4-45 08/01/98 223 B 3.5-32 04/27/12 120 B 3.3-228 08/01/98 026A B 3.4-46 08/01/98 223 B 3.6-1 08/01/98 223 B 3.3-229 04/27/12 120 B 3.4-47 04/27/12 120 B 3.6-2 08/01/98 223 B 3.3-230 04/27/12 120 B 3.4-48 08/01/98 223 B 3.6-3 04/09/04 044A B 3.4-1 08/01/98 223 B 3.4-49 08/01/98 223 B 3.6-4 08/01/98 223 B 3.4-2 08/01/98 223 B 3.4-50 08/01/98 223 B 3.6-5 04/27/12 120 B 3.4-3 11/07/01 044 B 3.4-51 04/30/99 017 B 3.6-6 08/01/98 223 B 3.4-4 11/07/01 044 B 3.4-52 04/30/99 017 B 3.6-7 11/07/01 044 B 3.4-5 08/01/98 223 B 3.4-53 04/30/99 017 B 3.6-8 08/01/98 223 B 3.4-6 08/01/98 223 B 3.4-54 04/27/12 120 B 3.6-9 08/01/98 223 B 3.4-7 08/01/98 223 B 3.4-55 04/30/99 017 B 3.6-10 08/01/98 223 B 3.4-8 04/27/12 120 B 3.4-56 04/27/12 120 B 3.6-11 08/01/98 223 B 3.4-9 04/09/04 044A B 3.4-57 04/27/12 120 B 3.6-12 08/01/98 223 B 3.4-10 08/01/98 223 B 3.4-58 04/09/04 044A B 3.6-13 04/27/12 120 B 3.4-11 08/01/98 223 B 3.4-59 10/26/07 097 B 3.6-14 9/30/10 104 B 3.4-12 08/01/98 223 B 3.4-60 04/27/12 120 B 3.6-15 02/09/07 074A B 3.4-13 04/27/12 120 B 3.4-61 10/26/07 097 B 3.6-16 9/30/10 104 B 3.4-14 04/09/04 044A B 3.5-1 08/01/98 223 B 3.6-17 9/30/10 104 B 3.4-15 08/01/98 223 B 3.5-2 08/01/98 223 B 3.6-18 09/30/10 104 B 3.4-16 11/07/01 044 B 3.5-3 08/01/98 223 B 3.6-19 07/02/99 006 B 3.4-17 08/01/98 223 B 3.5-4 10/10/08 112 B 3.6-20 09/30/10 104 B 3.4-18 08/01/98 223 B 3.5-5 10/10/08 112 B 3.6-21 09/30/10 104 B 3.4-19 10/20/99 009 B 3.5-6 10/10/08 112 B 3.6-22 09/30/10 104 B 3.4-20 04/27/12 120 B 3.5-7 04/18/05 064 B 3.6-23 09/30/10 104

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B 3.6-24 09/30/10 104 B 3.6-73 Deleted B 3.7-24B 04/27/12 120 B 3.6-25 09/30/10 104 B 3.6-74 07/27/07 083A B 3.7-24C 04/27/12 120 B 3.6-26 04/27/12 120 B 3.6-75 07/27/07 083A B 3.7-25 12/18/08 223 B 3.6-27 04/27/12 120 B 3.6-76 04/27/12 120 B 3.7-26 12/18/08 223 B 3.6-28 04/27/12 120 B 3.6-77 07/27/07 083A B 3.7-27 12/18/08 113 B 3.6-29 4/16/10 096A B 3.6-78 05/16/01 037 B 3.7-28 01/18/08 068 B 3.6-30 11/07/01 044 B 3.6-79 05/16/01 037 B 3.7-29 04/27/12 120 B 3.6-31 08/01/98 223 B 3.6-80 05/16/01 037 B 3.7-30 04/09/04 044A B 3.6-32 04/27/12 120 B 3.6-81 04/27/12 120 B 3.7-31 08/01/98 223 B 3.6-33 08/01/98 223 B 3.6-82 04/09/04 044A B 3.7-32 04/27/12 120 B 3.6-34 08/01/98 223 B 3.6-83 09/30/10 104 B 3.7-33 08/25/10 123 B 3.6-35 04/27/12 120 B 3.6-84 09/30/10 104 B 3.7-34 02/23/09 115 B 3.6-36 04/27/12 120 B 3.6-85 05/16/01 037 B 3.7-35 04/27/12 120 B 3.6-37 08/01/98 223 B 3.6-86 09/30/10 104 B 3.7-36 04/27/12 120 B 3.6-38 08/01/98 223 B 3.6-87 09/30/10 104 B 3.7-37 04/09/04 044A B 3.6-39 08/01/98 223 B 3.6-88 04/27/12 120 B 3.7-38 04/27/12 120 B 3.6-40 08/01/98 223 B 3.6-89 04/27/12 120 B 3.7-39 04/09/04 044A B 3.6-41 08/01/98 223 B 3.6-90 04/09/04 044A B 3.740 04/09/04 044A B 3.6-42 04/27/12 120 B 3.6-91 08/20/01 037 B 3.741 07/02/99 006 B 3.6-43 08/01/98 223 B 3.6-92 05/16/01 223 B 3.7-42 07/02/99 006 B 3.6-44 04/09/04 044A B 3.6-93 05/16/01 037 B 3.7-43 07/02/99 006 B 3.6-45 08/01/98 223 B 3.6-94 04/27/12 120 B 3.7-44 04/27/12 120 B 3.6-46 08/01/98 223 B 3.6-95 04/27/12 120 B 3.8-1 04/09/04 044A B 3.6-47 04/27/12 120 B 3.6-96 04/09/04 044A B 3.8-2 10/10/08 111 B 3.6-48 04/27/12 120 B 3.7-1 04/09/04 044A B 3.8-3 04/09/04 044A B 3.6-49 08/01/98 044A B 3.7-2 04/09/04 044A B 3.8-4 06/09/06 082 B 3.6-50 11/07/01 223 B 3.7-3 08/01/98 044A B 3.8-5 06/09/06 082 B 3.6-51 11/02/98 005 B 3.7-4 04/18/05 064 B 3.8-6 06/09/06 082 B 3.6-52 08/01/98 223 B 3.7-5 08/01/98 223 B 3.8-7 08/01/98 223 B 3.6-53 04/27/12 120 B 3.7-6 04/27/12 120 B 3.8-8 09/26/08 1OlA B 3.6-54 04/09/04 044A B 3.7-7 04/02/09 095 B 3.8-9 09/26/08 lOlA B 3.6-55 08/01/98 223 B 3.7-8 04/02/09 095 B 3.8-10 09/26/08 lOlA B 3.6-56 08/01/98 223 B 3.7-9 04/02/09 095 B 3.8-11 09/26/08 lOlA B 3.6-57 04/27/12 120 B 3.7-10 04/27/12 120 B 3.8-12 09/26/08 lOlA B 3.6-58 08/01/98 223 B 3.7-11 04/27/12 120 B 3.8-13 09/26/08 1OlA B 3.6-59 11/07/01 044 B 3.7-12 04/27/12 120 B 3.8-14 09/26/08 lOlA B 3.6-60 11/07/01 044 B 3.7-13 04/09/04 044A B 3.8-15 04/27/12 120 B 3.6-61 08/01/98 223 B 3.7-14 05/27/11 127 B 3.8-16 04/27/12 120 B 3.6-62 08/01/98 223 B 3.7-15 08/01/98 223 B 3.8-17 04/27/12 120 B 3.6-63 04/27/12 120 B 3.7-16 08/01/98 223 B 3.8-18 04/27/12 120 B 3.6-64 04/09/04 044A B 3.7-17 04/27/12 120 B 3.8-19 04/27/12 120 B 3.6-65 10/20/99 018 B 3.7-18 12/18/08 092 B 3.8-20 04/27/12 120 B 3.6-66 10/20/99 018 B 3.7-19 12/18/08 092 B 3.8-21 04/27/12 120 B 3.6-67 08/01/98 223 B 3.7-20 12/18/08 092 B 3.8-22 04/27/12 120 B 3.6-68 04/27/12 120 B 3.7-21 12/18/08 092 B 3.8-23 04/09/04 044A B 3.6-69 07/27/07 083A B 3.7-22 12/18/08 092 B 3.8-24 04/27/12 120 B 3.6-70 Deleted B 3.7-23 12/18/08 092 B 3.8-25 06/09/06 082 B 3.6-71 Deleted B 3.7-24 12/18/08 092 B 3.8-26 08/01/98 223 B 3.6-72 Deleted B 3.7-24A 04/27/12 120 B 3.8-27 08/01/98 223

Page 5 of 5 LIST OF EFFECTIVE PAGES Appendix A to DPR-49 Technical Specifications Bases Revision Date 04/27/12 Paoe Date Rev. PaPe Date R ev. Pare Date Rev.

B 3.8-28 08/01/98 223 B 3.8-77 11/02/98 005 B 3.10-16 08/01/98 223 B 3.8-29 08/01/98 223 B 3.8-78 04/27/12 120 B 3.10-17 08/01/98 223 B 3.8-30 10/30/00 026A B 3.9-1 08/01/98 223 B 3.10-18 08/01/98 223 B 3.8-31 10/30/00 026A B 3.9-2 08/01/98 223 B 3.10-19 08/01/98 223 B 3.8-32 08/18/06 085 B 3.9-3 08/01/98 223 B 3.10-20 04/27/12 120 B 3.8-33 08/18/06 085 B 3.9-4 04/27/12 120 B 3.10-21 08/01/98 223 B 3.8-34 08/01/98 223 B 3.9-5 08/01/98 223 B 3.10-22 08/01/98 223 B 3.8-35 10/27/06 086 B 3.9-6 08/01/98 223 B 3.10-23 08/01/98 223 B 3.8-36 08/01/98 223 B 3.9-7 04/27/12 120 B 3.10-24 08/01/98 223 B 3.8-37 .04/27/12 120 B 3.9-8 04/27/12 120 B 3.10-25 04/27/12 120 B 3.8-38 08/01/98 223 B 3.9-9 08/01/98 223 B 3.10-26 08/01/98 223 B 3.8-39 04/27/12 120 B 3.9-10 04/27/12 120 B 3.10-27 08/01/98 223 B 3.8-40 04/27/12 120 B 3.9-11 04/09/04 044A B 3.10-28 04/27/12 120 B 3.8-41 08/01/98 223 B 3.9-12 08/01/98 223 B 3.10-29 08/01/98 223 B 3.8-42 06/02/09 118 B 3.9-13 08/01/98 223 B 3.10-30 08/01/98 223 B 3.8-43 04/09/04 044A B 3.9-14 08/01/98 223 B 3.10-31 08/01/98 223 B 3.8-44 08/01/98 223 B 3.9-15 04/09/04 044A B 3.10-32 08/01/98 223 B 3.8-45 11/22/02 048 B 3.9-16 08/01/98 223 B 3.10-33 08/01/98 223 B 3.8-46 11/22/02 048 B 3.9-17 08/01/98 223 B 3.10-34 08/01/98 223 B 3.8-47 04/27/12 120 B 3.9-18 04/27/12 120 B 3.10-35 08/01/98 223 B 3.8-48 04/27/12 120 B 3.9-19 04/09/04 044A B 3.10-36 08/01/98 223 B 3.8-49 04/27/12 120 B 3.9-20 08/01/98 223 B 3.10-37 04/27/12 120 B 3.8-50 01/24/03 060 B 3.9-21 04/27/12 120 B 3.10-38 04/27/12 120 B 3.8-51 04/27/12 120 B 3.9-22 08/01/98 223 B 3.8-52 04/09/04 044A B 3.9-23 10/30/00 223 B 3.8-53 08/01/98 223 B 3.9-24 06/12/09 117 B 3.8-54 08/01/98 223 B 3.9-25 03/17/99 019 B 3.8-55 04/09/04 044A B 3.9-26 04/27/12 120 B 3.8-56 04/09/04 044A B 3.9-27 08/01/98 223 B 3.8-57 06/12/09 118 B 3.9-28 10/30/00 026A B 3.8-58 06/12/09 118 B 3.9-29 03/17/99 019 B 3.8-59 04/27/12 120 B 3.9-30 08/01/98 223 B 3.8-60 08/01/98 223 B 3.9-31 04/27/12 120 B 3.8-61 08/01/98 223 B 3.10-1 02/16/07 078 B 3.8-62 04/09/04 044A B 3.10-2 02/16/07 078 B 3.8-63 04/09/04 044A B 3.10-3 02/16/07 078 B 3.8-64 11/02/98 005 B 3.10-4 02/16/07 078 B 3.8-65 08/01/98 223 B 3.10-5 02/16/07 078 B 3.8-66 08/01/98 223 B 3.10-5A 02/16/07 078 B 3.8-67 08/01/98 223 B 3.10-6 08/01/98 223 B 3.8-68 08/01/98 223 B 3.10-7 08/01/98 223 B 3.8-69 08/01/98 223 B 3.10-8 08/01/98 223 B 3.8-70 11/02/98 005 B 3.10-9 08/01/98 223 B 3.8-71 04/27/12 120 B 3.10-10 04/27/12 120 B 3.8-72 04/27/12 120 B 3.10-11 08/01/98 223 B 3.8-73 08/01/98 223 B 3.10-12 08/01/98 223 B 3.8-74 04/09/04 044A B 3.10-13 08/01/98 223 B 3.8-75 08/01/98 223 B 3.10-14 08/01/98 223 B 3.8-76 11/02/98 005 B 3.10-15 04/27/12 120

Control Rod OPERABILITY B 3.1.3 BASES ACTIONS E.1 (continued)

If any Required Action and associated Completion Time of Condition A, C, or D are not met, or there are nine or more inoperable control rods, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . This ensures all insertable control rods are inserted and places the reactor in a condition that does not require the active function (i.e., scram) of the control rods. The number of control rods permitted to be inoperable when operating above 10% RTP (e.g., no CRDA considerations) could be more than the value specified, but the occurrence of a large number of inoperable control rods could be indicative of a generic problem, and investigation and resolution of the potential problem should be undertaken. The allowed Completion Time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.1.3.1 REQUIREMENTS The position of each control rod must be determined to ensure adequate information on control rod position is available to the operator for determining control rod OPERABILITY and controlling rod patterns. Control rod position may be determined by the use of OPERABLE position indicators, by moving control rods to a position with an OPERABLE indicator, by use of TIP traces, by alternate rod position determination methods, or by the use of other appropriate methods. The Frequency of this SR is based on operating experience related to expected changes in control rod position and the availability of control rod position indications in the control room. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.1.3.2 Control rod insertion capability is demonstrated by inserting each partially or fully withdrawn control rod at least one notch and observing that the control rod moves. The control rod may then be returned to its original position. This ensures the control rod is not stuck and is free to insert on a scram signal. These Surveillances are not required when THERMAL POWER is less (continued)

DAEC B 3.1-20 TSCR-1 20

Control Rod OPERABILITY B 3.1.3 BASES SURVEILLANCE SR 3.1.3.2 (continued)

REQUIREMENTS than or equal to 20% RTP since the notch insertions may not be compatible with the requirements of the Banked Position Withdrawal Sequence (BPWS) (LCO 3.1.6) and the RWM (LCO 3.3.2.1). Partially and fully withdrawn control rods are tested periodically, based on the potential power reduction required to allow the control rod movement. Furthermore, the Frequency takes into account operating experience related to changes in CRD performance. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

At any time, if a control rod is immovable (e.g., due to an inoperable insert or withdrawn solenoid valve), a determination of that control rod's ability to be moved with scram pressure OPERABILITY must be made and appropriate action taken.

This SR is modified by a Note that allows 31 days after withdrawal of the control rod and increasing power to above 20% RTP, to perform the Surveillance. This acknowledges that the control rod must be first withdrawn and THERMAL POWER must be increased to above 20% RTP before performance of the Surveillance, and therefore the Notes avoid potential conflicts with SR 3.0.3 and SR 3.0.4.

SR 3.1.3.3 Verifying that the scram time for each control rod to notch position 04 is < 7 seconds provides reasonable assurance that the control rod will insert when required during a DBA or transient, thereby completing its shutdown function. This SR is performed in conjunction with the control rod scram time testing of SR 3.1.4.1 and SR 3.1.4.2. The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

and the functional testing of SDV vent and drain valves in LCO 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," overlap this Surveillance to provide complete testing of the assumed safety function. The associated Frequencies are acceptable, considering the more frequent testing performed to (continued)

DAEC B 3.1-21 TSCR-120

Control Rod Scram Accumulators B 3.1.5 BASES ACTIONS D.1 (continued)

The reactor mode switch must be immediately placed in the shutdown position if either Required Action and associated Completion Time associated with loss of the CRD charging pump (Required Actions B.1 and C.1) cannot be met. This ensures that all insertable control rods are inserted and that the reactor is in a condition that does not require the active function (i.e., scram) of the control rods. The insertion of a manual scram prior to placing the reactor mode switch in the Shutdown position is permitted by the definition of an Immediate Completion Time. This Required Action is modified by a Note stating that the action is not applicable if all control rods associated with the inoperable scram accumulators are fully inserted, since the function of the control rods has been performed.

SURVEILLANCE SR 3.1.5.1 REQUIREMENTS SR 3.1.5.1 requires that the accumulator pressure be checked periodically to ensure adequate accumulator pressure exists to provide sufficient scram force. The primary indicator of accumulator OPERABILITY is the accumulator pressure. A minimum accumulator pressure is specified below which the capability of the accumulator to perform its intended function becomes degraded and the accumulator is considered inoperable.

The minimum accumulator pressure of 940 psig is well below the expected pressure of 1100 psig (Ref. 1). Declaring the accumulator inoperable when the minimum pressure is not maintained ensures that significant degradation in scram times does not occur. The Frequency has been shown to be acceptable through operating experience and takes into account indications available in the control room. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

DAEC B 3.1-32 TSCR-120

Rod Pattern Control B 3.1.6 BASES (continued)

SURVEILLANCE SR 3.1.6.1 REQUIREMENTS The control rod pattern is periodically verified to be in compliance with the BPWS to ensure the assumptions of the CRDA analyses are met. The Frequency was developed considering that the primary check on compliance with the BPWS is performed by the RWM (LCO 3.3.2.1), which provides control rod blocks to enforce the required sequence and is required to be OPERABLE when operating at _<10% RTP. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES

1. NEDE-2401 1-P-A-US, "General Electric Standard Application for Reactor Fuel, Supplement for United States," Section 2.2.3.1.

2. Letter from T. A. Pickens (BWROG) to G.E. Laines (NRC),

"Amendment 17 to General Electric Licensing Topical Report NEDE-2401 1-P-A", BWROG-8644, August 15, 1988.

3. NUREG-0979, Section 4.2.1.3.2, April 1983.

4. NUREG-0800, Section 15.4.9, Revision 2, July 1981.

5. 10 CFR 50.67.

6. NEDO-21778-A, "Transient Pressure Rises Affected Fracture Toughness Requirements for Boiling Water Reactors," December 1978.

7. ASME, Boiler and Pressure Vessel Code.

8. NEDO-21231, "Banked Position Withdrawal Sequence,"

January 1977.

9. GE SIL No. 316, "Reduced Notch Worth Procedures,"

November 1979.

10. NEDO-33091-A, Rev.2, "Improved BPWS Control Rod Insertion Process," July 2004.

DAEC B 3.1-38 TSCR-120

SLC System B 3.1.7 BASES (continued)

SURVEILLANCE SR 3.1.7.1, SR 3.1.7.2, and SR 3.1.7.3 REQUIREMENTS SR 3.1.7.1 through SR 3.1.7.3 are Surveillances verifying certain characteristics of the SLC System (e.g., the volume and temperature of the borated solution in the storage tank), thereby ensuring SLC System OPERABILITY without disturbing normal plant operation. These Surveillances ensure that the proper borated solution volume and temperature, including the temperature of the pump suction piping, are maintained.

Maintaining a minimum specified borated solution temperature is important in ensuring that the boron remains in solution and does not precipitate out in the storage tank or in the pump suction piping. The temperature versus concentration curve of Figure 3.1.7-2 ensures that a 50 F margin will be maintained above the saturation temperature. The Frequency is based on operating experience and has shown there are relatively slow variations in the measured parameters of volume and temperature. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.1.7.4 SR 3.1.7.4 verifies the continuity of the explosive charges in the injection valves to ensure that proper operation will occur if required. Other administrative controls, such as those that limit the shelf life of the explosive charges, must be followed. The Frequency is based on operating experience and has demonstrated the reliability of the explosive charge continuity.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.1.7.5 This Surveillance requires an examination of the sodium pentaborate solution by using chemical analysis to ensure that the proper concentration of boron exists in the storage tank.

SR 3.1.7.5 must be performed anytime boron or water is added to the storage tank solution to determine that the boron solution concentration is within the specified limits. SR 3.1.7.5 must also be performed anytime the temperature is restored to within the limits of Figure 3.1.7-2, to ensure that no significant boron precipitation occurred. The Frequency of this Surveillance is appropriate because of the relatively slow variation of boron concentration between surveillances. The Surveillance Frequency is controlled under the Surveillance Frequency Control Progam.

(continued)

DAEC B 3.1-42 TSCR-120

SLC System B 3.1.7 BASES SURVEILLANCE SR 3.1.7.6 REQUIREMENTS (continued) Demonstrating that each SLC System pump develops a flow rate

> 26.2 gpm at a discharge pressure _>1150 psig when pumping demineralized water to the test tank ensures that pump performance has not degraded below design values during the fuel cycle. This minimum pump flow rate requirement ensures that, when combined with the sodium pentaborate solution concentration requirements, the rate of negative reactivity insertion from the SLC System will adequately compensate for the positive reactivity effects encountered during power reduction, cooldown of the moderator, and xenon decay. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this Surveillance is in accordance with the Inservice Testing Program.

SR 3.1.7.7 and SR 3.1.7.8 These Surveillances ensure that there is a functioning flow path from the boron solution storage tank to the RPV, including the firing of an explosive valve. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch that has been certified by having one of that batch successfully fired. The Surveillance may be performed in separate steps to prevent injecting boron into the RPV. An acceptable method for verifying flow from the pump to the RPV is to pump demineralized water from a test tank through one SLC subsystem and into the RPV. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

(continued)

DAEC B 3.1-43 TSCR-1 20

SLC System B 3.1.7 BASES SURVEILLANCE SR 3.1.7.7 and SR 3.1.7.8 (continued)

REQUIREMENTS Demonstrating that all heat traced piping between the boron solution storage tank and the suction inlet to the injection pumps is unblocked ensures that there is a functioning flow path for injecting the sodium pentaborate solution. Acceptable methods for verifying that the suction piping is unblocked include pumping from the storage tank to the test tank or establishing flow from the pump suction drains.

The periodic Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The periodic Frequency is acceptable since there is a low probability that the subject piping will be blocked due to precipitation of the boron from solution in the heat traced piping. This is especially true in light of the temperature verification of this piping required by SR 3.1.7.3.

However, if, in performing SR 3.1.7.3, it is determined that the temperature of this piping has fallen below the specified minimum, SR 3.1.7.8 must be performed once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the piping temperature is restored to within the limits of Figure 3.1.7-2.

