Text

Final Technical Specification Markup and Clean Pages for License Amendment Request to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
	ML16132A561
Person / Time
Site:	Columbia
Issue date:	05/11/2016
From:	Hettel W; Energy Northwest
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GO2-16-071
	Download: ML16132A561 (282)
	v • d • e

William G. Hettel Vice President, Operations P.O. Box 968, Mail Drop PE23 Richland, WA 99352-0968 Ph. 509-377-8311 F. 509-377-4674 wghettel@energy-northwest.com May 11, 2016 GO2-16-071 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 FINAL TECHNICAL SPECIFICATION MARKUP AND CLEAN PAGES FOR LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATION TASK FORCE (TSTF)-425, REVISION 3 TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCIES TO A LICENSEE CONTROLLED PROGRAM

References:

1. Letter, GO2-15-007, dated March 17, 2015, WG Hettel (Energy Northwest) to NRC, License Amendment Request for Adoption of Technical Specification Task Force Traveler (TSTF)-425, Revision 3

2. Letter, GO2-15-128, dated September 17, 2015, RE Schuetz (Energy Northwest) to NRC, Response to Request for Additional Information on License Amendment Request for Adopt Technical Specification Task Force (TSTF)-425, Revision 3

3. Letter, GO2-15-145, dated October 29, 2015, RE Schuetz (Energy Northwest to NRC, Response to Request for Additional Information (RAI) 3 on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3

4. Letter, GO2-15-152, dated November 17, 2015, WG Hettel (Energy Northwest) to NRC, Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3

5. Letter, GO2-15-173, dated December 28, 2015, WG Hettel (Energy Northwest) to NRC, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3

G02-16-071 Page 2 of 3

6. Letter, G02-16-057, dated April 7, 2016, WG Hettel (Energy Northwest) to NRC, "Response to Second Request for Additional Information (RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program"

Dear Sir or Madam:

By Reference 1 as supplemented by References 2, 3, 4, 5 and 6, Energy Northwest submitted for approval the License Amendment Request (LAR) to adopt TSTF-425, Revision 3.

This letter transmits the final markup and clean pages of the Technical Specifications

{TS) for the LAR submitted in Reference 1 as supplemented by References 2, 3, 4, 5, and 6. This final set of markup and clean TS pages supersedes all other previously submitted markup and clean TS pages for this LAR. Attachment 1 contains the markup pages of the TS. Attachment 2 contains the clean pages of the TS.

All TS pages made obsolete by implementation of License Amendment 226 remain retained in the Columbia TS. These obsolete pages