REFERENCES 1. 10 CFR 50.62.

2. UFSAR, Section 9.3.4.3.

3. NEDC-30859, "Duane Arnold ATWS Assessments" December 1984.

DAEC B 3.1-44 TSCR-120

SDV Vent and Drain Valves B 3.1.8 BASES (continued)

ACTIONS C.1 (continued)

If any Required Action and associated Completion Time is not met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems..

SURVEILLANCE SR 3.1.8.1 REQUIREMENTS (continued) During normal operation, the SDV vent and drain valves should be in the open position (except when performing SR 3.1.8.2) to allow for drainage of the SDV piping. Verifying that each valve is in the open position ensures that the SDV vent and drain valves will perform their intended functions during normal operation. This SR does not require any testing or valve manipulation; rather, it involves verification that the valves are in the correct position.

This SR is modified by a Note that allows the SR to be met for OPERABLE valves that are temporarily closed while performing the testing required by SR 3.1.8.2. The Note is necessary to avoid potential conflicts between the two SRs created by SR 3.0.1.

The Frequency is based on engineering judgment and is consistent with the procedural controls governing valve operation, which ensure correct valve positions. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.1.8.2 During a scram, the SDV vent and drain valves should close to contain the reactor water discharged to the SDV piping. Cycling each valve through its complete range of motion (closed and open) ensures that the valve will function properly during a scram.

The Frequency is based on operating experience and takes into account the level of redundancy in the system design as well as being in accordance with the Inservice Testing Program.

(continued)

DAEC B 3.1-48 TSCR-120

SDV Vent and Drain Valves B 3.1.8 BASES SURVELLANCE SR 3.1.8.3 REQUIREMENTS SR 3.1.8.3 is an integrated test of the SDV vent and drain valves to verify total system performance. After receipt of a simulated or actual scram signal, the closure of the SDV vent and drain valves is verified. The closure time of 30 seconds after receipt of a scram signal is based on the bounding leakage case evaluated in the accident analysis (Ref. 2). Similarly, after receipt of a simulated or actual scram reset signal, the opening of the SDV vent and drain valves is verified. The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.1.1 and the scram time testing of control rods in LCO 3.1.3 overlap this Surveillance to provide complete testing of the assumed safety function. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. UFSAR, Section 4.6.2.3.

2. 10 CFR 50.67.

3. NUREG-0803, "Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping,"

August 1981.

DAEC B 3.1-49 TSCR-1 20

APLHGR B 3.2.1 BASES (continued)

ACTIONS A.1 If any APLHGR exceeds the required limits, an assumption regarding an initial condition of the DBA and transient analyses may not be met. Therefore, prompt action should be taken to restore the APLHGR(s) to within the required limits such that the plant operates within analyzed conditions and within design limits of the fuel rods. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time is sufficient to restore the APLHGR(s) to within its limits and is acceptable based on the low probability of a transient or DBA occurring simultaneously with the APLHGR out of specification.

B.1 If the APLHGR cannot be restored to within its required limits within the associated Completion Time, the plant must be brought to a MODE or other specified condition in which the LCO does not apply. To achieve this status, THERMAL POWER must be reduced to < 21.7% RTP within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The allowed Completion Time is reasonable, based on operating experience, to reduce THERMAL POWER to < 21.7% RTP in an orderly manner and without challenging plant systems because in general, a power reduction from full power would normally have already been initiated as part of Required Action A.1.

SURVEILLANCE SR 3.2.1.1 REQUIREMENTS APLHGRs are required to be initially calculated within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is > 21.7% RTP and then periodically thereafter. They are compared to the specified limits in the COLR to ensure that the reactor is operating within the assumptions of the safety analysis. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on both engineering judgment and recognition of the slowness of changes in power distribution during normal operation. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowance after THERMAL POWER

> 21.7% RTP is achieved is acceptable given the large inherent margin to operating limits at low power levels.

(continued)

DAEC B 32-4 TSCR-120

MCPR B 3.2.2 BASES (continued)

SURVEILLANCE SR 3.2.2.1 REQUIREMENTS The MCPR is required to be initially calculated within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is _>21.7% RTP and then periodically I thereafter. It is compared to the specified limits in the COLR to ensure that the reactor is operating within the assumptions of the safety analysis. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on both engineering judgment and recognition of the slowness of changes in power distribution during normal operation. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowance after THERMAL POWER

_>21.7% RTP is achieved is acceptable given the large inherent margin to operating limits at low power levels.

SR 3.2.2.2 Because the transient analysis takes credit for conservatism in the scram speed performance, it must be demonstrated that the specific scram speed distribution is consistent with that used in the transient analysis. Therefore, in order to perform SR 3.2.2.2, the value of r, which is a measure of the actual scram speed distribution compared with the assumed distribution must first be determined. The MCPR operating limit is then determined based on an interpolation between the applicable limits for Option A (scram times of LCO 3.1.4,"Control Rod Scram Times") and Option B (realistic scram times) analyses. The parameter -c must be determined once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each set of scram time tests required by SR 3.1.4.1 and SR 3.1.4.2 because the effective scram speed distribution may change after maintenance that could affect scram times. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is acceptable due to the large inherent margin to operating limits at low power.

REFERENCES 1. NUREG-0562, June 1979.

2. NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version).

3. UFSAR, Chapters 4.2.3, 4.4.2, and 4.4.4.

4. UFSAR, Chapter 15.0.

5. "Supplemental Reload Licensing Report for Duane Arnold Energy Center," (latest version referenced in COLR).

(continued)

DAEC B 3.2-10 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES (continued)

SURVEILLANCE As noted at the beginning of the SRs, the SRs for each RPS REQUIREMENTS instrumentation Function are located in the SRs column of Table 3.3.1.1-1.

The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , provided the associated Function maintains RPS trip capability. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken.

This Note is based on the reliability analysis (Ref. 9) assumption of the average time required to perform channel Surveillance.

That analysis demonstrated that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly reduce the probability that the RPS will trip when necessary.

SR 3.3.1.1.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels (continued)

DAEC B 3.3-26 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.1 (continued)

REQUIREMENTS during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.1.1.2 To ensure that the APRMs are accurately indicating the true core average power, the APRMs are calibrated to the reactor power calculated from a heat balance. LCO 3.4.1, "Recirculation Loops Operating," allows the APRMs to be reading greater than actual THERMAL POWER to effectively lower the APRM Flow Biased High setpoints by 6.3% for single recirculation loop operation.

When this adjustment is made, the requirement for the APRMs to indicate within 2% RTP of calculated power is modified to require the APRMs to indicate within 2% RTP of calculated power plus 6.3%. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on minor changes in LPRM sensitivity, which could affect the APRM reading between performances of SR 3.3.1.1.8.

A restriction to satisfying this SR when < 21.7% RTP is provided that requires the SR to be met only at _>21.7% RTP because it is difficult to accurately maintain APRM indication of core THERMAL POWER consistent with a heat balance when < 21.7% RTP. At low power levels, a high degree of accuracy is unnecessary because of the large, inherent margin to thermal limits (MCPR and APLHGR). At _>21.7% RTP, the Surveillance is required to have been satisfactorily performed within the previous Frequency, in accordance with SR 3.0.2. A Note is provided which allows an increase in THERMAL POWER above 21.7% if the Frequency is not met per SR 3.0.2. In this event, the SR must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reaching or exceeding 21.7% RTP. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

SR 3.3.1.1.3 The surveillance frequency extensions for various RPS functions are permitted by Reference 9, provided the automatic scram contactors are functionally tested weekly. There are four pairs of RPS automatic scram contactors (i.e., K14 relay contacts) with each pair associated with an automatic scram logic (Al, A2, B1, and B2). The automatic scram contactors can be functionally tested without the necessity of using an automatic scram (continued)

DAEC B 3.3-27 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.3 (continued)

REQUIREMENTS function trip. This functional test can be accomplished by placing the associated RPS Test Switch in the trip position, which will deenergize a pair of the automatic scram contactors and in turn, trip the associated RPS logic. The RPS Test Switches were not specifically credited in the accident analysis and thus, do not have any OPERABILITY requirements of their own. However, because the Manual Scram pushbuttons at the DAEC are not configured the same as the generic model used in Reference 9, (i.e., they are in a separate RPS logic - A3 and B3), the RPS Test Switches have been found to be functionally equivalent to the Manual Scram pushbuttons in the generic model for performing the weekly functional test of the automatic scram contactors required by Reference 9. If an RPS Test Switch(es) is (are) not available for performing this test, it is permissible to take credit for a CHANNEL FUNCTIONAL TEST of an automatic RPS trip function (i.e., SR 3.3.1.1.9), if performed within the required Frequency for this Surveillance, as it will also test the K14 relay contacts.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the reliability analysis in Reference 9.

SR 3.3.1.1.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

As noted, SR 3.3.1.1.4 is not required to be performed when entering MODE 2 from MODE 1, since testing of the MODE 2 required IRM and APRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads, or movable links.

(continued)

DAEC B 3.3-28 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.4 (continued)

REQUIREMENTS This allows entry into MODE 2 if the Frequency is not met per SR 3.0.2. In this event, the SR must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2 from MODE 1. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency provides an acceptable level of system average unavailability over the Frequency interval and is based on reliability analysis (Ref. 9).

SR 3.3.1.1.5 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency provides an acceptable level of system average availability over the Frequency and is based on the reliability analysis using the concepts developed in Reference 10.

SR 3.3.1.1.6 and SR 3.3.1.1.7 These Surveillances are established to ensure that no gaps in neutron flux indication exist from subcritical to power operation for monitoring core reactivity status.

The overlap between SRMs and IRMs is required to be demonstrated to ensure that reactor power will not be increased into a neutron flux region without adequate indication. This is required prior to withdrawing SRMs from the fully inserted position since indication is being transitioned from the SRMs to the IRMs.

The overlap between IRMs and APRMs is of concern when reducing power into the IRM range. On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained.

(continued)

DAEC B 3.3-29 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.6 and SR 3.3.1.1.7 (continued)

REQUIREMENTS Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block (i.e.,

approximately one-half decade of range). Overlap between SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are indicating at least 5/40 on range 1 before SRMs have reached 106 counts per second.

As noted, SR 3.3.1.1.7 is only required to be met during entry into MODE 2 from MODE 1. That is, after the overlap requirement has been met and indication has transitioned to the IRMs, maintaining overlap is not required (APRMs may be reading downscale once in MODE 2).

If overlap for a group of channels is not demonstrated (e.g.,

IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate channel(s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment and the reliability of the IRMs and APRMs.

SR 3.3.1.1.8 LPRM gain settings are determined using analytical methods with input from the axial flux profiles measured by the Traversing Incore Probe (TIP) System. This establishes the relative local flux profile for appropriate representative input to the APRM System.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience with LPRM sensitivity changes.

SR 3.3.1.1.9 and SR 3.3.1.1.13 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verificiation of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay (continued)

DAEC B 3.3-30 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.9 and SR 3.3.1.1.13 (continued)

REQUIREMENTS are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of SR 3.3.1.1.9 is based on the reliability analysis of Reference 9.

The Frequency of SR 3.3.1.1.13 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

SR 3.3.1.1.10 Calibration of trip units provides a check of the actual trip setpoints. The channel must be declared inoperable if the trip setting is discovered to be less conservative than the Allowable Value specified in Table 3.3.1.1-1. If the trip setting is discovered to be less conservative than accounted for in the appropriate setpoint methodology, but is not beyond the Allowable Value, the channel performance is still within the requirements of the plant safety analysis. Under these conditions, the setpoint must be readjusted to be equal to or more conservative than accounted for in the appropriate setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the reliability analysis of Reference 9.

SR 3.3.1.1.11, SR 3.3.1.1.12 and SR 3.3.1.1.14 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies that the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The CHANNEL CALIBRATION for Functions 5 and 8 shall consist of the physical inspection and actuation of these position switches.

(mtionue DAEC B3.3-31 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.11, SR 3.3.1.1.12 and SR 3.3.1.1.14 (continued)

REQUIREMENTS Note 1 states that neutron detectors are excluded from CHANNEL CALIBRATION because they are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signal. Changes in neutron detector sensitivity are compensated for by performing the calorimetric calibration (SR 3.3.1.1.2) and the LPRM calibration against the TIPs (SR 3.3.1.1.8). A second Note is provided that requires the APRM and IRM SRs to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering MODE 2 from MODE 1.

Testing of the MODE 2 APRM and IRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads, or movable links. This Note allows entry into MODE 2 from MODE 1 if the associated Frequency is not met per SR 3.0.2. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the assumption of a specified calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.1.1.15 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel.

The functional testing of control rods (LCO 3.1.3), and SDV vent and drain valves (LCO 3.1.8), overlaps this Surveillance to provide complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

(continued)

DAEC B 3.3-32 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.16 REQUIREMENTS (continued) This SR ensures that scrams initiated from the Turbine Stop Valve

- Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions will not be inadvertently bypassed when THERMAL POWER is _>26% RTP. This involves calibration of the bypass channels. Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint.

Because main turbine bypass flow, as well as other turbine steam loads, can affect this setpoint nonconservatively (THERMAL POWER is derived from turbine first stage pressure), the main turbine bypass valves must remain closed at THERMAL POWER

> 26% RTP to ensure that the calibration remains valid. If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at _>26% RTP, either due to open main turbine bypass valve(s) (e.g., required testing or upon actual demand) or other reasons, such as changes in turbine steamload to the Main Steam Reheaters), then the affected Turbine Stop Valve -

Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure

- Low Functions are considered inoperable. Alternatively, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the nonbypass condition, this SR is met and the channel is considered OPERABLE.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment and reliability of the components.

SR 3.3.1.1.17 The Average Power Range Monitor Flow Biased - High Function uses the recirculation loop drive flows to vary the trip setpoint.

This SR ensures that the total loop drive flow signals from the flow units used to vary the setpoint is appropriately compared to a calibrated flow signal and, therefore, the APRM Function accurately reflects the required setpoint as a function of flow.

Each flow signal from the respective flow unit must be < 110% of the calibrated flow signal. If the flow unit signal is not within the limit, that flow unit may be bypassed, and its output to the low auction circuit will be maximum, making the low auction circuit select the input from the operating flow unit.

(continued)

DAEC B 3.3-33 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.17 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment, operating experience, the reliability of this instrumentation, the other surveillances performed on the components of the flow biasing network, and the fact that a half scram will be present for an extended period of time during the performance of this surveillance.

SR 3.3.1.1.18 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. The RPS Response Time test only applies to the Functions of Reactor Vessel Water Level - Low and Reactor Vessel Steam Dome Pressure - High. These RPS Functions are the only ones that were identified, in a program conducted prior to the first refueling outage, that require sensor response time testing. This test may be performed in one measurement or in overlapping segments, with verification that all components are tested. The RPS RESPONSE TIME acceptance criteria are included in Reference 13.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This Frequency is based on the logic interrelationships of the various channels required to produce an RPS scram signal. The Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

SR 3.3.1.1.19 This SR ensures that the RPS logic system response times are less than or equal to the maximum value assumed in the accident analysis. The RPS logic system response time test is measured from the opening of the sensor contact up to and including the opening of the trip actuator contacts. As such, this test does not include the sensor response time. All RPS Functions except the RPS Manual Scram and Reactor Mode Switch - Shutdown Position are included in this test.

(continued)

DAEC B 3.3-34 TSCR-120

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.19 (continued)

REQUIREMENTS These two RPS Functions are excluded since they directly trip their scram solenoid relays without any intervening devices, thus there is nothing to response time test. This test may be performed in one measurement or in overlapping segments, with verification that all components are tested. The RPS logic system response time acceptance criteria are included in Reference 13.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This Frequency is based on the logic interrelationships of the various channels required to produce an RPS scram signal. The Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

REFERENCES 1. UFSAR, Figure 7.2-2.

2. UFSAR, Section 15.1.4.2.

3. NEDO-23842, "Continuous Control Rod Withdrawal in the Startup Range," April 18, 1978.

4. UFSAR, Section 5.2.2 and Appendix 5B.

5. UFSAR, Section 15.2.4.

6. UFSAR, Section 15.2.1.

7. UFSAR, Chapter 15.1.

8. P. Check (NRC) letter to G. Lainas (NRC), "BWR Scram Discharge System Safety Evaluation," December 1, 1980.

9. NEDO-30851-P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System,"

March 1988.

10. Reliability of Engineered Safety Features as a Function of Testing Frequency, Volume 9, No. 4, July-August 1968.

(continued)

DAEC B 3.3-35 TSCR-1 20

SRM Instrumentation B 3.3.1.2 BASES SURVEILLANCE SR 3.3.1.2.1 and SR 3.3.1.2.3 REQUIREMENTS (continued) Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on another channel. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience that demonstrates channel failure is rare.

While in MODES 3 and 4, reactivity changes are not expected; therefore, the Frequency is relaxed from MODES 2 and 5. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.1.2.2 To provide adequate coverage of potential reactivity changes in the core when the fueled region encompasses more than one SRM, one SRM is required to be OPERABLE in the quadrant where CORE ALTERATIONS are being performed, and the other OPERABLE SRM must be in an adjacent quadrant containing fuel. Note 1 states that the SR is required to be met only during CORE ALTERATIONS. It is not required to be met at other times in MODE 5 since core reactivity changes are not occurring. This Surveillance consists of a review of plant logs to ensure that SRMs required to be OPERABLE for given CORE ALTERATIONS are, in fact, OPERABLE. In the event that only one SRM is required to be OPERABLE, per Table 3.3.1.2-1, footnote (b),

(continued)

DAEC B 3.3-42 TSCR-1 20

SRM Instrumentation B 3.3.1.2 BASES SURVEILLANCE SR 3.3.1.2.2 (continued)

REQUIREMENTS only the a. portion of this SR is required. Note 2 clarifies that more than one of the three requirements can be met by the same OPERABLE SRM. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon operating experience and supplements operational controls over refueling activities that include steps to ensure that the SRMs required by the LCO are in the proper quadrant.

SR 3.3.1.2.4 This Surveillance consists of a verification of the SRM instrument readout to ensure that the SRM reading is greater than a specified minimum count rate with the detector fully inserted into the core.

The requirement of at least 3 cps assures that any transient, should it occur, begins at or above the initial value of 10-8 of RTP which is used in the analysis of transients in cold conditions. With few fuel assemblies loaded, the SRMs may not have a high enough count rate to satisfy the SR. Therefore, allowances are made for loading sufficient "source" material, in the form of irradiated fuel assemblies, to establish the minimum count rate.

To accomplish this, the SR is modified by a Note that states that the count rate is not required to be met on an SRM that has less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies are in the associated core quadrant. With four or less fuel assemblies loaded around each SRM and no other fuel assemblies in the associated core quadrant, even with a control rod withdrawn, the configuration will not be critical.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon channel redundancy and other information available in the control room, and ensures that the required channels are frequently monitored during CORE ALTERATIONS. When no reactivity changes are in progress, the Frequency is relaxed from that during CORE ALTERATIONS.

(continued)

DAEC B 3.3-43 TSCR-120

SRM Instrumentation B 3.3.1.2 BASES SURVEILLANCE SR 3.3.1.2.5 and SR 3.3.1.2.6 REQUIREMENTS (continued) Performance of a CHANNEL FUNCTIONAL TEST demonstrates the associated channel will function properly. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

SR 3.3.1.2.5 is required in MODE 5, and the Frequency ensures that the channels are OPERABLE while core reactivity changes could be in progress. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience and on other Surveillances (such as a CHANNEL CHECK), that ensure proper functioning between CHANNEL FUNCTIONAL TESTS.

SR 3.3.1.2.6 is required in MODE 2 with IRMs on Range 2 or below, and in MODES 3 and 4. Since core reactivity changes do not normally take place in MODES 3 and 4 and core reactivity changes are due solely to control rod movement in MODE 2, the Frequency has been extended from that in MODE 5. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience and on other Surveillances (such as CHANNEL CHECK) that ensure proper functioning between CHANNEL FUNCTIONAL TESTS.

The Note to the Surveillance allows the Surveillance to be delayed until entry into the specified condition of the Applicability (THERMAL POWER decreased to IRM Range 2 or below). The SR must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs are on Range 2 or below. The allowance to enter the Applicability with the Surveillance Frequency not met is reasonable, based on the limited time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed after entering the Applicability and the inability to perform the Surveillance while at higher power levels. Although the Surveillance could be performed while on IRM Range 3, the plant would not be expected to maintain steady state operation at this power level. In this event, the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, based on the SRMs being otherwise verified to be OPERABLE (i.e., satisfactorily performing the CHANNEL CHECK) and the time required to perform the Surveillances.

(continued)

DAEC B 3.3-44 TSCR-120

SRM Instrumentation B 3.3.1.2 BASES SURVEILLANCE SR 3.3.1.2.7 REQUIREMENTS (continued) Performance of a CHANNEL CALIBRATION verifies the performance of the SRM detectors and associated circuitry. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency considers the plant conditions required to perform the test, the ease of performing the test, and the likelihood of a change in the system or component status. Note 1 to the Surveillance allows the neutron detectors to be excluded from the CHANNEL CALIBRATION because they cannot readily be adjusted. The detectors are fission chambers that are designed to have a relatively constant sensitivity over the range and with an accuracy specified for a fixed useful life.

Note 2 to the Surveillance allows the Surveillance to be delayed until entry into the specified condition of the Applicability. The SR must be performed in MODE 2 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering MODE 2 with IRMs on Range 2 or below. The allowance to enter the Applicability with the Surveillance Frequency not met is reasonable, based on the limited time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed after entering the Applicability and the inability to perform the Surveillance while at higher power levels. Although the Surveillance could be performed while on IRM Range 3, the plant would not be expected to maintain steady state operation at this power level. In this event, the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, based on the SRMs being otherwise verified to be OPERABLE (i.e., satisfactorily performing the CHANNEL CHECK) and the time required to perform the Surveillances.

REFERENCES None.

DAEC B 3.3-45 TSCR-120

Control Rod Block Instrumentation B 3.3.2.1 BASES (continued)

SURVEILLANCE SR 3.3.2.1.1 REQUIREMENTS A CHANNEL FUNCTIONAL TEST is performed for each RBM channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. It includes the Reactor Manual Control Multiplexing System input.

Testing of the Reactor Manual Control Multiplexing System input shall include inputs of "no rod selected," "peripheral rod selected,"

and "center rod selected with two, three, or four LPRM strings around it" (Ref. 10).

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on reliability analyses (Ref. 8).

SR 3.3.2.1.2 and SR 3.3.2.1.3 A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The CHANNEL FUNCTIONAL TEST for the RWM is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs and for SR 3.3.2.1.2, and by attempting to select a control rod, in each fully inserted group, not in compliance with the prescribed sequence and verifying a selection error occurs. As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at <

10% RTP in MODE 2, and SR 3.3.2.1.3 is not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is _ 10% RTP in (continued)

DAEC B 3.3-54 TSCR-120

Control Rod Block Instrumentation B 3.3.2.1 BASES (continued)

SURVEILLANCE SR 3.3.2.1.2 and SR 3.3.2.1.3 (continued)

REQUIREMENTS MODE 1. This allows entry into MODE 2 for SR 3.3.2.1.2, and entry into MODE 1 when THERMAL POWER is < 10% RTP for SR 3.3.2.1.3, to perform the required Surveillance if the Surveillance Frequency is not met per SR 3.0.2. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months allowance is based on operating experience and in consideration of providing a reasonable time in which to complete the SRs. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequencies are based on reliability analysis (Ref. 8).

SR 3.3.2.1.4 The RBM setpoints are automatically varied as a function of power. Three Allowable Values are specified in Table 3.3.2.1-1, each within a specific power range. The power at which the control rod block Allowable Values, which are verified during the CHANNEL CALIBRATION, automatically change are based on the APRM signal's input to each RBM channel. Below the minimum power setpoint, the RBM is automatically bypassed.

These power Allowable Values must be verified periodically to be within the specified ranges to ensure that the Analytical Limits for the ranges specified in Table 3.3.2.1-1 are met. If any power range setpoint is nonconservative, then the affected RBM channel is considered inoperable. Alternatively, the power range channel can be placed in the conservative condition (i.e., enabling the proper RBM setpoint). If placed in this condition, the SR is met and the RBM channel is not considered inoperable. As noted, neutron detectors are excluded from the Surveillance because they are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signal. Neutron detectors are adequately tested in SR 3.3.1.1.2 and SR 3.3.1.1.8. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the actual trip setpoint methodology utilized for these channels.

SR 3.3.2.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

(continued)

DAEC B 3.3-55 TSCR-120

Control Rod Block Instrumentation B 3.3.2.1 BASES (continued)

SURVEILLANCE SR 3.3.2.1.5 (continued)

REQUIREMENTS CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the DAEC Instrument Setpoint Methodology.

As noted, neutron detectors are excluded from the CHANNEL CALIBRATION because they are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signal. Neutron detectors are adequately tested in SR 3.3.1.1.2 and SR 3.3.1.1.8.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the determination of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.2.1.6 A CHANNEL FUNCTIONAL TEST is performed for the Reactor Mode Switch. Shutdown Position Function to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay.

This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The CHANNEL FUNCTIONAL TEST for the Reactor Mode Switch Shutdown Position Function is performed by attempting to withdraw any control rod with the reactor mode switch in the shutdown position and verifying a control rod block occurs. As noted in the SR, the Surveillance is not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the reactor mode switch is in the shutdown position, since testing of this interlock with the reactor mode switch in any other position cannot be performed without using jumpers, lifted leads, or movable links. This allows entry into MODES 3 and 4 if the Surveillance Frequency is not met per SR 3.0.2. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months allowance is based on operating experience and in consideration of providing a reasonable time in which to complete the SRs.

(continued)

DAEC B 3.3-56 TSCR-120

Control Rod Block Instrumentation B 3.3.2.1 BASES (continued)

SURVEILLANCE SR 3.3.2.1.6 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the on this Frequency.

SR 3.3.2.1.7 The RWM will only enforce the proper control rod sequence if the rod sequences are properly input into the RWM computer.

This SR ensures that the proper sequences are loaded into the RWM so that it can perform its intended function. The Surveillance is performed once prior to declaring the RWM OPERABLE following loading of a sequence into the RWM, since this is when rod sequence input errors are possible.

(continued)

DAEC B 3.3-57 TSCR-120

PAM Instrumentation B 3.3.3.1 BASES (continued)

SURVEILLANCE The following SRs apply to the PAM instrumentation Functions in REQUIREMENTS Table 3.3.3.1-1, except as noted.

SR 3.3.3.1.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION. The HPCI and RCIC steam line instrumentation of the reactor steam dome pressure Function are compared to each other to satisfy this SR. For PCIV position indication, the CHANNEL CHECK consists of a comparison of the open and closed position lights with the expected position of the PCIV.

Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including isolation, indication, and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon plant operating experience, with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel of a given Function in this interval is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of those displays associated with the required channels of this LCO.

(continued)

DAEC B 3.3-67 TSCR-120

PAM Instrumentation B 3.3.3.1 BASES SURVEILLANCE SR 3.3.3.1.2 REQUIREMENTS (continued)

A CHANNEL CALIBRATION is performed approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies the channel responds to the measured parameter with the necessary range and accuracy. For PCIV position indication, the CHANNEL CALIBRATION is a comparison of a local visual check to remote control room indication to verify the PCIV's indicated position agrees with the actual position. If an indication does not agree with the actual position, adjustments are made to the PCIV's indication channel. For Primary Containment Area Radiation instrumentation (Drywell and Suppression Chamber), the CHANNEL CALIBRATION shall consist of an electronic calibration of the channel for ranges above 10 R/hr and a one point calibration check of the detector below 10 R/hr with a portable gamma source.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience and consistency with the typical industry refueling cycles.

REFERENCES 1. Regulatory Guide 1.97, Revision 2, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," December 1980.

2. R. M. Pulsifer (NRC) to L. Liu (IELP), "Duane Arnold Energy Center - Conformance to Regulatory Guide 1.97, Revision 2 (TAC M84788)," dated August 4, 1993.

3. DAEC License Amendment 254, transmitted by letter, D.

Beaulieu (USNRC) to M. Peifer (NMC), "Duane Arnold Energy Center - Issuance ofAmendment Re: Relocation of Requirements for Hydrogen and Oxygen Monitors," dated June 10, 2004.

(continued)

DAEC B 3.3-68 TSCR-120

Remote Shutdown System B 3.3.3.2 BASES ACTIONS As such, a Note has been provided that allows separate Condition (continued) entry for each inoperable Remote Shutdown System Function.

A.1 Condition A addresses the situation where one or more required Functions of the Remote Shutdown System is inoperable. This includes any instrument channel Function listed in Table B 3.3.3.2-1, as well as the transfer/control circuit Functions.

The Required Action is to restore the Function to OPERABLE status within 30 days. The Completion Time is based on operating experience and the low probability of an event that would require evacuation of the control room.

B.1 If the Required Action and associated Completion Time of Condition A are not met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Time is reasonable, based on operating experience, to reach the required MODE from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.3.3.2.1 REQUIREMENTS SR 3.3.3.2.1 verifies each required Remote Shutdown System transfer switch and control circuit performs the intended function.

This verification is performed from the remote shutdown panel and locally, as appropriate. Operation of the equipment from the remote shutdown panel is not necessary. The Surveillance can be satisfied by performance of a continuity check. This will ensure that if the control room becomes inaccessible, the plant can be placed and maintained in MODE 3 from the remote shutdown panel and the local control stations. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Operating experience demonstrates that Remote Shutdown System control channels usually pass the Surveillance when performed at this Frequency.

(continued)

DAEC B 3.3-73 TSCR-1 20

Remote Shutdown System B 3.3.3.2 BASES SURVEILLANCE SR 3.3.3.2.2 REQUIREMENTS (continued) CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor for each of the instrument channel functions.

The test verifies the channel responds to measured parameter values with the necessary range and accuracy.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon operating experience and consistency with the typical industry refueling cycle.

REFERENCES 1. UFSAR, Section 7.4.2.

(continued)

DAEC B 3.3-74 TSCR-120

EOC-RPT Instrumentation B 3.3.4.1 BASES ACTIONS C.1 and C.2 (continued)

With any Required Action and associated Completion Time not met, THERMAL POWER must be reduced to < 26% RTP within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Alternately, the associated recirculation pump may be removed from service, since this performs the intended function of the instrumentation. The allowed Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is reasonable, based on operating experience, to reduce THERMAL POWER to < 26% RTP from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE The Surveillances are modified by a Note to indicate that when a REQUIREMENTS channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken.

This Note is based on the reliability analysis (Ref. 4) assumption of the average time required to perform channel Surveillance.

That analysis demonstrated that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly reduce the probability that the recirculation pumps will trip when necessary.

SR 3.3.4.1.1 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The RPT breaker is excluded from this testing.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on reliability analysis of Reference 4.

(continued)

DAEC B 3.3-84 TSCR-120

EOC-RPT Instrumentation B 3.3.4.1 BASES SURVEILLANCE SR 3.3.4.1.2 REQUIREMENTS (continued) CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the magnitude of equipment drift in the setpoint analysis.

SR 3.3.4.1.3 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel.

The functional test of the pump breakers is included as a part of this test, overlapping the LOGIC System Functional Test, to provide complete testing of the associated safety function.

Therefore, if a breaker is incapable of operating, the associated instrument channel(s) would also be inoperable.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at this Frequency.

SR 3.3.4.1.4 This SR ensures that an EOC-RPT initiated from the TSV -

Closure and TCV Fast Closure, Trip Oil Pressure - Low Functions will not be inadvertently bypassed when THERMAL POWER is >_26% RTP. This involves calibration of the bypass channels. The 26% RTP is the analytical limit. Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint. Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from turbine first stage pressure) the main turbine bypass valves must remain closed whenever THERMAL POWER > 26% RTP to ensure (continued)

DAEC B 3.3-85 TSCR-1 20

EOC-RPT Instrumentation B 3.3.4.1 BASES SURVEILLANCE SR 3.3.4.1.4 (continued)

REQUIREMENTS that the calibration remains valid. If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at

>_26% RTP, either due to open main turbine bypass valves (e.g.,

required testing or upon actual demand) or other reasons), the affected TSV - Closure and TCV Fast Closure, Trip Oil Pressure

- Low Functions are considered inoperable. Alternatively, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the nonbypass condition, this SR is met with the channel considered OPERABLE.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgement and the reliability of the components.

SR 3.3.4.1.5 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the transient analysis. The EOC-RPT SYSTEM RESPONSE TIME acceptance criteria are documented in Reference 3.

EOC-RPT SYSTEM RESPONSE TIME test Frequency is controlled under the Surveillance Frequency Control Program.

Response times cannot be determined at power because operation of final actuated devices is required. Therefore, the Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components that cause serious response time degradation, but not channel failure, are infrequent occurrences.

(continued)

DAEC B 3.3-86 TSCR-1 20

ATWS-RPT Instrumentation B 3.3.4.2 BASES (continued)

SURVEILLANCE SR 3.3.4.2.1 REQUIREMENTS Performance of the CHANNEL CHECK for the Reactor Vessel Water Level-Low Low Function ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal but more frequent checks of channels during normal operational use of the displays associated with the required channels of this LCO.

SR 3.3.4.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The RPT breaker itself is excluded from this testing.

(continued)

DAEC B 3.3-94 TSCR-120

ATWS-RPT Instrumentation B 3.3.4.2 BASES (continued)

SURVEILLANCE SR 3.3.4.2.2 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of is based on the fact that ATWS is considered a very low probability event and is outside the normal design basis. Therefore, the surveillance frequency is less stringent than for safety-related instrumentation.

SR 3.3.4.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the magnitude of equipment drift in the setpoint analysis.

SR 3.3.4.2.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel.

The system functional test of the pump breakers is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide complete testing of the assumed safety function. Therefore, if a breaker is incapable of operating, the associated instrument channel(s) would be inoperable.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at this Frequency.

(continued)

DAEC B 3.3-95 TSCR-120

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE Because the Ref. 5 analysis made no assumptions regarding the REQUIREMENTS elapsed time between testing of consecutive channels in the same (continued) logic, it is not necessary to remove jumpers/relays blocks or reconnect lifted leads used to prevent actuation of the trip logic during testing of logic channels with instruments in series solely for the purpose of administering the AOT clocks, provided that the AOT allowance is not exceeded on a per instrument channel basis.

SR 3.3.5.1.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK guarantees that undetected outright channel failure is limited in time; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.5.1.2, SR 3.3.5.1.3, and SR 3.3.5.1.5 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all (continued)

DAEC B 3.3-137 TSCR-120

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE SR 3.3.5.1.2, SR 3.3.5.1.3, and SR 3.3.5.1.5 (continued)

REQUIREMENTS of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

The Surveillance Frequency for SR 3.3.5.1.3 is based on the reliability analyses of Reference 5.

The Surveillance Frequencies of SR 3.3.5.1.2 and SR 3.3.5.1.5 are based upon engineering judgment and the reliability of the components.

The Surveillance Frequencies are controlled under the Surveillance Frequency Control Program.

SR 3.3.5.1.4. SR 3.3.5.1.6. SR 3.3.5.1.7. and SR 3.3.5.1.8 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequencies are controlled under the Surveillance Frequency Control Program. The Frequency is based upon the magnitude of equipment drift in the setpoint analysis.

(continued)

DAEC B 3.3-138 TSCR-120

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE SR 3.3.5.1.9 REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.8.1, and LCO 3.8.2 overlaps this Surveillance to complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. UFSAR, Section 5.4.7.

2. UFSAR, Section 6.3.2.

3. UFSAR, Chapter 15.

4. NEDC-32980P, "Safety Analysis Report for Duane Arnold Energy Center Extended Power Uprate," Rev. 1, April 2001.

5. NEDC-30936-P-A, "BWR Owners' Group Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Part 2," December 1988.

DAEC B 3.3-139 TSCR-120

RCIC System Instrumentation B 3.3.5.2 BASES (continued)

SURVEILLANCE As noted in the beginning of the SRs, the SRs for each RCIC REQUIREMENTS System instrumentation Function are found in the SRs column of Table 3.3.5.2-1.

The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2 and 3; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Function 1, provided the associated Function maintains trip-capability. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to status or the applicable Condition entered and Required Actions taken. This Note is based on the reliability analysis (Ref. 1) assumption of the average time required to perform channel surveillance. That analysis demonstrated that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly reduce the probability that the RCIC will initiate when necessary. Because the Ref. 1 analysis made no assumptions regarding the elapsed time between testing of consecutive channels in the same logic, it is not necessary to remove jumpers/relay blocks or reconnect lifted leads used to prevent actuation of the trip logic during testing of logic channels with instruments in series solely for the purpose of administering the AOT clocks, provided that the AOT allowance is not exceeded on a per instrument channel basis.

SR 3.3.5.2.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a parameter on other similar channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

(continued)

DAEC B 3.3-148 TSCR-120

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.5.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extenstions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the reliability analysis of Reference 1.

SR 3.3.5.2.3 and SR 3.3.5.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the magnitude of equipment drift in the setpoint analysis.

(continued)

DAEC B 3.3-149 TSCR-120

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.5 REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in LCO 3.5.3 overlaps this Surveillance to provide complete testing of the safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. GENE-770-06-2, "Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.

DAEC B 3.3-150 TSCR-120

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.1 and SR 3.3.6.1.2 REQUIREMENTS (continued) Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.6.1.3, and SR 3.3.6.1.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

(continued)

DAEC B 3.3-186 TSCR-1 20

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.3, and SR 3.3.6.1.4 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Surveillance Frequency of SR 3.3.6.1.4 is based on the reliability analyses described in References 5 and 6. The Surveillance Frequency of SR 3.3.6.1.3 is based on engineering judgment and the reliability of the components.

SR 3.3.6.1.5. SR 3.3.6.1.6. SR 3.3.6.1.7 and SR 3.3.6.1.8 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the magnitude of equipment drift in the setpoint analysis.

(continued)

DAEC B 3.3-187 TSCR-120

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.9 REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. UFSAR, Section 6.2.

2. UFSAR, Chapter 15.

3. NEDO-31466, "Technical Specification Screening Criteria Application and Risk Assessment," November 1987.

4. UFSAR, Section 9.3.4.2.

5. NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

6. NEDC-30851 P-A Supplement 2, "Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

7. UFSAR, Section 7.3.

8. UFSAR, Section 15.2.1.5.

(continued)

DAEC B 3.3-188 TSC R-120

Secondary Containment Isolation Instrumentation B 3.316.2 BASES SURVEILLANCE The Surveillances are modified by a Note to indicate that when a REQUIREMENTS channel is placed in an inoperable status solely for performance of (continued) required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains secondary containment isolation capability. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the reliability analysis (Refs. 4 and 5) assumption of the average time required to perform channel surveillance. That analysis demonstrated the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly reduce the probability that the SCIV/Ds will isolate the associated penetration flow paths and that the SBGT System will initiate when necessary.

SR 3.3.6.2.1 and SR 3.3.6.2.2 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION. Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

(continued)

DAEC B 3.3-198 TSCR-1 20

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE SR 3.3.6.2.3 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the reliability analysis of References 4 and 5.

SR 3.3.6.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on SCIV/Ds and the SBGT System in LCO 3.6.4.2 and LCO 3.6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

(continued)

DAEC B 3.3-199 TSCR-1 20

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE SR 3.3.6.2.5 (continued)

REQUIREMENTS Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. UFSAR, Section 6.2.3.

2. UFSAR, Chapter 15.

3. UFSAR, Section 15.2.1.

4. NEDC-30851 P-A Supplement 2, "Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

5. NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

DAEC B 3.3-200 TSCR-120

LLS Instrumentation B 3.3.6.3 BASES SURVEILLANCE does not significantly reduce the probability that the LLS valves REQUIREMENTS will initiate when necessary.

(continued)

SR 3.3.6.3.1, and SR 3.3.6.3.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the reliability analysis of Reference 3.

A portion of the SRV tailpipe pressure switch channels is located inside the primary containment and is not available for testing during reactor operation. Therefore, SR 3.3.6.3.1 is only required on that portion of the channel that is outside primary containment.

SR 3.3.6.3.3, SR 3.3.6.3.4, and SR 3.3.6.3.5 CHANNEL CALIBRATION is a complete check of the instrument loop and sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

(continued)

DAEC B 3.3-207 TSCR-120

LLS Instrumentation B 3.3.6.3 BASES SURVEILLANCE SR 3.3.6.3.6 REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specified channel. The system functional testing performed in LCO 3.4.3, "Safety Relief Valves (SRVs)" and LCO 3.6.1.5, "Low-Low Set (LLS) Safety Relief Valves (SRVs)," for SRVs overlaps this test to provide complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency for SR 3.3.6.3.6 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. UFSAR, Figure 7.6-31.

2. NEDE-30021-P, Low-Low Set Relief Logic System and Lower MSIV Water Level Trip for the DAEC, January 1983.

3. GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.

4 UFSAR, Chapter 15.

DAEC B 3.3-208 TSCR-120

SFU System Instrumentation B 3.3.7.1 BASES ACTIONS A.1, and A.2 (continued)

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is intended to allow the operator time to place the SFU subsystem(s) in the isolation mode of operation, and is acceptable because it minimizes risk while allowing time for restoration of channels, or for placing the associated SFU in its safety mode, or for entering the applicable Conditions and Required Actions for the inoperable SFU subsystem(s).

SURVEILLANCE The Surveillances are modified by a Note to indicate that when a REQUIREMENTS channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , provided the other channel is OPERABLE. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the reliability analysis (Refs. 4 and 5) assumption of the average time required to perform channel surveillance. That analysis demonstrated that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly reduce the probability that the SFU System will initiate when necessary.

SR 3.3.7.1.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

(continued)

DAEC B 3.3-212 TSCR-1 20

SFU System Instrumentation B 3.3.7.1 BASES SURVEILLANCE SR 3.3.7.1.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.7.1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the reliability analyses of References 4 and 5.

SR 3.3.7.1.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the equipment drift in the setpoint analysis.

(continued)

DAEC B 3.3-213 TSCR-120

SFU System Instrumentation B 3.3.7.1 BASES SURVEILLANCE SR 3.3.7.1.4 REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in LCO 3.7.4, "Standby Filter Unit (SFU) System," overlaps this Surveillance to provide complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience that has shown these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. UFSAR, Section 15.2.

2. UFSAR, Section 6.4.4.

3. [Deleted]

4. GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.

5. NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

DAEC B 3.3-214 TSCR-120

LOP Instrumentation B 3.3.8.1 BASES ACTIONS C.1 (continued)

If the Required Action and associated Completion Time is not met, the associated Function is not capable of performing the intended function. Therefore, the associated DG(s) is declared inoperable immediately. This requires entry into applicable Conditions and Required Actions of LCO 3.8.1 and LCO 3.8.2, which provide appropriate actions for the inoperable DG(s).

SURVEILLANCE As noted at the beginning of the SRs, the SRs for each LOP REQUIREMENTS instrumentation Function are located in the SRs column of Table 3.3.8.1-1.

The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided the associated Function maintains DG initiation capability. Upon completion of the Surveillance, or expiration of the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken.

SR 3.3.8.1.1 and SR 3.3.8.1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequencies is based on operating experience with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel of a given Function in this interval is a rare event.

(continued)

DAEC B 3.3-222 TSCR-1 20

LOP Instrumentation B 3.3.8.1 BASES SURVEILLANCE SR 3.3.8.1.3 and SR 3.3.8.1.4 REQUIREMENTS (continued) A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequencies is based upon the magnitude of equipment drift in the setpoint analysis.

SR 3.3.8.1.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specific channel. The system functional testing performed in LCO 3.8.1 and LCO 3.8.2 overlaps this Surveillance to provide complete testing of the assumed safety functions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. UFSAR, Section 6.2.

2. UFSAR, Section 6.3.

3. UFSAR, Chapter 15.

DAEC B 3.3-223 TSCR-120

RPS Electric Power Monitoring B 3.3.8.2 BASES SURVEILLANCE SR 3.3.8.2.1 (continued)

REQUIREMENTS As noted in the Surveillance, the CHANNEL FUNCTIONAL TEST is only required to be performed while the plant is in a condition in which the loss of the RPS bus will not jeopardize steady state power operation (the design of the system is such that the power source must be removed from service to conduct the Surveillance). The 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is intended to indicate an outage of sufficient duration to allow for scheduling and proper performance of the Surveillance.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency and the Note in the Surveillance are based on guidance provided in Generic Letter 91-09 (Ref. 2).

SR 3.3.8.2.2 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies that the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the magnitude of equipment drift in the setpoint analysis.

SR 3.3.8.2.3 Performance of a system functional test demonstrates that, with a required system actuation (simulated or actual) signal, the system will automatically trip open the associated EPA. Only one signal per EPA is required to be tested. This Surveillance overlaps with the CHANNEL CALIBRATION to provide complete testing of the safety function. The system functional test of the Class 1 E circuit breakers is included as part of this test to provide complete testing of the safety function. If the breakers are incapable of operating, the associated EPA would be inoperable.

(continued)

DAEC B 3-3-229 TSCR-120

RPS Electric Power Monitoring B 3.3.8.2 BASES SURVEILLANCE SR 3.3.8.2.3 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

REFERENCES 1. UFSAR, Section 7.2.1.1.2.

2. NRC Generic Letter 91-09, "Modification of Surveillance Interval for the Electrical Protective Assemblies in Power Supplies for the Reactor Protection System."

DAEC B 3.3-230 TSCR-120

BASES VOLUME 2

Recirculation Loops Operating B 3.4.1 BASES SURVEILLANCE SR 3.4.1.1 (continued)

REQUIREMENTS Analyses indicate that above 69.4% RTP the LPCI Loop Select Logic could be expected to function at a speed differential up to 14% of average recirculation pump speed with the specification limit set at approximately +/- 10% of average recirculation pump speed to provide margin. Below 69.4% RTP the Loop Select Logic would be expected to function at a speed differential up to 20% of average recirculation pump speed with the specification limit set at approximately +/- 15% of average recirculation pump speed to provide margin. If the reactor is operating on one recirculation pump, the Loop Select Logic trips the pump before making the loop selection. The mismatch is measured in terms of percent of the speed of one recirculation pump compared to the speed of the other recirculation pump. If the speed mismatch exceeds the specified limits and cannot be restored within two hours, one recirculation pump shall be tripped. The SR is not required when both loops are not in operation since the mismatch limits are meaningless during single loop operation. The Surveillance must be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both loops are in operation. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is consistent with the Surveillance Frequency for jet pump OPERABILITY verification and has been shown by operating experience to be adequate to detect off normal jet pump loop flows in a timely manner.

SR 3.4.1.2 This SR ensures the reactor THERMAL POWER and core flow are within appropriate parameter limits to prevent uncontrolled power oscillations. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal hydraulic instability if operation is permitted in the Exclusion Region shown in the Core Operating Limits Report. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience and the operators' inherent knowledge of reactor status, including significant changes in THERMAL POWER and core flow.

(continued)

DAEC B 3.4-8 TSC R-120

Jet Pumps B 3.4.2 BASES (continued)

SURVEILLANCE SR 3.4.2.1 (continued)

REQUIREMENTS Individual jet pumps in a recirculation loop normally do not have the same flow. The unequal flow is due to the drive flow manifold, which does not distribute flow equally to all risers. The flow (or jet pump diffuser to lower plenum differential pressure) pattern or relationship of one jet pump to the loop average is repeatable. An appreciable change in this relationship is an indication that increased (or reduced) resistance has occurred in one of the jet pumps. This may be indicated by an increase in the relative flow for a jet pump that has experienced beam cracks.

The deviations from normal are considered indicative of a potential problem in the recirculation drive flow or jet pump system (Ref. 2). Normal flow ranges and established jet pump flow and differential pressure patterns are established by plotting historical data as discussed in Reference 2.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency has been shown by operating experience to be timely for detecting jet pump degradation and is consistent with the Surveillance Frequency for recirculation loop OPERABILITY verification.

This SR is modified by three Notes. Notes 1 and 2 affect the entire SR. The third Note only affects criterion c. Note 1 allows this Surveillance not to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the associated recirculation loop is in operation, since these checks can only be performed during jet pump operation. The 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is an acceptable time to establish conditions appropriate for data collection and evaluation.

Note 2 allows this SR not to be performed when THERMAL POWER is _ 21.7% of RTP. During low flow conditions, jet pump noise approaches the threshold response of the associated flow instrumentation and precludes the collection of repeatable and meaningful data.

(continued)

DAEC B 3.4-13 TSCR-120

SRVs and SVs B 3.4.3 BASES (continued)

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS This Surveillance requires that the SRVs and SVs will open at the pressures assumed in the safety analysis of Reference 1. The demonstration of the SRV and SV lift settings must be performed during shutdown, since this is a bench test, to be done in accordance with the Inservice Testing Program. The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures. The SRV and SV setpoints are +/- 3% for OPERABILITY; however the valves are reset to +/- 1% during the Surveillance to allow for drift.

The Surveillance Frequency is in accordance with the Inservice Testing Program requirements contained in the ASME Code,Section XI. This Surveillance must be performed during shutdown conditions.

SR 3.4.3.2 A manual actuation of each SRV is performed to verify that, mechanically, the valve is functioning properly and no blockage exists in the valve discharge line. This can be demonstrated by the response of the turbine control valves or bypass valves, by a change in the measured steam flow, by pressure switches and thermocouple readings downstream of the SRV indicating steam flow, or by any other method suitable to verify steam flow.

Adequate reactor steam dome pressure must be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the SRVs divert steam flow upon opening. Sufficient time is therefore allowed after the required pressure and flow are achieved to perform this test. Adequate pressure at which this test is to be performed is approximately 150 psig which is the lowest pressure EHC can maintain. Adequate steam flow is represented by approximately 1.15 turbine bypass valves open. Plant startup is allowed prior to performing this test because valve OPERABILITY and the setpoints for overpressure protection are verified, per ASME Code requirements, prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam (continued)

DAEC B 3.4-19 TSCR-009

SRVs and SVs B 3.4.3 BASES SURVEILLANCE SR 3.4.3.2 (continued)

REQUIREMENTS pressure and flow are adequate to perform the test. The 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed for manual actuation after the required pressure and flow are reached is sufficient to achieve stable conditions for testing and provides a reasonable time to complete the SR. If a valve fails to actuate due only to the failure of the solenoid but is capable of opening on overpressure, the safety function of the SRV is not considered inoperable.

This SR is not applicable to the SVs, due to their design which does not include the manual relief capability, nor do they have a discharge line that can become blocked.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Surveillance Frequency is consistent with the guidance of NUREG 1482, part 4.3.4 (Ref. 4),

where the staff recommends reducing the number of challenges to dual function relief valves, because failure in the open position is equivalent to a small break LOCA. Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

REFERENCES 1. UFSAR, Section 5.2.2.2.1.

2. UFSAR, Section 15.1.2.

3. ASME, Boiler and Pressure Vessel Code,Section XI.

4. NUREG 1482, Guidelines for Inservice Testing at Nuclear Power Plants.

DAEC B 3.4-20 TSCR-120

RCS Operational LEAKAGE B 3.4.4 BASES ACTIONS C.1 and C.2 (continued)

If any Required Action and associated Completion Time of Condition A or B is not met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems.

SURVEILLANCE SR 3.4.4.1 REQUIREMENTS The RCS LEAKAGE is monitored by a variety of instruments designed to provide alarms when LEAKAGE is indicated and to quantify the various types of LEAKAGE. Leakage detection instrumentation is discussed in more detail in the Bases for LCO 3.4.5, "RCS Leakage Detection Instrumentation." Sump level and flow rate are typically monitored to determine actual LEAKAGE rates; however, other methods may be used to quantify LEAKAGE within the guidelines of References 4 and 5. It is permissible to use pre-existing information, in conjunction with secondary measurements (e.g., Drywell pressure and temperature), to verify that LEAKAGE remains within limits by looking for step changes in conditions or to perform calculations to estimate LEAKAGE. The complete failure to demonstrate that RCS LEAKAGE is within limits, on the required Frequency, constitutes a failure to meet this SR, notwithstanding entrance into Conditions and Required Actions of LCO 3.4.5.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. In conjunction with alarms and other administrative controls, the Frequency for this Surveillance is appropriate for identifying LEAKAGE and for tracking required trends (Ref. 5).

(continued)

DAEC B 3.4-25 TSCR-120

RCS Leakage Detection Instrumentation B 3.4.5 BASES ACTIONS D.1 and D.2 (continued)

If any Required Action of Condition A or C cannot be met within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.4.5.1 REQUIREMENTS This SR is for the performance of a CHANNEL CHECK of the required Primary Containment Air Sampling System. The check gives reasonable confidence that the channel is operating properly. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on instrument reliability and is reasonable for detecting off normal conditions.

SR 3.4.5.2 This SR is for the performance of a CHANNEL FUNCTIONAL TEST of the required Primary Containment Air Sampling System instrumentation, equipment drain sump flow integrator and floor drain sump flow integrator. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. These tests ensure that the monitors can perform their function in the desired manner and also verifies the Primary Containment Air Sampling System alarm functions properly. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency considers instrument reliability, and operating experience has shown it proper for detecting degradation.

(continued)

DAEC B 3.4-32 TSCR-120

RCS Leakage Detection Instrumentation B 3.4.5 BASES SURVEILLANCE SR 3.4.5.3 REQUIREMENTS (continued) This SR is for the performance of a CHANNEL FUNCTIONAL TEST of required equipment drain sump fill and sump pump out timers and floor drain sump fill and sump pump out timers. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency considers channel reliability. Operating experience has proven this Frequency is acceptable.

SR 3.4.5.4 and SR 3.4.5.5 These SRs are for the performance of a CHANNEL CALIBRATION of required Primary Containment Air Sampling System instrumentation, equipment drain sump flow integrator, floor drain sump flow integrator, equipment drain sump fill and sump pump out timers and floor drain sump fill and sump pump out timers. The calibration verifies the accuracy of the instrument string, excluding the level elements located inside containment.

The level elements have no adjustable parts and thus, do not require calibration. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency considers channel reliability. Operating experience has proven these Frequencies are acceptable.

REFERENCES 1. UFSAR Section 3.1.2.4.1.

2. GEAP-5620, "Failure Behavior in ASTM A106B Pipes Containing Axial Through-Wall Flaws," April 1968.

3. NUREG-75/067, "Investigation and Evaluation of Cracking in Austenitic Stainless Steel Piping of Boiling Water Reactors," October 1975.

4. UFSAR, Section 5.2.5.2.3.

5. DAEC Operating License Amendment # 169, 9-19-90.

DAEC B 3.4-32a TSCR-120

RCS Specific Activity B 3.4.6 BASES (continued)

SURVEILLANCE SR 3.4.6.1 REQUIREMENTS This Surveillance is performed to ensure iodine remains within limits during normal operation. The analysis is performed using filtrate from a 0.45p filter. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is adequate to trend changes in the iodine activity level.

This SR is modified by a Note that requires this Surveillance to be performed only in MODE 1 because the level of fission products generated in other MODES is much less.

REFERENCES 1. 10 CFR 50.67

2. UFSAR, Sections 15.0.8 and 15.0.9.

3. UFSAR, Section 15.2.1.5 DAEC B 3.4-36 TSCR-120

RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES ACTIONS B.1, B.2, and B.3 (continued)

With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or recirculation pump must be restored without delay. Until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service.

This will provide the necessary circulation for monitoring coolant temperature. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. This will provide assurance of continued temperature monitoring capability. An alternate method of reactor coolant circulation that can be used includes (but is not limited to) Reactor Water Cleanup System.

During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This Surveillance verifies that one required RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant. The RHR shutdown cooling subsystem or recirculation pump flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is sufficient in view of other visual and audible indications available to the operator for monitoring the RHR subsystem in the control room.

This Surveillance is modified by a Note allowing sufficient time to align the RHR System for shutdown cooling operation after clearing the RCIC Steam Supply Line Pressure - Low isolation pressure, or for placing a recirculation pump in operation. The Note takes exception to the requirements of the Surveillance being met (i.e., forced coolant circulation is not required for this initial 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period), which also allows entry into the Applicability (continued)

DAEC B 3.4-41 TSCR-120

RHR Shutdown Cooling System - Cold Shutdown B 3.4.8 BASES ACTIONS B.1 and B.2 (continued)

With no RHR shutdown cooling subsystem and no recirculation pump in operation except as permitted by LCO Note 1, and until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This alternate method may consist of the losses to ambient surroundings if such losses are sufficiently large so as to prevent RCS temperature from increasing and if natural circulation has been established. This will provide the necessary circulation for monitoring coolant temperature. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. This will provide assurance of continued temperature monitoring capability. Alternate methods of reactor coolant circulation that can be used include (but are not limited to) raising reactor water level above the minimum natural circulation level (i.e., lowest turnaround point for water in the steam separator) and Reactor Water Cleanup System.

During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR Shutdown Cooling System or recirculation pump), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

SURVEILLANCE SR 3.4.8.1 REQUIREMENTS This Surveillance verifies that one required RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant. The RHR shutdown cooling subsystem or recirculation pump flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is sufficient in view of other visual and audible indications available to the operator for monitoring the RHR subsystem in the control room.

(continued)

DAEC B 3.4-47 TSCR-120

RCS P/T Limits B 3.4.9 BASES ACTIONS C.1 and C.2 (continued)

Operation outside the P/T limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that has been verified by stress analyses. The Required Action must be initiated without delay and continued until the limits are restored.

Besides restoring the P/T limit parameters to within limits, an evaluation is required to determine if RCS operation is allowed.

This evaluation must verify that the RCPB integrity is acceptable and must be completed before approaching criticality or heating up to > 212'F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components. ASME Code,Section XI, Appendix E (Ref. 6), may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.

Condition C is modified by a Note requiring Required Action C.2 be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.

SURVEILLANCE SR 3.4.9.1 REQUIREMENTS Verification that operation is within limits is required periodically when RCS pressure and temperature conditions are undergoing planned changes. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also, since temperature rate of change limits are specified in hourly increments, this Frequency permits a reasonable time for assessment and correction of minor deviations. The limits of Figure 3.4.9-1 are met when operation is to the right of the applicable limit curve.

(continued)

DAEC B 3.4-54 TSCR-120

RCS P/T Limits B 3.4.9 BASES SURVEILLANCE SR 3.4.9.3 and SR 3.4.9.4 (continued)

REQUIREMENTS Performing the Surveillance within 15 minutes before starting the idle recirculation pump provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start.

For SR 3.4.9.3, an acceptable means of measuring Reactor Pressure Vessel (RPV) coolant temperature is by using the saturation temperature corresponding to reactor steam dome pressure.

Acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.9.4 include but are not limited to comparing the temperatures of the operating recirculation loop and the idle loop. The idle loop and RPV coolant temperature using saturation temperature corresponding to reactor steam dome pressure, or the idle loop and the bottom head coolant temperature with flow through the bottom head drain.

SR 3.4.9.3 and SR 3.4.9.4 have been modified by a Note that requires the Surveillance to be met only in MODES 1, 2, 3, and 4 during a recirculation pump startup, since this is when the stresses occur. In MODE 5, the overall stress on limiting components is lower. Therefore, AT limits are not required.

SR 3.4.9.5, SR 3.4.9.6, and SR 3.4.9.7 Limits on temperature at the reactor vessel head flange and the shell adjacent to the head flange are generally bounded by the other P/T limits during system heatup and cooldown. However, operations approaching MODE 4 from MODE 5 and in MODE 4 with RCS temperature less than or equal to certain specified values require assurance that these temperatures meet the LCO limits.

SR 3.4.9.5 requires that temperatures at the reactor vessel head flange and the shell adjacent to the head flange must be verified to be above the limits within the Surveillance Frequency before and while tensioning the vessel head bolting studs to ensure that once the head is tensioned the limits are satisfied. When in MODE 4 with (continued)

DAEC B 3.4-56 TSCR-120

RCS P/T Limits B 3.4.9 BASES SURVEILLANCE SR 3.4.9.5, SR 3.4.9.6, and SR 3.4.9.7 (continued)

REQUIREMENTS RCS temperature < 80'F, more frequent checks of the temperatures at the reactor vessel head flange and the shell adjacent to the head flange are required by SR 3.4.9.6 because of the reduced margin to the limits. When in MODE 4 with RCS temperature _<100'F, monitoring of the temperatures at the reactor vessel head flange and the shell adjacent to the head flange are required periodically by SR 3.4.9.7 to ensure the temperatures are within the specified limits.

The Surveillance Frequencies are controlled under the Surveillance Frequency Control Program. The Frequency for SR 3.4.9.5 and SR 3.4.9.6 reflects the urgency of maintaining the temperatures within limits, and also limits the time that the temperature limits could be exceeded. The Frequency for SR 3.4.9.7 is reasonable based on the rate of temperature change possible at these temperatures.

SR 3.4.9.5 is modified by a Note that requires the Surveillance to be performed only when tensioning the reactor vessel head bolting studs. However, per SR 3.0.4, the Surveillance needs to be met prior to tensioning, i.e., verified within the Surveillance Frequency prior to the start of tensioning. SR 3.4.9.6 is modified by a Note that requires the Surveillance to be initiated 30 minutes after RCS temperatures _<80'F in Mode 4. SR 3.4.9.7 is modified by a Note that requires the Surveillance to be initiated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature

_<100'F in Mode 4. The Notes contained in these SRs are necessary to specify when the reactor vessel flange and head flange temperatures are required to be verified to be within the limits specified.

(continued)

DAEC B 3.4-57 TSCR-120

Reactor Steam Dome Pressure B 3.4.10 BASES APPLICABILITY In MODES 4, and 5, the reactor pressure is well below the (continued) required limit due to the pressure and temperature limits of these MODES, and no anticipated events will challenge either the fuel thermal limits or the vessel overpressure limit.

ACTIONS A.1 With the reactor steam dome pressure greater than the limit, prompt action should be taken to reduce pressure to below the limit and return the reactor to operation within the bounds of the analyses. The 15 minute Completion Time is reasonable considering the importance of maintaining the pressure within limits. This Completion Time also ensures that the probability of an accident occurring while pressure is greater than the limit is minimized.

B.1 If the reactor steam dome pressure cannot be restored to within the limit within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.4.10.1 REQUIREMENTS Verification that reactor steam dome pressure is _<1025 psig ensures that the initial conditions of the accident and transient analyses are met. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Operating experience has shown the Frequency to be sufficient for identifying trends and verifying operation within safety analyses assumptions.

(continued)

DAEC B 3.4-60 TSCR-120

ECCS - Operating B 3.5.1 BASES ACTIONS M.1 and M.2 (continued)

If any Required Action and associated Completion Time of Condition K or L is not met, or if two or more ADS valves are inoperable, the plant must be brought to a condition in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reactor steam dome pressure reduced to <_100 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

N.1 When multiple ECCS subsystems are inoperable, as stated in Condition N, the plant is in a condition outside of the accident analyses. Therefore, LCO 3.0.3 must be entered immediately.

SURVEILLANCE SR 3.5.1.1 REQUIREMENTS The flow path piping has the potential to develop bubbles and pockets of entrained air. Maintaining the pump discharge line of the HPCI system, CS system, and LPCI subsystems full of water (up to the normally closed injection valve) ensures that the ECCS will perform properly, injecting its full capacity into the RCS upon demand. This will also prevent a potential water hammer following an ECCS initiation signal. An acceptable method of ensuring that the CS or LPCI discharge lines are full is to vent at the respective high points. Another acceptable method for CS and LPCI is to verify the absence of their respective discharge line Low Pressure Annuciator alarms. Acceptable methods for HPCI are the combination of venting at high points and, either ensuring adequate CST water level or that the HPCI Low Pressure Keep Fill is in service. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the gradual nature of bubble buildup in the ECCS piping, the procedural controls governing system operation and operating experience.

(continued)

DAEC B 3.5-13 TSCR-1 20

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.2 REQUIREMENTS (continued) Verifying the correct alignment for power operated and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to manual valves or valves that cannot be inadvertently misaligned, such as check valves. For the HPCI System, this SR also includes the steam flow path for the turbine and the flow controller position.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing. The Frequency is further justified because the valves are operated under procedural control and because improper valve position would only affect a single subsystem. This Frequency has been shown to be acceptable through operating experience.

In Mode 3 with reactor steam dome pressure less than the actual RHR interlock pressure, the RHR System may be required to operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore, this SR is modified by Note 1, which allows the LPCI System to be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable. Alignment and operation for decay heat removal includes when the required RHR pump is not operating or when the system is realigned from or to the RHR shutdown cooling mode. At the low pressures and decay heat loads associated with operation in Mode 3 with reactor steam dome pressure less than the RHR interlock pressure, a reduced complement of low pressure ECCS subsystems should provide the required core cooling, thereby allowing operation of RHR shutdown cooling, when necessary.

(continued)

DAEC B 3.5-14 TSCR-120

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.3 REQUIREMENTS (continued)

Verification that a 100 day supply of nitrogen exists for each ADS accumulator ensures adequate nitrogen pressure for reliable ADS operation. The accumulator on each ADS valve provides pneumatic pressure for valve actuation. The design pneumatic supply pressure requirements for the accumulator are such that following a failure of the pneumatic supply to the accumulator, each ADS valve can be actuated at least 5 times up to 100 days following a LOCA (Reference 4). This SR can be met by either: 1) verifying that the drywell nitrogen header supply pressure is _>90 psig, or 2) when drywell nitrogen header supply pressure is < 90 psig, using the actual accumulator check valve leakage rates obtained from the most-recent tests to determine, analytically, that a 100 day supply of nitrogen exists for each accumulator. The results of this analysis can also be used to determine when the 100 day supply of nitrogen will no longer exist for individual ADS accumulators, and when each ADS valve would subsequently be required to be declared inoperable, assuming the drywell nitrogen supply pressure is not restored to >_90 psig. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into consideration administrative controls over operation of the nitrogen system and alarms for low nitrogen pressure.

SR 3.5.1.4, SR 3.5.1.5, and SR 3.5.1.6 The performance requirements of the low pressure ECCS pumps are determined through application of the 10 CFR 50, Appendix K criteria (Ref. 8). This periodic Surveillance is performed (in accordance with the ASME Code, Section Xl, requirements for the ECCS pumps) to verify that the ECCS pumps will develop the flow rates required by the respective analyses. The low pressure ECCS pump flow rates ensure that adequate core cooling is provided to satisfy the acceptance criteria of Reference 10. The pump flow rates are verified against a system head equivalent to the RPV pressure expected during a LOCA. The total system pump outlet pressure is adequate to overcome the elevation head pressure between the pump suction and the vessel discharge, the piping friction losses, and RPV pressure present during a LOCA.

These values may be established during preoperational testing or by analysis.

(continued)

DAEC B 3.5-15 TSCR-120

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.4, SR 3.5.1.5, and SR 3.5.1.6 (continued)

REQUIREMENTS The flow tests for the HPCI System are performed at two different pressure ranges such that system capability to provide rated flow is tested at both the higher and lower operating ranges of the system. Additionally, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the HPCI System diverts steam flow. Reactor steam pressure must be _>940 psig to perform SR 3.5.1.5, the high pressure test, and < 160 psig to perform SR 3.5.1.6, the low pressure test. Adequate steam flow is represented by approximately 0.5 turbine bypass valves open.

Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these tests. Reactor startup is allowed prior to performing the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the. Surveillance test is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure test has been satisfactorily completed and there is no indication or reason to believe that HPCI is inoperable.

Therefore, SR 3.5.1.5 and SR 3.5.1.6 are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the reactor steam pressure and flow are adequate to perform the test. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowance to reach the required pressure and flow is sufficient to achieve stable conditions for testing and provide a reasonable time to complete the SRs.

The Frequency for SR 3.5.1.4 and SR 3.5.1.5 is in accordance with the Inservice Testing Program requirements. The Surveillance Frequency for SR 3.5.1.6 is controlled under the Surveillance Frequency Control Program. The Frequency for SR 3.5.1.6 is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a plant outage. Operating experience has shown that these components usually pass the SR when performed at this Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

(continued)

DAEC B 3.5-16 TSCR-120

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.7 REQUIREMENTS (continued) The ECCS subsystems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, CS, and LPCI will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emergency operating sequence, automatic pump startup and actuation of all automatic valves to their required positions. As part of this SR for the LPCI system, a verification of the "power-seeking" logic for the LPCI "Swing Bus" (1B34A and 1B44A), i.e., the ability to transfer power sources from either AC Essential Bus upon loss of power (either AC or 125 VDC), is included. This verification, when coupled with the verification of the "break-before-make" coordination of the breakers in SR 3.8.7.2, demonstrate the ability of the Swing Bus to perform its intended safety function in support of the Loop Select design of the LPCI system without compromising the independence of the AC Distribution System (Reference 16). This SR also ensures that the HPCI System will automatically restart on an RPV low water level signal received subsequent to an RPV high water level trip and that the suction is automatically transferred from the CST to the suppression pool on a CST Low Water Level Signal or Torus High Water Level Signal. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlaps this Surveillance to provide complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Operating experience has shown that these components usually pass the SR when performed at this Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by two Notes. The first Note excludes vessel injection/spray during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance. The second Note is added to SR 3.5.1.7 to allow the surveillance to be met by performing the test in any number of sequential and/or overlapping steps, rather than in a single, contiguous performance.

(continued)

DAEC B 3.5-17 TSCR-120

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.7 (continued)

REQUIREMENTS This is necessary because testing the entire LPCI Loop Select Logic would interfere with forced reactor coolant circulation and/or decay heat removal functions and require multiple LPCI System starts to demonstrate all the Loop Select Logic features (e.g.,

injections paths, single loop operation and "swing" bus).

Therefore, each of the required features can be tested either individually or in appropriate combinations (including overlap with other LCO 3.5.1 surveillances, the Instrumentation surveillances required by LCO 3.3.5.1 and the "swing" bus breaker coordination surveillance in LCO 3.8.7), such that the overall function is tested on the required Frequency.

SR 3.5.1.8 The ADS designated SRVs are required to actuate automatically upon receipt of specific initiation signals. A system functional test is performed to demonstrate that the mechanical portions of the ADS function (i.e., solenoids) operate as designed when initiated either by an actual or simulated initiation signal, causing proper actuation of all the required components. SR 3.5.1.9 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform the Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the SR when performed at this Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes valve actuation, since the valves are individually tested in accordance with SR 3.5.1.9.

This prevents an RPV pressure blowdown.

(continued)

DAEC B 3.5-18 TSCR-120

ECCS - Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.9 REQUIREMENTS (continued) A manual actuation of each ADS valve is performed to verify that the valve and solenoid are functioning properly and that no blockage exists in the SRV discharge lines. This is demonstrated by the response of the turbine control or bypass valve or by a change in the measured flow or by any other method suitable to verify steam flow (such as actuation of the SRV tailpipe pressure switches or thermocouples). Adequate reactor steam dome pressure must be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the ADS valves divert steam flow upon opening. Sufficient time is therefore allowed after the required pressure and flow are achieved to perform this SR. Adequate pressure at which this SR is to be performed is approximately 150 psig which is the lowest pressure EHC can maintain. Adequate steam flow is represented by approximately 1.15 turbine bypass valves open. Reactor startup is allowed prior to performing this SR because valve OPERABILITY and the setpoints for overpressure protection are verified, per ASME requirements, prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test. The 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed for manual actuation after the required pressure and flow is reached is sufficient to achieve stable conditions and provides adequate time to complete the Surveillance. SR 3.5.1.8 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a plant outage. Operating experience has shown that these components usually pass the SR when performed at this Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

(continued)

DAEC B 3.5-19 TSCR-1 20

ECCS - Shutdown B 3.5.2 BASES SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 (continued)

REQUIREMENTS When suppression pool level is < 8.0 ft, the CS System is considered OPERABLE only if it can take suction from the CST, and the CST water level is sufficient to provide the required NPSH for the CS pump. Therefore, a verification that either the suppression pool water level is >_8.0 ft or that CS is aligned to take suction from the CSTs and the CSTs contain

_>75,000 gallons of water, equivalent to 11 ft in one CST or _>7 ft in both CSTs, ensures that the CS System can supply at least 75,000 gallons of makeup water to the RPV. However, as noted, only one required CS subsystem may take credit for the CST option during OPDRVs. During OPDRVs, the volume in the CST may not provide adequate makeup if the RPV were completely drained. Therefore, only one CS-subsystem is allowed to use the CST. This ensures the other required ECCS subsystem has adequate makeup volume.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of these SRs was developed considering operating experience related to suppression pool water level and CST water level variations during the applicable MODES. Furthermore, the Frequency is considered adequate in view of other indications available in the control room to alert the operator to an abnormal suppression pool or CST water level condition.

SR 3.5.2.3, SR 3.5.2.5, and SR 3.5.2.6 The Bases provided for SR 3.5.1.1, SR 3.5.1.4, and SR 3.5.1.7 are applicable to SR 3.5.2.3, SR 3.5.2.5, and SR 3.5.2.6, respectively.

SR 3.5.2.4 Verifying the correct alignment for power operated and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the (continued)

DAEC B 3.5-25 TSCR-120

ECCS - Shutdown B 3.5.2 BASES SURVEILLANCE SR 3.5.2.4 (continued)

REQUIREMENTS valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to manual valves or to valves that cannot be inadvertently misaligned, such as check valves. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is appropriate because the valves are operated under procedural control and the probability of their being mispositioned during this time period is low.

In Modes 4 and 5, the RHR System may be required to operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore, this SR is modified by a Note that allows one LPCI subsystem to be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable. Alignment and operation for decay heat removal includes when the required RHR pump is not operating or when the system is realigned from or to the RHR shutdown cooling mode. Because of the low pressure and low temperature conditions in Modes 4 and 5, sufficient time will be available to manually align and initiate LPCI subsystem operation to provide core coverage prior to postulated fuel uncovery. This will ensure adequate core cooling if an inadvertent RPV draindown should occur.

REFERENCES 1. UFSAR, Section 15.2.1.1.

DAEC B 3.5-26 TSCR-120

RCIC System B 3.5.3 BASES ACTIONS B.1 and B.2 (continued)

If the RCIC System cannot be restored to OPERABLE status within the associated Completion Time, or if the HPCI System is simultaneously inoperable, the plant must be brought to a condition in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reactor steam dome pressure reduced to < 150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.5.3.1 REQUIREMENTS The flow path piping has the potential to develop bubbles and pockets of entrained air. Maintaining the pump discharge line of the RCIC system full of water ensures that the system will perform properly, injecting its full capacity into the RCS upon demand.

This will also prevent a potential water hammer following an initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points with RCIC suction aligned to the CST. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the gradual nature of bubble buildup in the RCIC piping, the procedural controls governing system operation and operating experience.

SR 3.5.3.2 Verifying the correct alignment for power operated and automatic valves in the RCIC flow path provides assurance that the proper flow path will exist for RCIC operation. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time.

This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to manual valves or to valves that cannot be inadvertently misaligned, such as check valves. For the RCIC System, this SR also includes the steam flow path for the turbine and the flow controller position.

(continued)

DAEC B 3.5-30 ' TSCR-120

RCIC System B 3.5.3 BASES SURVEILLANCE SR 3.5.3.2 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing. The Frequency is further justified because the valves are operated under procedural control and because improper valve position would affect only the RCIC System. This Frequency has been shown to be acceptable through operating experience.

SR 3.5.3.3 and SR 3.5.3.4 The RCIC pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized conditions with the RPV isolated. The flow tests for the RCIC System are performed at two different pressure ranges such that system capability to provide rated flow is tested both at the higher and lower operating ranges of the system. Additionally, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the RCIC System diverts steam flow. Reactor steam pressure must be > 940 psig to perform SR 3.5.3.3, the high pressure test, and < 160 psig to perform SR 3.5.3.4, the low pressure test. Adequate steam flow is represented by approximately 0.4 turbine bypass valves open.

Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these SRs. Reactor startup is allowed prior to performing the low pressure Surveillance because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure Surveillance has been satisfactorily completed and there is no indication or reason to believe that RCIC is inoperable.

Therefore, these SRs are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the reactor steam pressure and flow are adequate to perform the test. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowance to reach the required pressure and flow is sufficient to achieve stable conditions for testing and provide a reasonable time to complete the SRs.

(continued)

DAEC B 3.5-31 TSCR-120

RCIC System B 3.5.3 BASES SURVEILLANCE SR 3.5.3.3 and SR 3.5.3.4 (continued)

REQUIREMENTS The Frequency for SR 3.5.3.3 is in accordance with the Inservice Testing Program. The Surveillance Frequency for SR3.5.3.4 is controlled under the Surveillance Frequency Control Program.

The Frequency for SR 3.5.3.4 is based on the need to perform the Surveillance under conditions that apply just prior to or during a startup from a plant outage. Operating experience has shown that these components usually pass the SR when performed at this Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

SR 3.5.3.5 The RCIC System is required to actuate automatically in order to verify its design function satisfactorily. This Surveillance verifies that, with a required system initiation signal (actual or simulated),

the automatic initiation logic of the RCIC System will cause the system to operate as designed, including actuation of the system throughout its emergency operating sequence; that is, automatic pump startup and actuation of all automatic valves to their required positions. This test also ensures the RCIC System will automatically restart on an RPV low water level signal received subsequent to an RPV high water level trip and that the suction is automatically transferred from the CST to the suppression pool on a CST Low Level signal. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps this Surveillance to provide complete testing of the assumed design function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform the Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the SR when performed at this Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes vessel injection during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

(continued)

DAEC B 3.5-32 TSCR-120

Primary Containment B 3.6.1.1 BASES SURVEILLANCE SR 3.6.1.1.2 (continued)

REQUIREMENTS drywell to suppression chamber differential pressure during a 10 minute period to measure and ensure that the leakage paths that would bypass the suppression pool are within allowable limits.

Satisfactory performance of this SR can be achieved by establishing a known differential pressure between the drywell and the suppression chamber and verifying that the increase in suppression chamber pressure is less than 0.009 psi per minute when averaged over a 10 minute period. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency was developed considering it is required that this Surveillance be performed during a unit outage and also in view of the fact that component failures that might have affected this test are identified by other primary containment SRs.

REFERENCES 1. UFSAR, Section 6.2.

2. UFSAR, Section 15.2.

3. 10 CFR 50, Appendix J, Option B.

4. NEI 94-01, Revision 0, "Industry Guideline for Implementing Performance - Based Option of 10 CFR Part 50, Appendix J."

5. ANSI/ANS-56.8-1994, "American National Standard for Containment System Leakage Testing Requirement."

DAEC B 3.6-5 TSCR-120

Primary Containment Air Lock B 3.6.1.2 BASES SURVEILLANCE SR 3.6.1.2.2 REQUIREMENTS (continued) The air lock interlock mechanism is designed to prevent simultaneous opening of both doors in the air lock. Since both the inner and outer doors of an air lock are designed to withstand the maximum expected post accident primary containment pressure, closure of either door will support primary containment OPERABILITY. Thus, the interlock feature supports primary containment OPERABILITY while the air lock is being used for personnel transit in and out of the containment. Periodic testing of this interlock demonstrates that the interlock will function as designed and that simultaneous inner and outer door opening will not inadvertently occur. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Due to the purely mechanical nature of this interlock, and given that the interlock mechanism is not normally challenged when the primary containment airlock door is used for entry and exit (procedures require strict adherence to single door opening) and the potential for loss of primary containment OPERABILITY if the Surveillance were performed with the reactor at power, this test is only required to be performed under the conditions that apply during a plant outage. The Frequency for the interlock is justified based on generic operating experience. The Frequency is based on engineering judgment and is considered adequate given that the interlock is not challenged during use of the airlock.

REFERENCES 1. UFSAR, Section 6.2.1.1.

2. 10 CFR 50, Appendix J, Option B.

3. UFSAR, Section 15.2.1.

DAEC B 3.6-13 TSCR-120

PCIVs B 3.6.1.3 BASES SUREVEILLANCE SR 3.6.1.3.1 (continued)

REQUIREMENTS inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surevillances that require the valves to be open. The 18 inch purge valves are capable of closing in the enviornment following a LOCA. Therefore, these valves are allowed to be open for limited periods of time.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency was chosen to provide added assurance that the purge valves are in the correct position.

SR 3.6.1.3.2 The traversing incore probe (TIP) shear isolation valves are actuated by explosive charges. Surveillance of explosive charge continuity provides assurance that TIP valves will actuate when required. Other administrative controls, such as those that limit the shelf life of the explosive charges, must be followed. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience that has demonstrated the reliability of the explosive charge continuity.

SR 3.6.1.3.3 Verifying the isolation time of each power operated automatic PCIV is within limits is required to demonstrate OPERABILITY.

MSIVs may be excluded from this SR since MSIV full closure isolation time is demonstrated by SR 3.6.1.3.5. The isolation time test ensures that the valve will isolate in a time period less than or equal to that assumed in the safety analyses. The isolation time and Frequency of this SR are in accordance with the requirements of the Inservice Testing Program.

SR 3.6.1.3.4 For primary containment purge valves with resilient seals, additional leakage rate testing beyond the test requirements of 10 CFR 50, Appendix J, Option B (Ref. 3), is required to ensure OPERABILITY. Operating experience has demonstrated that this type of seal has the potential to degrade in a shorter time period than do other seal types. Based on this observation and the importance of maintaining this penetration leak tight (due to the direct path between primary containment and the environment), a (continued)

DAEC B 3.6-26 TSCR-120

PCIVs B 3.6.1.3 BASES SURVEILLANCE SR 3.6.1.3.4 (continued)

REQUIREMENTS corresponding Surveillance Frequency. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The purge system isolation valves are tested in three groups, by penetration:

drywell purge exhaust group (CV-4302 and CV-4303), torus purge exhaust group (CV-4300 and CV-4301), and drywell/torus purge supply group (CV-4307, CV-4308 and CV-4306). If the results of a combined leak rate or pressure drop test indicate excessive leakage, credit can be taken for one of the purge valves to satisfy Required Action E.1, if it can be reasonably determined that the purge valve to be credited for isolation is not leaking excessively.

Additionally, this SR must be performed once within 92 days after opening the valve. The 92 day Frequency was chosen recognizing that cycling the valve could introduce additional seal degradation (beyond that which occurs to a valve that has not been opened.) Thus, decreasing the normal Surveillance interval is a prudent measure after a valve has been opened.

SR 3.6.1.3.5 Verifying that the isolation time of each MSIV is within the specified limits is required to demonstrate OPERABILITY. The isolation time test ensures that the MSIV will isolate in a time period that does not exceed the times assumed in the DBA analyses. This ensures that the calculated radiological consequences of these events remain within 10 CFR 50.67 limits and that the core remains covered. The Frequency of this SR is in accordance with the requirements of the Inservice Testing Program.

SR 3.6.1.3.6 Automatic PCIVs close on a primary containment isolation signal to prevent leakage of radioactive material from primary containment following a DBA. This SR ensures that each automatic PCIV will actuate to its isolation position on a primary containment isolation signal.

The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.6.1, "Primary Containment Isolation Instrumentation," overlaps this SR to provide complete testing of the safety function. A Note has been added for the MSIVs, that allows this SR to be met by any series of sequential, overlapping, or total steps so that proper operation of the MSIVs on receipt of an actual or simulated isolation signal is verified. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency was developed considering it is prudent that this Surveillance be performed only during a unit outage since isolation of penetrations would eliminate cooling water flow and (continued)

DAEC B 3.6-27 TSCR-120

PCIVs B 3.6.1.3 BASES SURVEILLANCE SR 3.6.1.3.6 (continued)

REQUIREMENTS disrupt the normal operation of many critical components.

Operating experience has shown that these components usually pass this Surveillance when performed at this Frequency.

Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

SR 3.6.1.3.7 This SR requires a demonstration that a representative sample of reactor instrumentation line Excess Flow Check Valves (EFCVs) are OPERABLE by verifying that the valves cause a marked decrease in flow rate on a simulated instrument line break. This SR provides assurance that the instrumentation line EFCVs will perform so that predicted radiological consequences will not be exceeded during the postulated instrument line break event evaluated in Reference 5. The representative sample consists of an approximately equal number of EFCVs, such that each EFCV is tested at least once every 10 years (nominal). The nominal 10 year interval is based on other performance-based testing programs, such as Inservice Testing (snubbers) and Option B to 10 CFR 50, Appendix J. EFCV test failures will be evaluated to determine if additional testing in that test interval is warranted to ensure overall reliability is maintained. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Operating experience has demonstrated that these components are highly reliable and that failures to isolate are very infrequent. Therefore, testing of a representative sample was concluded to be acceptable from a reliability standpoint (Reference 10).

SR 3.6.1.3.8 The TIP shear isolation valves are actuated by explosive charges.

An in place functional test is not possible with this design. The explosive squib is removed and tested to provide assurance that the valves will actuate when required. The replacement charge for the explosive squib shall be from the same manufactured batch as the one fired or from another batch that has been certified by having one of the batch successfully fired. Other administrative controls, such as those that limit the shelf life of the explosive charges, must also be followed. The Frequency of this SR is in accordance with the requirements of the Inservice Testing Program.

(continued)

DAEC B 3.6-28 TSCR-120

Drywell Air Temperature B 3.6.1.4 BASES (continued)

SURVEILLANCE SR 3.6.1.4.1 REQUIREMENTS Verifying that the drywell average air temperature is within the LCO limit ensures that operation remains within the limits assumed for the primary containment analyses. Drywell air temperature is monitored in all quadrants and at various elevations (referenced to mean sea level). Due to the shape of the drywell, a volumetric average is used to determine an accurate representation of the actual average temperature.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of the SR was developed based on operating experience related to drywell average air temperature variations and temperature instrument drift during the applicable MODES and the low probability of a DBA occurring between surveillances. Furthermore, the Frequency is considered adequate in view of other indications available in the control room, including alarms, to alert the operator to an abnormal drywell air temperature condition.

REFERENCES 1. UFSAR, Section 15.0.

2. UFSAR, Section 15.2.1.

DAEC B 3.6-32 TSCR-120

LLS Valves B 3.6.1.5 BASES ACTIONS B.1 and B.2 (continued)

If both LLS valves are inoperable or if the inoperable LLS valve cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.1.5.1 REQUIREMENTS A manual actuation of each LLS valve is performed to verify that the valve and solenoids are functioning properly and no blockage exists in the valve discharge line. This can be demonstrated by the response of the turbine control or bypass valve, by a change in the measured steam flow, or by any other method that is suitable to verify steam flow. Adequate reactor steam dome pressure must be available to perform this test to avoid damaging the valve. Adequate pressure at which this test is to be performed is approximately 150 psig which is the lowest pressure EHC can maintain. Also, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the LLS valves divert steam flow upon opening. Adequate steam flow is represented by approximately 1.15'turbine bypass valves open. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency was based on the SRV tests required by the ASME Boiler and Pressure Vessel Code,Section XI (Ref. 2).

Operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

Since steam pressure is required to perform the Surveillance, however, and steam may not be available during a unit outage, the Surveillance may be performed during the startup following a unit outage. Unit startup is allowed (continued)

DAEC B 3.6-35 TSCR-1120

LLS Valves B 3.6.1.5 BASES SURVEILLANCE SR 3.6.1.5.1 (continued)

REQUIREMENTS prior to performing the test because valve OPERABILITY and the setpoints for overpressure protection are verified in accordance with Reference 2 prior to valve installation. After adequate reactor steam dome pressure and flow are reached, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed to prepare for and perform the test.

SR 3.6.1.5.2 The LLS designated SRVs are required to actuate automatically upon receipt of specific initiation signals. A system functional test is performed to verify that the mechanical portions (i.e., solenoids) of the LLS function operate as designed when initiated either by an actual or simulated automatic initiation signal. The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.6.3, "Low-Low Set (LLS) Instrumentation," overlaps this SR to provide complete testing of the safety function.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at this Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes valve actuation. This prevents a reactor pressure vessel pressure blowdown.

REFERENCES 1. UFSAR, Section 5.4.13.

2. ASME, Boiler and Pressure Vessel Code, Section Xl.

3. NEDE-30021-P, Low-Low Set Relief Logic System and Lower MSIV Water Level Trip for DAEC, January 1983.

DAEC B 3.6-36 TSCR-120

Reactor Building-to-Suppression Chamber Vacuum Breakers B 3.6.1.6 BASES SURVEILLANCE SR 3.6.1.6.1 (continued)

REQUIREMENTS breaker assembly valve be periodically verified to be closed by visual inspection. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment, is considered adequate in view of other indications of vacuum breaker assembly valve status available to operations personnel, and has been shown to be acceptable through operating experience.

Two Notes are added to this SR. The first Note allows reactor building-to-suppression chamber vacuum breaker assembly valves opened in conjunction with the performance of a Surveillance to not be considered as failing this SR. These periods of opening vacuum breaker assembly valves are controlled by plant procedures and do not represent inoperable vacuum breaker assembly valves. The second Note is included to clarify that vacuum breaker assembly valves open due to an actual differential pressure are not considered as failing this SR.

SR 3.6.1.6.2 Each vacuum breaker assembly valve must be cycled to ensure that it opens properly to perform its design function and returns to its fully closed position. This ensures that the safety analysis assumptions are valid. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of this SR was developed based upon Inservice Testing Program requirements for performing valve testing.

SR 3.6.1.6.3 Demonstration of vacuum breaker assembly valve opening setpoint is necessary to ensure that the safety analysis assumption regarding vacuum breaker assembly valve full open differential pressure of*< 0.614 psid is valid. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based upon the magnitude of equipment drift in the setpoint analysis.

REFERENCES 1. UFSAR, Section 6.2.1.1.2.5.

DAEC B 3.6-42 TSCR-120

Suppression Chamber-to-Drywell Vacuum Breakers B 3.6.1.7 BASES ACTIONS C.1 and C.2 (continued) must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.1.7.1 REQUIREMENTS Each vacuum breaker is verified closed (except when performing its intended function as stated in LCO 3.6.1.7) to ensure that this potential large bypass leakage path is not present. This Surveillance is performed by observing the vacuum breaker position indication or by verifying that a differential pressure of 0.5 psid between the suppression chamber and drywell is maintained for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months without makeup. Each vacuum breaker is equipped with two closed position indicators. One position indicator indicating closed is sufficient to verify the vacuum breaker is closed. However, if one closed position indicator is found to be inoperable, actions should be initiated to restore it to OPERABLE status, if possible. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is based on engineering judgment, is considered adequate in view of other indications of vacuum breaker status available to operations personnel, and has been shown to be acceptable through operating experience.

A Note is added to this SR which allows suppression chamber-to-drywell vacuum breakers opened in conjunction with the performance of a Surveillance to not be considered as failing this SR. These periods of opening vacuum breakers are controlled by plant procedures and do not represent inoperable vacuum breakers.

SR 3.6.1.7.2 Each required vacuum breaker must be cycled to ensure that it opens adequately to perform its design function and returns to the fully closed position. This ensures that the safety analysis assumptions are valid. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of this SR was developed, based on Inservice Testing Program requirements (continued)

DAEC B 3.6-47 TSCR-120

Suppression Chamber-to-Drywell Vacuum Breakers B 3.6.1.7 BASES SURVEILLANCE SR 3.6.1.7.2 (continued)

REQUIREMENTS for performing valve testing. The Frequency was chosen to provide additional assurance that the vacuum breakers are OPERABLE, since they are located in a harsh environment (the suppression chamber airspace).

SR 3.6.1.7.3 Verification of the vacuum breaker opening setting is necessary to ensure that the safety analysis assumption regarding vacuum breaker full open differential pressure of 0.5 psid is valid. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. The Frequency has been shown to be acceptable, based on operating experience, and is further justified because of other surveillances performed at shorter Frequencies that convey the proper functioning status of each vacuum breaker.

REFERENCES 1. UFSAR, Section 6.2.1.1.2.5.

2. UFSAR, Section 6.2.1.4.2.

DAEC B 3.6-48 TSCR-120

Suppression Pool Average Temperature B 3.6.2.1 BASES ACTIONS D.1, D.2, and D.3 (continued)

Given the high suppression pool average temperature in this Condition, the monitoring Frequency is increased to twice that of Condition A. Furthermore, the 30 minute Completion Time is considered adequate in view of other indications available in the control room to alert the operator to an abnormal suppression pool average temperature condition.

E.1 and E.2 If suppression pool average temperature cannot be maintained at

< 120'F, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the reactor pressure must be reduced to < 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and the plant must be brought to at least MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

Continued addition of heat to the suppression pool with suppression pool temperature > 120'F could result in exceeding the design basis maximum allowable values for primary containment temperature or pressure post-LOCA. Furthermore, if a blowdown were to occur when the temperature was > 120 0 F, the maximum allowable bulk suppression pool temperature could be exceeded very quickly and possibly exceed the allowable loads on the Torus.

SURVEILLANCE SR 3.6.2.1.1 REQUIREMENTS The suppression pool average temperature is regularly monitored to ensure that the required limits are satisfied. The average temperature is determined by taking an arithmetic average of OPERABLE suppression pool water temperature channels. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency has been shown, based on operating experience, to be acceptable. When heat is being added to the suppression pool by testing, however, it is necessary to monitor suppression pool temperature more frequently.

(continued)

DAEC B 3.6-53 TSCR-120

Suppression Pool Water Level B 3.6.2.2 BASES (continued)

ACTIONS A.1 With suppression pool water level outside the limits, the conditions assumed for the safety analyses are not met. Ifwater level is below the minimum level, the pressure suppression function still exists as long as vent system downcomer pipes are covered, HPCI and RCIC turbine exhausts are covered, and SRV T-quenchers are covered. If suppression pool water level is above the maximum level, protection against overpressurization still exists due to the margin in the peak containment pressure analysis. Therefore, continued operation for a limited time is allowed. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time is sufficient to restore suppression pool water level to within limits. Also, it takes into account the low probability of an event impacting the suppression pool water level occurring during this interval.

B.1 and B.2 If suppression pool water level cannot be restored to within limits within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.2.2.1 REQUIREMENTS Verification of the suppression pool water level is to ensure that the required limits are satisfied. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency of this SR was developed considering operating experience related to trending variations in suppression pool water level and water level instrument drift during the applicable MODES and to assessing the proximity to the specified LCO level limits. Furthermore, the Frequency is considered adequate in view of other indications available in the control room, including alarms, to alert the operator to an abnormal suppression pool water level condition.

(continued)

DAEC B 3.6-57 TSCR-1120

RHR Suppression Pool Cooling B 3.6.2.3 BASES (continued)

SURVEILLANCE SR 3.6.2.3.1 REQUIREMENTS Verifying by administrative means the correct alignment for manual, power operated and automatic valves in the RHR suppression pool cooling mode flow path provides assurance that the proper flow path exists for system operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these valves were verified to be in the correct position prior to locking, sealing or securing. A valve is also allowed to be in the nonaccident position provided it can be aligned to the accident position within the time assumed in the accident analysis. This is acceptable since the RHR suppression pool cooling mode is manually initiated. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position. This SR does not apply to manual valves or to valves that cannot be inadvertently misaligned, such as check valves.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is justified because the valves are operated under procedural control, improper valve position would affect only a single subsystem, the probability of an event requiring initiation of the system is low, and the subsystem is a manually initiated system. This Frequency has been shown to be acceptable based on operating experience.

SR 3.6.2.3.2 Verifying that each RHR pump develops a flow rate _>4800 gpm while operating in the suppression pool cooling mode with flow through the associated heat exchanger ensures that the primary containment peak pressure and temperature and the local suppression pool temperature can be maintained below design limits. This test also verifies that pump performance has not degraded during the surveillance interval. Flow is a normal test of centrifugal pump performance required by ASME Code, Section X1 (Ref. 2). This test confirms one point on the pump design curve, and the results are indicative of overall performance. Such inservice testing confirms component OPERABILITY, trends performance, and detects incipient failures by indicating abnormal performance. The Frequency of this SR is in accordance with the Inservice Testing Program.

(continued)

DAEC B 3.6-63 TSCR-120

RHR Suppression Pool Spray B 3.6.2.4 BASES (continued)

SURVEILLANCE SR 3.6.2.4.1 REQUIREMENTS Verifying that the spray header and nozzles are unobstructed assures that the suppression pool airspace can be sprayed when desired. An air test is specified as this test is generally performed on both the drywell and suppression pool spray nozzles at the same time and it is not desirable to spray water into the drywell, due to the adverse impact on equipment located there.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Operating experience has shown that these components usually pass the SR when performed at this Frequency. Therefore, the Frequency was concluded to be acceptable from the reliability standpoint.

REFERENCES 1. UFSAR, Section 15.2.1.

2. NG-98-0342, J. Franz (IES) to U.S. NRC, "Request for Technical Specification Change (RTS-291): Revision E to the Duane Arnold Energy Center Improved Technical Specifications," February 26, 1998.

DAEC B 3.6-68 TSCR-120

Primary Containment Oxygen Concentration B 3.6.3.2 BASES ACTIONS B.1 (continued)

If oxygen concentration cannot be restored to within limits within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, power must be reduced to _<15% RTP within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Completion Time is reasonable, based on operating experience, to reduce reactor power from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.3.2.1 REQUIREMENTS The primary containment must be determined to be inert by verifying that oxygen concentration is < 4.0 v/o. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based. on the slow rate at which oxygen concentration can change and on other indications of abnormal conditions (control room alarms for containment high oxygen concentration, excessive cycling of the Containment Nitrogen Makeup System or unexplained changes in containment pressure). Indication of abnormal conditions would lead to more frequent monitoring of primary containment oxygen concentration.

Also, this Frequency has been shown to be acceptable through operating experience.

REFERENCES 1. Federal Register Notice 68 FR 54123, Combustible Gas Control in Containment, Final Rule, dated September 16, 2003.

(continued)

DAEC B 3.6-76 TSCR-1120

Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.1 and SR 3.6.4.1.2 (continued)

REQUIREMENTS opening is being used for entry and exit or when maintenance is being performed on an access. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency for these SRs has been shown to be adequate, based on operating experience, and is considered adequate in view of the other indications of door and hatch status that are available to the operator (alarmed security/secondary containment doors, frequent plant tours by operations and security personnel and unexplained drops in reactor building to outside atmosphere differential pressure while secondary containment is isolated with SBGT in service). SR 3.6.4.1.2 is modified by a Note that applies to doors located in high radiation areas and allows them to be verified by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Therefore, the probability of misalignment of these doors, once they have been verified to be in the proper position, is low.

SR 3.6.4.1.3 The SBGT System exhausts the secondary containment atmosphere to the environment through appropriate treatment equipment. SR 3.6.4.1.3 demonstrates that one SBGT subsystem can maintain > 0.25 inches of vacuum water gauge under calm wind conditions (i.e., less than 15 mph wind speed) at a flow rate

_<4000 cfm. This cannot be accomplished if the secondary containment boundary is not intact. Therefore, this test is used to ensure secondary containment boundary integrity. Since this SR is a secondary containment test, it need not be performed with each SBGT subsystem. The SBGT subsystems are tested on an alternating basis, however, to ensure that in addition to the requirements of LCO 3.6.4.3, either SBGT subsystem will perform this test, and also to ensure that the secondary containment remains sufficiently leak tight, even with a worst case single failure present (i.e., a lockout relay failure that results in either all of the inboard or all of the outboard SCIV/Ds failing to close). The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Operating experience has shown these components usually pass the Surveillance when performed at this Frequency.

Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

(continued)

DAEC B 3.6-81 TSCR-120

SCIV/Ds B 3.6.4.2 BASES (continued)

ACTIONS C.1 and C.2 (continued)

The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

D.1 If any Required Action and associated Completion Time are not met, the plant must be placed in a condition in which the LCO does not apply. Actions must be immediately initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and the subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

LCO 3.0.3 is not applicable while in MODE 4 or 5 when OPDRVs can occur. Required Action D.1 has been modified by a Note stating that LCO 3.0.3 is not applicable.

SURVEILLANCE SR 3.6.4.2.1 REQUIREMENTS Verifying that the isolation time of each power operated automatic SCIV/D is within limits is required to demonstrate OPERABILITY.

The isolation time test ensures that the SCIV/D will isolate in a time period less than or equal to that assumed in the safety analyses. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.6.4.2.2 Verifying that each automatic SCIV/D closes on a secondary containment isolation signal is required to prevent leakage of radioactive material from secondary containment following a DBA or which are released during certain operations when primary containment is not required to be OPERABLE or take place outside primary containment. This SR ensures that each automatic SCIV/D will actuate to the isolation position on a secondary containment isolation signal. The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," overlaps this SR to provide complete testing of the safety function. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is based (continued)

DAEC B 3.6-88 TSCR-1 20

SCIV/Ds B 3.6.4.2 BASES SURVEILLANCE SR 3.6.4.2.2 (continued)

REQUIREMENTS on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at this Frequency.

Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

REFERENCES 1. UFSAR, Section 15.2.1.1.

DAEC B 3.6-89 TSCR-120

SBGT System B 3.6.4.3 BASES ACTIONS E.1 (continued)

When two SBGT subsystems are inoperable, if applicable, actions must Immediately be initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

LCO 3.0.3 is not applicable in MODE 4 or 5 when OPDRVs can occur. Required Action E.1 has been modified by a Note stating that LCO 3.0.3 is not applicable.

SURVEILLANCE SR 3.6.4.3.1 REQUIREMENTS Operating each SBGT subsystem ensures that both subsystems are OPERABLE and that all associated controls are functioning properly. It also ensures that blockage or fan or motor failure, can be detected for corrective action. Periodically operation with the heaters on (automatic heater cycling to maintain temperature) for

_>10 continuous hours eliminates moisture on the adsorbers and HEPA filters. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is sufficient to ensure potential moisture build-up does not impact the adsorption and filtering function. The Frequency was also developed in consideration of the known reliability of fan motors and controls and the redundancy available in the system, however these components are not the most-limiting for overall system reliability at this SR Frequency. It is not necessary to run the system for the full 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to demonstrate Operability following maintenance, if that maintenance did not affect the filters and charcoal beds.

SR 3.6.4.3.2 This SR verifies that the required SBGT filter testing is performed in accordance with Specification 5.5.7, Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, system flow capability, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.

(continued)

DAEC B 3.6-94 TSCR-120

SBGT System B 3.6.4.3 BASES SURVEILLANCE SR 3.6.4.3.2 (continued)

REQUIREMENTS A Note has been added to this SR delaying the entry into associated Conditions and Required Actions for up to one hour.

This is necessary because, due to a cross-tie duct between the two SBGT subsystems, the flow path through the SBGT subsystem not being tested must be isolated, making it inoperable, to establish conditions necessary to ensure the tested SBGT subsystem meets the filter train differential pressure requirements of the VFTP. During the testing, the ability to draw a vacuum on Secondary Containment is maintained by the subsystem under test. One hour minimizes the amount of time the SBGT subsystem is inoperable while providing enough time to perform the required testing. Additionally, LCO 3.0.5 provides allowances for post-maintenance testing required to return a SBGT subsystem to Operable status. The allowance provided by the Note avoids potential entry into LCO 3.0.3 (Condition D) during required routine surveillances and during demonstration of Operability for a previously inoperable subsystem under LCO 3.0.5.

SR 3.6.4.3.3 This SR verifies that each SBGT subsystem starts on receipt of an actual or simulated initiation signal. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

While this Surveillance can be performed with the reactor at power, operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," overlaps this SR to provide complete testing of the safety function. Therefore, the Frequency was found to be acceptable from a reliability standpoint.

SR 3.6.4.3.4 This SR verifies that the filter cooler bypass damper can be opened and the fan started. This ensures that the ventilation mode of SBGT System operation is available. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This Surveillance can be performed with the reactor at power and operating experience has shown that these components usually pass the Surveillance when performed at this Frequency. Therefore, the Frequency was found to be acceptable from a reliability standpoint.

(continued)

DAEC B 3.6-95 TSCR-120

RHRSW System B 3.7.1 BASES SURVEILLANCE SR 3.7.1.1 (continued)

REQUIREMENTS This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position. This SR does not apply to manual valves or to valves that cannot be inadvertently misaligned, such as check valves. This SR is considered met for OPERABLE valves that are temporarily placed in a position other than the standby readiness position under appropriate administrative and procedural controls. The administrative and procedural controls (such as positioning during a Surveillance Test Procedure or operating in accordance with an approved Operating Instruction) ensure the Operators are cognizant of valve positions and ensure valves are promptly returned to the standby readiness position when the evolution is completed.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions.

REFERENCES 1. UFSAR, Section 9.2.3.2.

2. UFSAR, Section 6.2.1.3.

3. UFSAR, Chapter 15.

4. UFSAR, Section 15.2.1.

DAEC B 3.7-6 TSCR-120

RWS System and UHS B 3.7.2 BASES ACTIONS B.1 and B.2 (continued)

If the RWS subsystem cannot be restored to OPERABLE status within the associated Completion Time, or both RWS subsystems are inoperable, or the UHS is determined to be inoperable, the unit must be placed in a MODE in which the LCO does not apply.

To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

The Required Actions of Condition B are modified by a Note indicating that the Applicable Condition of LCO 3.4.7 "Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown,"

be entered and Required Actions taken if the inoperable RWS subsystem results in an inoperable RHR Shutdown Cooling subsystem. The Note also alerts the operator that RHR shutdown cooling will be inoperable when the Applicability of LCO 3.4.7 is met. This allows the operator to make provisions for an alternate method of decay heat removal for each inoperable RHR shutdown cooling subsystem, in accordance with the Required Actions of LCO 3.4.7. This is in accordance with LCO 3.0.6 and ensures proper actions are taken for these components.

SURVEILLANCE SR 3.7.2.1 REQUIREMENTS This SR verifies the river water level to be sufficient for the proper operation of the RWS pumps (net positive suction head and pump vortexing are considered in determining this limit). The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience related to trending of the parameter variations during the applicable MODES.

SR 3.7.2.2 Verification of the River Water temperature ensures that the heat removal capability of the RHRSW and ESW Systems are within the assumptions of the DBA analysis. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience related to trending of the parameter variations during the applicable MODES.

(continued)

DAEC B 3.7-10 TSCR-120

RWS System and UHS B 3.7.2 BASES SURVEILLANCE SR 3.7.2.3 REQUIREMENTS (continued) This SR verifies the river depth to provide sufficient flow to meet the plant's emergency cooling requirements. River depth is measured in front of the Intake Structure. This SR is modified by a note which allows this SR not to be performed when river depth is > 2 feet. If river depth falls below 2 feet, this SR is performed periodically until the river depth increases to at least 2 feet. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency will ensure that river bed conditions are monitored until corrective actions, such as dredging, are implemented.

SR 3.7.2.4 Verifying the correct alignment for each power operated and automatic valve in each RWS subsystem flow path provides assurance that the proper flow paths will exist for RWS operation.

This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve is also allowed to be in the nonaccident position, and yet considered in the correct position, provided it can be automatically realigned to its accident position within the required time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position. This SR does not apply to manual valves or to valves that cannot be inadvertently misaligned, such as check valves.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions.

SR 3.7.2.5 This SR verifies the river depth to provide sufficient flow to meet the plant's emergency cooling requirements. River depth is measured in front of the Intake Structure. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience related to trending of river bottom fluctuations.

(continued)

DAEC B 3.7-11 TSCR-120

RWS System and UHS B 3.7.2 BASES (continued)

SURVEILLANCE SR 3.7.2.6 REQUIREMENTS (continued) This SR verifies that the automatic isolation valves of the RWS System will automatically switch to the safety or emergency position to provide cooling water exclusively to the RHRSW/ESW Stilling Basin in the pump house during an accident event. This is demonstrated by the use of an actual or simulated initiation signal.

This SR also verifies the automatic start capability of one of the two RWS pumps in each subsystem.

The Surveillance frequency is controlled under the Surveillance Frequency Control Program. Operating experience has shown that these components usually pass the SR when performed at this Frequency. Therefore, this Frequency is concluded to be acceptable from a reliability standpoint.

REFERENCES 1. UFSAR, Chapter 15.

2. UFSAR, Section 6.2.2.

3. UFSAR, Section 9.2.2.

4. UFSAR, Section 1.8.27.

DAEC B 3.7-12 TSCR-120

ESW System B 3.7.3 BASES SURVEILLANCE SR 3.7.3.1 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions.

SR 3.7.3.2 This SR verifies the automatic start capability of the ESW pump in each subsystem. This is demonstrated by the use of an actual or simulated initiation signal The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Operating experience has shown that these components usually pass the SR when performed at this Frequency. Therefore, this Frequency is concluded to be acceptable from a reliability standpoint.

REFERENCES 1. UFSAR, Section 9.2.3.

2. UFSAR, Chapter 15.

DAEC B 3.7-17 TSCR-120

SFU System B 3.7.4 BASES SURVEILLANCE SR 3.7.4.2 REQUIREMENTS (continued) This SR verifies that the required SFU testing is performed in accordance with the Ventilation Filter Testing Program (VFTP).

The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test Frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.4.3 This SR verifies that on an actual or simulated initiation signal, each SFU subsystem starts and operates. This SR also ensures that the control building isolates. The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.7.1, "Standby Filter Unit Instrumentation," overlaps this SR to provide complete testing of the safety function. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

While this Surveillance can be performed with the reactor at power, operating experience has shown that these components usually pass the Surveillance when performed at this Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

SR 3.7.4.4 This SR verifies the OPERABILITY of the CBE boundary by testing for unfiltered air inleakage past the CBE boundary and into the CBE. The details of the testing are specified in the Control Building Envelope Habitability Program.

The CBE is considered habitable when the radiological dose to CBE occupants calculated in the licensing basis analyses of DBA consequences is no more than 5 rem TEDE and the CBE occupants are protected from hazardous chemicals and smoke.

For DAEC, there is no automatic SFU actuation for hazardous chemical releases or smoke and there are no Surveillance Requirements that verify OPERABILITY in cases of hazardous chemicals or smoke. This SR verifies that the unfiltered air inleakage into the CBE is no greater than the flow rate assumed in the licensing basis analyses of DBA consequences. When unfiltered air inleakage is greater than the assumed flow rate, Condition B must be entered. Required Action B.3 allows time to restore the CBE boundary to OPERABLE status provided mitigating actions can ensure that the CBE remains within the licensing basis habitability limits for the occupants following an accident. Compensatory measures are discussed in Regulatory (continued)

DAEC B 3.7-24B1 TSCR-120

SFU System B 3.7.4 BASES SURVEILLANCE SR 3.7.4.4 (continued)

REQUIREMENTS (continued) Guide 1.196, Section C.2.7.3, (Ref. 4) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref. 5).

These compensatory measures may also be used as mitigating actions as required by Required Action B.2. Temporary analytical methods may also be used as compensatory measures to restore OPERABILITY (Ref. 6). Options for restoring the CBE boundary to OPERABLE status include changing the licensing basis DBA consequence analysis, repairing the CBE boundary, or a combination of these actions. Depending upon the nature of the problem and the corrective action, a full scope inleakage test may not be necessary to establish that the CBE boundary has been restored to OPERABLE status.

REFERENCES 1. UFSAR, Section 6.4.

2. UFSAR, Section 9.4.4.

3. UFSAR, Section 15.2.

4. Regulatory Guide 1.196.

5. NEI 99-03, "Control Room Habitability Assessment," June 2001.

6. Letter from Eric J. Leeds (NRC) to James W. Davis (NEI) dated January 30, 2004, "NEI Draft White Paper, Use of Generic Letter 91-18 Process and Alternative Source Terms in the Context of Control Room Habitability."

(ADAMS Accession No. ML040300694).

7. Letter from Mark A. Peifer (NMC, LLC) to Document Control Desk (USNRC) dated January 28, 2005, "Generic Letter 2003-01: Control Room Habitability - Design Bases, Licensing Bases and Inleakage Testing Results." (ADAMS Accession No. ML050390308).

DAEC B 3.7-24C TSCR-120

CBC System B 3.7.5 BASES ACTIONS E.1, E.2, and E.3 (continued)

During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, if Required Actions B.1 and B.2 cannot be met within the required Completion Times, action must be taken to immediately suspend activities that present a potential for releasing radioactivity that might require isolation of the control building. This places the unit in a condition that minimizes risk.

If applicable, CORE ALTERATIONS and handling of irradiated fuel in the secondary containment must be suspended immediately. Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, actions must be initiated immediately to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until the OPDRVs are suspended.

SURVEILLANCE SR 3.7.5.1 REQUIREMENTS This SR verifies that the heat removal capability of the system is sufficient to remove available control building heat load. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is appropriate since significant degradation of the CBC System is not expected over this time period.

REFERENCES 1. UFSAR, Section 9.4.4.2.

TSCR-120 B 3.7-29 DAEC B 3.7-29 TSCR-1120

Main Condenser Offgas B 3.7.6 BASES (continued)

SURVEILLANCE SR 3.7.6.1 REQUIREMENTS This SR requires a periodic isotopic analysis of an offgas sample to ensure that the required limits are satisfied. The noble gases to be sampled are Xe-1 33, Xe-1 35, Xe-1 38, Kr-85m, Kr-87, and Kr-88. Ifthe measured rate of radioactivity increases significantly (by _>50% after correcting for expected increases due to changes in THERMAL POWER), an isotopic analysis is also performed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the increase is noted, to ensure that the increase is not indicative of a sustained increase in the radioactivity rate. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is adequate in view of other instrumentation that continuously monitor the offgas, and is acceptable, based on operating experience.

This SR is modified by a Note indicating that the SR is not required to be performed until 31 days after any main steam line is not isolated and the SJAE is in operation. Only in this condition can radioactive fission gases be in the Main Condenser Offgas System at significant rates.

REFERENCES 1. UFSAR, Section 11.3.3.

2. 10 CFR 50.67.

3. UFSAR, Section 15.2.1.5.

DAEC B 3.7-32 TSCR-120

Main Turbine Bypass System B 3.7.7 BASES ACTIONS B. 1 (continued)

If the Main Turbine Bypass System cannot be restored to OPERABLE status and the MCPR limits for an inoperable Main Turbine Bypass System are not applied, THERMAL POWER must be reduced to < 21.7% RTP. As discussed in the Applicability section, operation at < 21.7% RTP results in sufficient margin to the required limits, and the Main Turbine Bypass System is not required to protect fuel integrity during the Feedwater Controller Failure Maximum Demand transient. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time is reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.7.1 REQUIREMENTS Cycling each main turbine bypass valve through one complete cycle of full travel demonstrates that the valves are mechanically OPERABLE and will function when required. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on operating experience, is consistent with the procedural controls governing valve operation, and ensures correct valve positions. Operating experience has shown that these components usually pass the SR when performed at this Frequency. Therefore, the Frequency is acceptable from a reliability standpoint. In addition, because this SR makes the RPS and EOC-RPT trips on TSV and TCV closure inoperable when performed above 26% RTP (Ref. SRs 3.3.1.1.16 and 3.3.4.1.4), the Frequency also considers the impact on those functions as well.

SR 3.7.7.2 The Main Turbine Bypass System is required to actuate automatically to perform its design function. This SR demonstrates that, with the required system initiation signals, the valves will actuate to their required position. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant startup and because of the potential for an unplanned transient if the Surveillance were performed with the reactor at power. In addition, as noted above, cycling the valves also impacts the RPS and EOC-RPT trips on TSV and TCV closure. Thus, it is preferable to perform this Surveillance when those trips are not required to be OPERABLE.

(continued)

DAEC R 3.7-35 TSCR-120

Main Turbine Bypass System B 3.7.7 BASES SURVEILLANCE SR 3.7.7.2 (continued)

REQUIREMENTS Operating experience has shown this Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.

SR 3.7.7.3 This SR ensures that the TURBINE BYPASS SYSTEM RESPONSE TIME is in compliance with the assumptions of the appropriate safety analysis. The response time limits are specified in the UFSAR (Ref. 4). The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the reactor at power. In addition, as noted above, cycling the valves also impacts the RPS and EOC-RPT trips on TSV and TCV closure. Thus, it is preferable to perform this Surveillance when those trips are not required to be OPERABLE.

Operating experience has shown this Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.

REFERENCES 1. UFSAR, Section 7.7.2.3.1.

2. UFSAR, Section 15.1.1.1.

3. UFSAR, Section 10.2.2.

4. UFSAR, Section 10.4.4.

DAEC B 3.7-36 TSCR-120

Spent Fuel Storage Pool Water Level B 3.7.8 BASES (continued)

LCO The specified water level preserves the assumptions of the fuel handling accident analysis (Ref. 2). As such, it is the minimum required for fuel movement within the spent fuel storage pool.

APPLICABILITY This LCO applies during movement of irradiated fuel assemblies in the spent fuel storage pool since the potential for a release of fission products exists.

ACTIONS A.1 LCO 3.0.3 is not applicable in MODE 4 or 5. However, since irradiated fuel assembly movement can occur in MODE 1, 2, or 3, required Action A.1 is modified by a Note indicating that LCO 3.0.3 does not apply. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of irradiated fuel assemblies is not a sufficient reason to require a reactor shutdown.

When the initial conditions for an accident cannot be met, action must be taken to preclude the accident from occurring. If the spent fuel storage pool level is less than required, the movement of irradiated fuel assemblies in the spent fuel storage pool is suspended immediately. Suspension of this activity shall not preclude completion of movement of an irradiated fuel assembly to a safe position. This effectively precludes a spent fuel handling accident from occurring.

SURVEILLANCE SR 3.7.8.1 REQUIREMENTS This SR verifies that sufficient water is available in the event of a fuel handling accident. The water level in the spent fuel storage pool must be checked periodically. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is acceptable, based on operating experience, considering that the water volume in the pool is normally stable, and all water level changes are controlled by unit procedures.

(continued)

DAEC B 3.7-38 TSCE-120

CB/SBGT Instrument Air System B 3.7.9 BASES (continued)

SUREVEILLANCE SR 3.7.9.1 REQUIREMENTS Operating each CB/SBGT Instrument Air compressor for Ž 20 minutes allows the oil and other components to reach their operating temperature. This periodic operation removes condensation which may cause rusting in the cylinders, if it were to accumulate. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency and the operating time are based on vendor recommendations.

SR 3.7.9.2 This SR verifies that each CB/SBGT Instrument Air subsystem has the capability to deliver suffcient quantity of compressed air to support the SBGT, SFU, CBC, and containment isolation functions. This SR takes into account both the compressor capacity and the integrity of the distribution system.

This SR also verifies the automatic start capability of the CB/SBGT Instrument Air compressor in each subsystem. This is demonstrated by the use of an actual or simulated initiation signal.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is consistent with the Frequency for pump testing in accordance with the Inservice Testing Program requirements. Therefore, this Frequency was concluded to be acceptable from a reliability standpoint.

REFERENCES 1. UFSAR, Section 9.3.1.2.1.

2. UFSAR, Section 6.2.4.

3. UFSAR, Section 6.2.5.

4. UFSAR, Section 6.5.3.3.

5. UFSAR, Section 6.4.2.

6. UFSAR, Section 9.4.4.

DAEC R 3.7-44 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.1 REQUIREMENTS (continued) This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and availability of offsite AC electrical power. The breaker alignment verifies that at least the minimum required offsite power supply breakers are in their correct position to ensure that distribution buses and loads are connected to either the preferred power source or the alternate preferred power source and that appropriate independence of offsite circuits is maintained. This can be accomplished by verifying that an essential bus is energized, and that the status of offsite supply breakers that are displayed in the control room are correct. The status of manual disconnects is verified administratively. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is adequate since breaker position is not likely to change without the operator being aware of it and because its status is displayed in the control room.

SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the standby electrical power supply to mitigate DBAs and transients and maintain the unit in a safe shutdown condition.

To minimize the wear on moving parts that do not get lubricated when the engine is not running, these SRs have been modified by a Note (Note 2 for SR 3.8.1.2 and Note 1 for SR 3.8.1.7) to indicate that all DG starts for these Surveillances may be preceded by an engine prelube period and (for SR 3.8.1.2 only) followed by a warmup prior to loading. Note 3 to SR 3.8.1.2 allows delaying the entry into associated Conditions and Required Actions for up to two hours during the performance of the conditional surveillance required by Required Actions B.3 or B.4.

This Note is necessary because to perform a slow start and warmup of the DG requires reducing the governor control setting to minimum and securing the generator field excitation. The governor control setting is gradually increased to bring the DG to synchronous speed and to allow for warmup. Once the DG is at synchronous speed, the generator field excitation is enabled and the DG is again capable of supplying the essential bus. During this warmup portion of the surveillance test, the DG is incapable of supplying the essential bus and is considered inoperable.

(continued)

DAEC B 3.8-15 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7 (continued)

REQUIREMENTS After completion of the SR, the fuel racks to the DG are disabled to allow purging of any residual fuel oil from the cylinders. This also renders the DG inoperable. The two hours allowed by the Note minimizes the amount of time a DG is inoperable while providing enough time to perform the required Conditional Surveillance and avoids entering the shutdown actions of Condition E or F unnecessarily.

For the purposes of this testing, the DGs are manually started from standby conditions. Standby conditions for a DG mean that the diesel engine coolant and oil are being continuously circulated and temperature is being maintained consistent with manufacturer recommendations.

In order to reduce stress and wear on diesel engines during testing, the manufacturer of the DGs installed at the DAEC recommends a modified start in which the starting speed of the DG is limited, warmup is limited to this lower speed, and the DGs are gradually accelerated to synchronous speed prior to loading.

These start procedures are the intent of Note 2 (SR 3.8.1.2).

SR 3.8.1.7 requires that DG starts from standby conditions and achieves required voltage and frequency (i.e. - voltage >_3744 V and frequency >_59.5 Hz) within 10 seconds; and achieves steady state voltage > 3744 V and _<4576 V and frequency _>59.5 Hz and

_<60.5 Hz. The 10 second start requirement supports the assumptions in the design basis LOCA analysis of UFSAR, Section 15.2.1 (Ref. 12). The 10 second start requirement is not applicable to SR 3.8.1.2 (see Note 3 of SR 3.8.1.2), when a modified start procedure as described above is used. If a modified start is not used, the 10 second start requirement of SR 3.8.1.7 applies. In addition to the SR requirements, the time for the DG to reach steady state operation, unless the modified DG start method is employed, is periodically monitored and the trend evaluated to identify degradation of governor and voltage regulator performance.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The normal Frequency for SR 3.8.1.2 is consistent with Safety Guide 9. The Frequency for SR 3.8.1.7 is a reduction in cold testing consistent with Generic Letter 84-15 (Ref. 7). These Frequencies provide adequate assurance of DG OPERABILITY, while minimizing degradation resulting from testing.

(continued)

DAEC B 3.8-16 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.3 REQUIREMENTS (continued) This Surveillance verifies that the DGs are capable of synchronizing and can be manually loaded to > 2750 kW and

< 2950 kW, providing a 200 kW range centered on the continuous duty rating of the DGs of 2850 kW. This range ensures that the DGs are tested at a load above the maximum expected accident load. A minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the DG is connected to the offsite source.

Although no power factor requirements are established by this SR, the DG is normally operated at a power factor greater than 0.9 lagging. While a value of 0.8 is the design rating of the machine, the machine is operated at power factors greater than 0.9 for normal operations and greater than 0.8 for surveillance testing. The load limit is provided to avoid routine overloading of the DG. Routine overloading may result in more frequent teardown inspections in accordance with vendor recommendations in order to maintain DG OPERABILITY.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The normal Frequency for this Surveillance is consistent with Safety Guide 9.

Note 1 modifies this Surveillance to indicate that diesel engine runs for this Surveillance may include gradual loading, as recommended by the manufacturer, so that mechanical stress and wear on the diesel engine are minimized. Note 2 modifies this Surveillance by stating that momentary transients because of changing bus loads do not invalidate this test. Similarly, momentary power factor transients above the limit do not invalidate the test.

Note 3 indicates that this Surveillance should be conducted on only one DG at a time in order to avoid common cause failures that might result from offsite circuit or grid perturbations.

Note 4 stipulates a prerequisite requirement for performance of this SR. A successful DG start must precede this test to credit satisfactory performance.

(continued)

DAEC B 3.8-17 TSCR-1 20

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.4 REQUIREMENTS (continued) This SR provides verification that the level of fuel oil in the day tank is at or above the level at which the day tank low level alarm is annunciated. This low level alarm should only be received if the automatic fuel oil transfer instrumentation is not functioning properly. The level is expressed as an equivalent volume in gallons, and is selected to ensure adequate fuel oil for a minimum of approximately one hour of DG operation at full load, considering a conservative fuel consumption rate. Verification that at least a one hour supply of fuel oil exists in a day tank provides assurance that a DG can operate continuously, and also allows the operating crew sufficient time to take corrective action should the automatic fuel oil transfer system not function properly.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and facility operators would be aware of any large uses of fuel oil during this period.

SR 3.8.1.5 Microbiological fouling is a major cause of fuel oil degradation.

There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive.

Testing for water content and removal of water from the fuel oil day tanks as necessary, eliminates the necessary environment for bacterial survival. This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during DG operation. Water may come from any of several sources, including condensation, ground water, rain water, contaminated fuel oil, and breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water, as necessary, minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Surveillance Frequencies meet the intent of Regulatory Guide 1.137 (Ref. 10). This SR is for preventive maintenance. The presence of water does not necessarily represent a failure of this SR provided that accumulated water is removed during performance of this Surveillance.

(continued)

DAEC B 3.8-18 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.6 REQUIREMENTS (continued) This Surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This Surveillance provides assurance that the fuel oil transfer pump is OPERABLE, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for manual fuel transfer systems are OPERABLE. Additional assurance of fuel oil transfer pump OPERABILITY is provided by meeting the testing requirements for pumps that are contained in the ASME Boiler and Pressure Vessel Code,Section XI (Ref. 13).

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.1.7 See SR 3.8.1.2.

SR 3.8.1.8 The slow transfer of each 4.16 kV essential bus power supply from the preferred offsite circuit (i.e. - the startup transformer) to the alternate preferred offsite circuit (i.e. the standby transformer) demonstrates the OPERABILITY of the alternate preferred circuit distribution network to power the shutdown loads. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of the Surveillance is based on engineering judgment taking into consideration the plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths.

Operating experience has shown that these components usually pass the SR when performed on this Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note. The reason for the Note is that, during operation with the reactor critical, performance of this SR could cause perturbations to the Electrical Distribution Systems that could challenge continued steady state operation and, as a result, plant safety systems. Credit may be taken for unplanned events that satisfy this SR.

(continued)

DAEC B 3.8-19 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.9 REQUIREMENTS (continued) Each DG is provided with an engine overspeed trip to prevent damage to the engine. Recovery from the transient caused by the loss of a large load could cause diesel engine overspeed, which, if excessive, might result in a trip of the engine. This Surveillance demonstrates the DG load response characteristics and the capability to reject the largest single load and return to the required voltage and frequency (i.e. - voltage > 3744 V and

4576 V and frequency > 59.5 Hz and < 60.5 Hz) within predetermined periods of time (i.e., 1.3 seconds for voltage and 3.9 seconds for frequency) while maintaining an acceptable margin to the overspeed trip. The largest single load for each DG is a core spray pump motor (700 hp). This Surveillance may be accomplished by tripping its associated single largest post-accident load with the DG solely supplying the bus.

As specified by IEEE-308 (Ref. 14), the load rejection test is acceptable if the increase in diesel speed does not exceed 75% of the difference between synchronous speed and the overspeed trip setpoint, or 15% above synchronous speed, whichever is lower.

For both DGs, this represents 64.5 Hz, equivalent to 75% of the difference between nominal speed and the overspeed trip setpoint.

The time, voltage, and frequency tolerances specified in the Bases for this SR are derived from UFSAR Table 8.3-1 (Ref. 16) recommendations for response during load sequence intervals.

The voltage and frequency are consistent with the design range of the equipment powered by the DG. SR 3.8.1.9.a corresponds to the frequency excursion, while SR 3.8.1.9.b and SR 3.8.1.9.c are the steady state voltage and frequency to which the system must recover following load rejection within a predetermined time period. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is consistent with the recommendation of Regulatory Guide 1.108 (Ref. 9).

This SR is modified by a Note. The reason for the Note is that, during operation with the reactor critical, performance of this SR could cause perturbations to the Electrical Distribution Systems that could challenge continued steady state operation and, as a result, plant safety systems. Credit may be taken for unplanned events that satisfy this SR.

(continued)

DAEC B 3.8-20 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.10 REQUIREMENTS (continued) This Surveillance demonstrates that DG non-critical protective functions (e.g., high jacket water temperature and low lubricating oil pressure) are bypassed on either an ECCS initiation test signal or a LOOP test signal and critical protective functions (engine overspeed and generator differential current) trip the DG to avert substantial damage to the DG unit. The non-critical trips are bypassed during DBAs and LOOPs and provide an alarm on an abnormal engine condition. This alarm provides the operator with sufficient time to react appropriately. The DG availability to mitigate the DBA is more critical than protecting the engine against minor problems that are not immediately detrimental to emergency operation of the DG.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment, takes into consideration plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths. Operating experience has shown that these components usually pass the SR when performed at this Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would remove a required DG from service. Credit may be taken for unplanned events that satisfy this SR.

SR 3.8.1.11 As specified by Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(6), this Surveillance ensures that the manual synchronization and load transfer from the DG to the offsite source can be made and that the DG can be returned to ready-to-load status when offsite power is restored. The DG is considered to be in ready-to-load status when the DG is at rated speed and voltage, the output breaker is open and can receive an auto-close signal on bus undervoltage, and the individual pump timers are reset.

(continued)

DAEC B 3.8-21 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.11 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9),

paragraph 2.a.(6), and takes into consideration plant conditions required to perform the Surveillance.

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would remove a required offsite circuit from service, perturb the electrical distribution system, and challenge safety systems. Credit may be taken for unplanned events that satisfy this SR.

SR 3.8.1.12 Under either LOCA conditions or during a loss of offsite power, loads are sequentially connected to the bus by a timed logic sequence using individual time delay relays. The sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading of the DGs due to high motor starting currents. Verifying the load sequence time interval is greater than or equal to 2 seconds ensures that sufficient time exists for the DG to restore frequency and voltage prior to applying the next load. The Allowable Values for the Core Spray and Low Pressure Coolant Injection Pump Start - Time Delay Relays, Table 3.3.5.1-1, Functions 1.e and 2.e, ensure this time interval is maintained as well as ensuring that safety analysis assumptions regarding ESF equipment time delays are not violated. Allowances for instrument inaccuracies in the load sequence time interval are also accounted for by the Pump Start -

Time Delay Relay Allowable Value.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9),

paragraph 2.a.(2); takes into consideration plant conditions required to perform the Surveillance; and is intended to be consistent with expected fuel cycle lengths.

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would remove a required offsite circuit from service, perturb the electrical distribution system, and challenge safety systems. Credit may be taken for unplanned events that satisfy this SR.

(continued)

DAEC B 3.8-22 TSCR-120

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.13 (continued)

REQUIREMENTS loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For instance, ECCS injection valves are not desired to be stroked open, or systems are not capable of being operated at full flow. In lieu of actual demonstration of connection and loading of these loads, testing that adequately shows the capability of the DG system to perform these functions is acceptable. This testing may include any series of sequential, overlapping, or total steps so that proper operation with each of the various signals present is verified.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into consideration plant conditions required to perform the Surveillance and is intended to be consistent with an expected fuel cycle length. Operating experience has shown that these components usually pass the SR when performed at this Frequency.

Therefore, the Frequency is acceptable from a reliability standpoint.

This SR is modified by two Notes. The reason for Note 1 is to minimize wear and tear on the DGs during testing. For the purpose of this testing, the DGs must be started from standby conditions, that is, with the engine coolant and oil being continuously circulated and temperature maintained consistent with manufacturer recommendations. The reason for Note 2 is that performing the Surveillance would remove the required offsite circuit from service, perturb the Electrical Distribution System, and challenge safety systems. Credit may be taken for unplanned events that satisfy this SR.

REFERENCES 1. UFSAR, Section 3.1.2.2.8.

2. UFSAR, Section 8.2.1.3 and Section 8.3.1.1.5

3. UFSAR, Section 1.8.9.

4. FPL letter, L-2006-073, dated April 3, 2006, Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power.

5. UFSAR, Chapter 15.

(continued)

DAEC B 3.8-24 TSCR-120

Diesel Fuel Oil, Lube Oil, and Starting Air B 3.8.3 BASES ACTIONS F.1 (continued)

With a Required Action and associated Completion Time not met, or the stored diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than addressed by Conditions A through E, the associated DG may be incapable of performing its intended function and must be immediately declared inoperable.

SURVEILLANCE SR 3.8.3.1 REQUIREMENTS This SR provides verification that there is an adequate inventory of fuel oil in the storage tank to support a single DG's operation for 7 days at full load. The 7 day period is sufficient time to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and unit operators would be aware of any large uses of fuel oil during this period.

SR 3.8.3.2 This Surveillance ensures that sufficient lubricating oil inventory is available to support at least 7 days of full load operation for each DG. The 257 gallon requirement for each DG is based on the DG manufacturer's consumption values for the run time of the DG.

Implicit in this SR is the requirement to verify the capability to transfer the lube oil from the lube oil makeup tank to the DG. The requirement is considered -to be fulfilled by observing that the DG lube oil sump level is maintained in the normal band by the lube oil sump level controller.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. A Frequency is adequate to ensure that a sufficient lube oil supply is onsite, since DG starts and run time are closely monitored by the plant staff.

(continued)

DAEC B 3.8-37 TSCR-120

Diesel Fuel Oil, Lube Oil, and Starting Air B 3.8.3 BASES SURVEILLANCE SR 3.8.3.3 (continued)

REQUIREMENTS effect on DG operation. This Surveillance ensures the availability of high quality fuel oil for the DGs.

Fuel oil degradation during long term storage shows up as an increase in particulate, mostly due to oxidation. The presence of particulate does not mean that the fuel oil will not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel oil injection equipment, however, which can cause engine failure.

Particulate concentrations should be determined in accordance with ASTM D2276-89 (Ref. 6), Method A2 or A3. These methods involve a gravimetric determination of total particulate concentration in the fuel oil and have a limit of 10 mg/I. It is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing.

The Frequency of this test takes into consideration fuel oil degradation trends that indicate that particulate concentration is unlikely to change significantly between Frequency intervals.

SR 3.8.3.4 This Surveillance ensures that, without the aid of any refill compressor, sufficient air start capacity for each DG is available.

The system design requirements provide for a minimum of five engine start cycles per air receiver without recharging. The pressure specified in this SR is intended to reflect a conservative value for which the five starts can be accomplished, assuming only one air start receiver is pressurized.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into account the capacity, capability, redundancy, and diversity of the AC sources and the Air Start System for each DG.

(continued)

DAEC B 3.8-39 TSCR-1 20

Diesel Fuel Oil, Lube Oil, and Starting Air B 3.8.3 BASES SURVEILLANCE SR 3.8.3.5 REQUIREMENTS (continued) Microbiological fouling is a major cause of fuel oil degradation.

There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive.

Checking for the presence of water, and removing water, as necessary, eliminates the necessary environment for bacterial survival. This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during DG operation. Water may come from any of several sources, including condensation, ground water, rain water, contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Surveillance Frequencies are consistent with those recommended and established by Regulatory Guide 1.137 (Ref. 2). This SR is for preventive maintenance. The presence of water does not necessarily represent failure of this SR, provided the water is removed during performance of the Surveillance.

REFERENCES 1. UFSAR, Section 9.5.4.

2. Regulatory Guide 1.137.

3. ANSI N195, 1976.

4. [Deleted]

5. UFSAR, Chapter 15.

6. ASTM Standards: D975-77, D1298-85 and D2276-89.

7. UFSAR, Section 8.3.1.

DAEC B 3.8-40 TSCR-120

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.1 (continued)

REQUIREMENTS the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery margin calculations (Ref. 4). The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is consistent with manufacturer recommendations and with the intent of IEEE-450 (Ref. 7).

SR 3.8.4.2 Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each inter-cell, inter-rack, inter-tier, and terminal connection, provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The connection resistance limits established for this SR must be no more than 20% above the resistance as measured during installation or not above the ceiling value established by the manufacturer. The resulting limits are 5.0 E-5 ohms for inter-cell connections and 1.4 E-4 ohms for inter-rack connections, inter-tier connections and terminal connections. The Frequency for these inspections, which can detect conditions that can cause power losses due to resistance heating, is controlled under the Surveillance Frequency Control Program. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends.

SR 3.8.4.3 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The presence of physical damage or deterioration does not necessarily represent a failure of this SR, provided an evaluation determines that the physical damage or deterioration does not affect the OPERABILITY of the battery (its ability to perform its design function).

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency for this SR is consistent with the intent of IEEE-450 (Ref. 7), which recommends detailed visual (continued)

DAEC B 3.8-47 TSCR-120

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.3 (continued)

REQUIREMENTS inspection of cell condition and rack integrity.

SR 3.8.4.4 and SR 3.8.4.5 Visual inspection and resistance measurements of inter-cell, inter-rack, inter-tier, and terminal connections provide an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anti-corrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and inspection under each terminal connection.

The removal of visible corrosion is a preventive maintenance SR.

The presence of visible corrosion does not necessarily represent a failure of this SR, provided visible corrosion is removed during performance of this Surveillance. The connection resistance limits for this SR must be no more than 20% above the resistance as measured during installation, or not above the ceiling value established by the manufacturer. The resulting limits are 5.0 E-5 ohms for inter-cell connections and 1.4 E-4 ohms for inter-rack connections, inter-tier connections and terminal connections.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency of these SRs is consistent with the intent of IEEE-450 (Ref. 7), which recommends detailed visual inspection of cell condition and inspection of cell to cell and terminal connection resistance.

SR 3.8.4.6 Battery charger capability requirements are based on the design capacity of the chargers (Ref. 3). According to the recommendations of Regulatory Guide 1.32 (Ref. 8), the battery charger supply is required to be based on the largest combined demands of the various steady state loads and the charging capacity to restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the unit during these demand occurences. The minimum required amperes ensures that these requirements can be satisfied.

(continued)

DAEC B 3.8-48 TSCR-120

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.6 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is acceptable, given the unit conditions required to perform the test and the other administrative controls existing to ensure adequate charger performance during these intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.

This SR is modified by a Note. The reason for the Note is that performing the Surveillance on a required battery charger would remove a required DC electrical power subsystem from service, perturb the electrical distribution system, and challenge safety systems. This Note does not preclude performance of this SR on the "spare" battery charger (i.e., a charger not in-service or "required"). This Note also acknowledges that credit may be taken for unplanned events that satisfy the Surveillance.

SR 3.8.4.7 A battery service test is a special test of the battery's capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length corresponds to the design duty cycle requirements as specified in Reference 4. The voltage of each cell shall be determined after the discharge. Following discharge, battery cell parameters must be restored in accordance with LCO 3.8.6. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is consistent with the maximum length of an operating cycle.

This SR is modified by two Notes. Note 1 allows the performance of a performance discharge test in lieu of a service test.

The modified performance discharge test is a simulated duty cycle consisting of just two rates; the one minute rate published for the battery or the largest current load of the duty cycle, followed by the test rate employed for the performance test, both of which envelope the duty cycle of the service test. Since the ampere-hours removed by a rated one minute discharge represents a very small portion of the battery capacity, the test rate can be changed to that for the performance test without compromising the results of the performance discharge test. The battery terminal voltage (continued)

DAEC B 3.8-49 TSCR-1 20

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.8 (continued)

REQUIREMENTS this test is normally controlled under the Surveillance Frequency Control Program. However, if the battery shows degradation, or if the battery has reached 85% of its expected life and capacity is

< 100% of the manufacturer's rating, the Surveillance Frequency is reduced to 12 months. However, if the battery shows no degradation but has reached 85% of its expected life, the Surveillance Frequency is only reduced to 24 months for batteries that retain capacity > 100% of the manufacturer's rating.

Degradation is indicated, according to IEEE-450 (Ref. 7), when the battery capacity drops by more than 10% relative to its capacity on the previous performance test or when it is 10% below the manufacturer's rating. All these Frequencies are consistent with the recommendations in IEEE-450 (Ref. 7).

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would remove a required DC electrical power subsystem from service, perturb the Electrical Distribution System, and challenge safety systems. Credit may be taken for unplanned events that satisfy the Surveillance.

Following discharge, battery cell parameters must be restored in accordance with LCO 3.8.6.

REFERENCES

1. UFSAR, Section 3.1.2.2.8.

2. UFSAR, Section 1.8.6.

3. IEEE Standard 308, 1971.

4. Calculations: CAL-E92-09, CAL-E92-08 and CAL-E92-07, latest approved revisions.

5. UFSAR, Chapter 15.

6. Regulatory Guide 1.93.

7. IEEE Standard 450, 1980.

8. Regulatory Guide 1.32, February 1977.

9. IEEE Standard 485, 1983.

10. UFSAR, Section 8.3.2 DAEC B 3.8-51 TSCR-120

Battery Cell Parameters B 3.8.6 BASES SURVEILLANCE SR 3.8.6.1 (continued)

REQUIREMENTS The SR should only be performed when the battery is on a float charge to allow obtaining meaningful, consistent, trendable readings. If the battery is on equalize charge or has been on equalize charge anytime during the previous 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the SR is due, performance of the SR should be delayed until the battery has been off equalize charge for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , utilizing the allowance of SR 3.0.2. If it is expected that a battery will need to be on equalize charge when the SR is due and past the extension time allowed by SR 3.0.2, the SR should be performed early before the battery is placed on equalize charge. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.6.2 The periodic inspection of specific gravity and voltage is consistent with IEEE-450 (Ref. 3). The actual Surveillance Frequency is controlled under the Surveillance Frequency Control Program. In addition, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of a battery discharge

<110 V for 125 V and <220 V for 250 V or a battery overcharge

> 150 V for 125 V and > 300 V for 250 V, the battery must be demonstrated to meet Category B limits. Transients, such as motor starting transients, which may momentarily cause battery voltage to drop to _<110 V for 125 V and

220 V for 250 V, do not constitute a battery discharge provided the battery terminal voltage and float current return to pre-transient values. This inspection is also consistent with IEEE-450 (Ref. 3), which recommends special inspections following a severe discharge or overcharge, to ensure that no significant degradation of the battery occurs as a consequence of such discharge or overcharge.

SR 3.8.6.3 This Surveillance that verifies the average temperature of representative cells is within limits is consistent with a recommendation of IEEE-450 (Ref. 3) that states that the temperature of electrolytes in representative cells should be determined on a routine basis. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Lower than normal temperatures act to inhibit or reduce battery capacity. This SR ensures that the operating temperatures remain within an acceptable operating range. This limit is based on manufacturer's recommendations.

(continued)

DAEC B 3.8-59 TSCR-120

Distribution Systems - Operating B 3.8.7 BASES ACTIONS F.1 (continued)

With the 125 VDC RCIC MCC inoperable, the equipment powered from the inoperable MCC are not capable of performing their intended functions. Immediately declaring the RCIC System and the outboard RCIC steam line isolation valve (MO-2401) inoperable allows the Actions of the associated LCOs (LCO 3.5.3, "RCIC System", and 3.6.1.3, "Primary Containment Isolation Valves") to apply appropriate limitations on continued reactor operation.

G.1 Condition G corresponds to a level of degradation in the electrical distribution system that causes a required safety function to be lost. When more than one AC or DC electrical power distribution subsystem is lost, and this results in the loss of a required function (except as allowed by Condition D), the plant is in a condition outside the accident analysis. Therefore, no additional time is justified for continued operation. LCO 3.0.3 must be entered immediately to commence a controlled shutdown.

SURVEILLANCE SR 3.8.7.1 REQUIREMENTS This Surveillance verifies that the AC and DC electrical power distribution systems are functioning properly, with the correct circuit breaker alignment. The correct breaker alignment ensures the appropriate separation and independence of the electrical buses are maintained, and power is available to each required bus. The verification of energization of the buses ensures that the required power is readily available for motive as well as control functions for critical system loads connected to these buses. This may be performed by verifying the absence of low voltage alarms, or by verifying a load powered from the bus is operating. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into account the redundant capability of the AC and DC electrical power distribution subsystems, and other indications available in the control room that alert the operator to subsystem malfunctions.

(continued)

DAEC B 3.8-71 TSCR-1 20

Distribution Systems - Operating B 3.8.7 BASES SURVEILLANCE SR 3.8.7.2 REQUIREMENTS (continued) This Surveillance verifies the "break-before-make" coordination of the circuit breakers for the LPCI Swing Bus (1 B34A and 1 B44A).

This SR, when coupled with SR 3.5.1.7, demonstrates the ability of the LPCI Swing Bus to perform its intended safety function in support of the LPCI Loop Select design without compromising the independence of the AC Electrical Power Distribution System (Reference 2). Consequently, failure to satisfy this SR requires that both 1 B34 and 1 B44 buses be declared inoperable, and Condition G be entered until either 1 B34 or 1 B44 can be isolated from the Swing Bus, as a loss of all low pressure ECCS has potentially occurred. If the Swing Bus can be isolated from 1B34 or 1 B44, then this SR is met, and the AC electrical power distribution subsystems are not inoperable. However, this will result in a failure to meet SR 3.5.1.7 (and Condition B of LCO 3.5.1 will be required to be entered since the LPCI system will be inoperable).

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. UFSAR, Chapter 15.

2. J. Hall (NRC) to L. Liu (IELP), "LPCI Swing Bus Design Modification (TAC No. 69556)," dated January 19, 1989 DAEC B 3.8-72 TSCR-120

Distribution Systems - Shutdown B 3.8.8 BASES (continued)

SURVEILLANCE SR 3.8.8.1 REQUIREMENTS This Surveillance verifies that the AC and DC electrical power distribution subsystems are functioning properly, with the correct circuit breaker alignment. The correct circuit breaker alignment ensures power is available to each required bus. The verification of energization of the buses ensures that the required power is readily available for motive as well as control functions for critical system loads connected to these buses. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into account the redundant capability of the electrical power distribution subsystems, as well as other indications available in the control room that alert the operator to subsystem malfunctions.

REFERENCES 1. UFSAR, Chapter 15.

DAEC B 3.8-78 TSCR-120

Refueling Equipment Interlocks B 3.9.1 BASES (continued)

SURVEILLANCE SR 3.9.1.1 REQUIREMENTS Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay.

This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment and is considered adequate in view of other indications of refueling interlocks and their associated input status that are available to unit operations personnel.

REFERENCES 1. UFSAR, Section 3.1.2.3.7.

2. UFSAR, Section 7.6.2.

3. UFSAR, Section 15.1.4.3.

4. UFSAR, Section 15.1.4.4.

DAEC B 3.9-4 TSCR-120

Refuel Position One-Rod-Out Interlock B 3.9.2 BASES (continued)

ACTIONS A.1 and A.2 With one or both channels of the refueling position one-rod-out interlock inoperable, the refueling interlocks may not be capable of preventing more than one control rod from being withdrawn. This condition may lead to criticality.

Control rod withdrawal must be Immediately suspended, and action must be Immediately initiated to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Action must continue until all such control rods are fully inserted.

Control rods in core cells containing no fuel assemblies do not affect the reactivity of the core and, therefore, do not have to be inserted.

SURVEILLANCE SR 3.9.2.1 REQUIREMENTS Proper functioning of the refueling position one-rod-out interlock requires the reactor mode switch to be in Refuel. During control rod withdrawal in MODE 5, improper positioning of the reactor mode switch could, in some instances, allow improper bypassing of required interlocks. Therefore, this Surveillance imposes an additional level of assurance that the refueling position one-rod-out interlock will be OPERABLE when required. By "locking" the reactor mode switch in the proper position (i.e.,

removing the reactor mode switch key from the switch while the reactor mode switch is positioned in Refuel), an additional administrative control is in place to preclude operator errors from resulting in unanalyzed operation.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is sufficient in view of other administrative controls utilized during refueling operations to ensure safe operation.

(continued)

DAEC B 3.9-7 TSCR-1 20

Refuel Position One-Rod-Out Interlock B 3.9.2 BASES SURVEILLANCE SR 3.9.2.2 REQUIREMENTS (continued) Performance of a CHANNEL FUNCTIONAL TEST on each channel demonstrates the associated refuel position one-rod-out interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is considered adequate because of demonstrated circuit reliability, procedural controls on control rod withdrawals, and visual and audible indications available in the control room to alert the operator to control rods not fully inserted. To perform the required testing, the applicable condition must be entered (i.e., a control rod must be withdrawn from its full-in position). Therefore, SR 3.9.2.2 has been modified by a Note that states the CHANNEL FUNCTIONAL TEST is not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

REFERENCES 1. UFSAR, Section 3.1.2.3.7.

2. UFSAR, Section 7.6.2.

3. UFSAR, Section 15.1.4.3.

DAEC B 3.9-8 TSCR-120

Control Rod Position B 3.9.3 BASES (continued)

LCO All control rods must be fully inserted during applicable refueling conditions to minimize the probability of an inadvertent criticality during refueling.

APPLICABILITY During MODE 5, loading fuel into core cells with control rods withdrawn may result in inadvertent criticality. Therefore, the control rods must be inserted before loading fuel into a core cell.

All control rods must be inserted before loading fuel to ensure that a fuel loading error does not result in loading fuel into a core cell with the control rod withdrawn.

In MODES 1, 2, 3, and 4, the reactor pressure vessel head is on, and no fuel loading activities are possible. Therefore, this Specification is not applicable in these MODES.

ACTIONS A.1 With all control rods not fully inserted during the applicable conditions, an inadvertent criticality could occur that is not analyzed in the UFSAR. All fuel loading operations must be Immediately suspended. Suspension of these activities shall not preclude completion of movement of a component to a safe position.

SURVEILLANCE SR 3.9.3.1 REQUIREMENTS During refueling, to ensure that the reactor remains subcritical, all control rods must be fully inserted prior to and during fuel loading.

Periodic checks of the control rod position ensure this condition is maintained. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into consideration the procedural controls on control rod movement during refueling as well as the redundant functions of the refueling interlocks.

(continued)

DAEC B 3.9-10 TSCR-1 20

Control Rod OPERABILITY - Refueling B 3.9.5 BASES SURVEILLANCE SR 3.9.5.1 and SR 3.9.5.2 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into consideration equipment reliability, procedural controls over the scram accumulators, and control room alarms and indicating lights that indicate low accumulator charge pressures.

SR 3.9.5.1 is modified by a Note that allows 7 days after withdrawal of the control rod to perform the Surveillance. This acknowledges that the control rod must first be withdrawn before performance of the Surveillance, and therefore avoids potential conflicts with SR 3.0.3 and SR 3.0.4.

REFERENCES 1. UFSAR, Section 3.1.2.3.7.

2. UFSAR, Section 15.1.4.3.

3. UFSAR, Section 15.1.4.4.1.

DAEC B 3.9-18 TSCR-120

RPV Water Level B 3.9.6 BASES SURVEILLANCE SR 3.9.6.1 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is based on engineering judgment and is considered adequate in view of the large volume of water and the normal procedural controls on valve positions, which make significant unplanned level changes unlikely.

REFERENCES 1. UFSAR, Section 15.2.5.

2. Regulatory Guide 1.183.

DAEC B 3.9-21 TSCR-120

RHR - High Water Level B 3.9.7 BASES ACTIONS C.1 and C.2 (continued)

If no RHR shutdown cooling is in operation when reactor coolant temperature is > 150'F, except as permitted by the LCO Note, an alternate method of coolant circulation is required to be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . However, with the water level high, coolant circulation is assured by virtue of being flooded up to a level significantly higher than the minimum natural circulation level (i.e., lowest turnaround point for water in the steam separator) and thus, Required Action C.1 is met.

During the period of time when the reactor coolant is either being naturally circulated or circulated by another alternate method, the reactor coolant temperature must be periodically monitored to ensure proper circulation is maintained. The once per hour Completion Time is deemed appropriate due to the passive nature of the circulation process.

SURVEILLANCE SR 3.9.7.1 REQUIREMENTS This Surveillance demonstrates that the RHR subsystem is in operation and circulating reactor coolant when reactor coolant temperature is > 150'F.

The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability corresponding to the decay heat load that is present. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is sufficient in view of other visual and audible indications available to the operator for monitoring the RHR subsystem in the control room.

REFERENCES 1. UFSAR, Section 3.1.2.4.5.

2. UFSAR, Section 5.4.7.2.2.

DAEC B 3.9-26 TSCR-120

RHR - Low Water Level B 3.9.8 BASES (continued)

SURVEILLANCE SR 3.9.8.1 REQUIREMENTS This Surveillance demonstrates that one RHR shutdown cooling subsystem is in operation and circulating reactor coolant. The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability corresponding to the decay heat load that is present.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is sufficient in view of other visual and audible indications available to the operator for monitoring the RHR subsystems in the control room.

REFERENCES 1. UFSAR, Section 3.1.2.4.5.

2. UFSAR, Section 5.4.7.2.2.

DAEC B 3.9-31 TSCR-120

Reactor Mode Switch Interlock Testing B 3.10.2 BASES (continued)

SURVEILLANCE SR 3.10.2.1 and SR 3.10.2.2 REQUIREMENTS Meeting the requirements of this Special Operations LCO maintains operation consistent with or conservative to operating with the reactor mode switch in the Shutdown position (or the Refuel position for MODE 5). The functions of the reactor mode switch interlocks that are not in effect, due to the testing in progress, are adequately compensated for by the Special Operations LCO requirements. The administrative controls are to be periodically verified to ensure that the operational requirements continue to be met. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Surveillances are intended to provide appropriate assurance that each operating shift is aware of and verifies compliance with these Special Operations LCO requirements.

REFERENCES 1. UFSAR, Section 7.2.1.1.6.

2. UFSAR, Section 15.1.4.3.

3. UFSAR, Section 15.1.4.4.1.

DAEC B 3.10-10 TSCR-120

Single Control Rod Withdrawal-Hot Shutdown B 3.10.3 BASES SURVEILLANCE SR 3.10.3.1, SR 3.10.3.2, and SR 3.10.3.3 (continued)

REQUIREMENTS It is preferred to electrically disarm the control rods since, in this case, drive water cools and minimizes crud accumulation in the drive. SR 3.10.3.2 has been modified by a Note, which clarifies that this SR is not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements, since SR 3.10.3.2 demonstrates that the alternative LCO 3.10.3.d.2 requirements are satisfied.

Also, SR 3.10.3.3 verifies that all control rods other than the control rod being withdrawn are fully inserted. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is acceptable because of the administrative controls on control rod withdrawal, the protection afforded by the LCOs involved, and hard-wired interlocks that preclude additional control rod withdrawals.

REFERENCES 1. UFSAR, Section 15.1.4.3.

DAEC B 3.10-15 TSC R-120

Single Control Rod Withdrawal- Cold Shutdown B 3.10.4 BASES (continued)

SURVEILLANCE SR 3.10.4.1, SR 3.10.4.2, SR 3.10.4.3, and SR 3.10.4.4 REQUIREMENTS The other LCOs made applicable by this Special Operations LCO are required to have their associated surveillances met to establish that this Special Operations LCO is being met. If the local array of control rods is inserted and disarmed while the scram function for the withdrawn rod is not available, periodic verification is required to ensure that the possibility of criticality remains precluded. The control rods can be hydraulically disarmed by closing the drive water and exhaust water isolation valves. Electrically, the control rods can be disarmed by disconnecting power from all four directional control valve solenoids. It is preferred to electrically disarm the control rods since, in this condition, drive water cools and minimizes crud accumulation in the drive. Verification that all the other control rods are fully inserted is required to meet the SDM requirements.

Verification that a control rod withdrawal block has been inserted ensures that no other control rods can be inadvertently withdrawn under conditions when position indication instrumentation is inoperable for the affected control rod. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is acceptable because of the administrative controls on control rod withdrawals, the protection afforded by the LCOs involved, and hard-wired interlocks to preclude an additional control rod withdrawal.

SR 3.10.4.2 and SR 3.10.4.4 have been modified by Notes, which clarify that these SRs are not required to be met if the alternative requirements demonstrated by SR 3.10.4.1 are satisfied.

REFERENCES 1. UFSAR, Section 15.1.4.3.

DAEC B 3.10-20 TSCR-120

Single CRD Removal - Refueling B 3.10.5 BASES SURVEILLANCE SR 3.10.5.1, SR 3.10.5.2, SR 3.10.5.3, SR 3.10.5.4, REQUIREMENTS and SR 3.10.5.5 (continued) is required to ensure the assumptions of the safety analysis are satisfied. Periodic verification of the administrative controls established by this Special Operations LCO is prudent to preclude the possibility of an inadvertent criticality. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is acceptable, given the administrative controls on control rod removal and hard-wired interlocks to block an additional control rod withdrawal.

REFERENCES 1. UFSAR, Section 15.1.4.3.

DAEC B 3.10-25 TSCR-120

Multiple Control Rod Withdrawal - Refueling B 3.10.6 BASES (continued)

APPLICABILITY Operation in MODE 5 is controlled by existing LCOs. The exceptions from other LCO requirements (e.g., the ACTIONS of LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5) allowed by this Special Operations LCO are appropriately controlled by requiring all fuel to be removed from cells whose "full in" indicators are allowed to be bypassed.

ACTIONS A.1, A.2.1, and A.2.2 If one or more of the requirements of this Special Operations LCO are not met, the immediate implementation of these Required Actions restores operation consistent with the normal requirements for refueling (i.e., all control rods inserted in core cells containing one or more fuel assemblies) or with the exceptions granted by this Special Operations LCO. The Completion Times for Required Action A.1, Required Action A.2.1, and Required Action A.2.2 are intended to require that these Required Actions be implemented in a very short time and carried through in an expeditious manner to either initiate action to restore the affected CRDs and insert their control rods, or initiate action to restore compliance with this Special Operations LCO.

SURVEILLANCE SR 3.10.6.1, SR 3.10.6.2, and SR 3.10.6.3 REQUIREMENTS Periodic verification of the administrative controls established by this Special Operations LCO is prudent to preclude the possibility of an inadvertent criticality. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The Frequency is acceptable, given the administrative controls on fuel assembly and control rod removal, and takes into account other indications of control rod status available in the control room.

REFERENCES 1. UFSAR, Section 15.1.4.3.

DAEC B 3.10-28 TSCR-120

SDM Test - Refueling B 3.10.8 BASES (continued)

SURVEILLANCE SR 3.10.8.1, SR 3.10.8.2, and SR 3.10.8.3 REQUIREMENTS LCO 3.3.1.1, Functions 2.a and 2.d, made applicable in this Special Operations LCO, are required to have applicable Surveillances met to establish that this Special Operations LCO is being met. However, the control rod withdrawal sequences during the SDM tests may be enforced by the RWM (LCO 3.3.2.1, Function 2, MODE 2 requirements) or by a second licensed operator or other qualified member of the technical staff. As noted, either the applicable SRs for the RWM (LCO 3.3.2.1) must be satisfied according to the applicable Frequencies (SR 3.10.8.2), or the proper movement of control rods must be verified (SR 3.10.8.3). This latter verification (i.e., SR 3.10.8.3) must be performed during control rod movement to prevent deviations from the specified sequence. These surveillances provide adequate assurance that the specified test sequence is being followed.

SR 3.10.8.4 Periodic verification of the administrative controls established by this LCO will ensure that the reactor is operated within the bounds of the safety analysis. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency is intended to provide appropriate assurance that each operating shift is aware of and verifies compliance with these Special Operations LCO requirements.

SR 3.10.8.5 Coupling verification is performed to ensure the control rod is connected to the control rod drive mechanism and will perform its intended function when necessary. The verification is required to be performed any time a control rod is withdrawn to the "full out" notch position, or prior to declaring the control rod OPERABLE after work on the control rod or CRD System that could affect coupling. This Frequency is acceptable, considering the low probability that a control rod will become uncoupled when it is not being moved as well as operating experience related to uncoupling events.

(continued)

DAEC B 3.10-37 TSCR-120

SDM Test - Refueling B 3.10.8 BASES SURVEILLANCE SR 3.10.8.6 REQUIREMENTS (continued) CRD charging water header pressure verification is performed to ensure the motive force is available to scram the control rods in the event of a scram signal. A minimum accumulator pressure is specified, below which the capability of the accumulator to perform its intended function becomes degraded and the accumulator is considered inoperable. The minimum accumulator pressure of 970 psig is well below the expected pressure of 1100 psig. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency has been shown to be acceptable through operating experience and takes into account indications available in the control room.

REFERENCES 1. NEDE-24011-P-A-US, General Electric Standard Application for Reactor Fuel, Supplement for United States (as amended).

2. Letter from T. Pickens (BWROG) to G.C. Lainas, NRC, "Amendment 17 to General Electric Licensing Topical Report NEDE-2401 1-P-A," August 15, 1986.

DAEC B 3.10-38 TSCR-120

ML12121A687

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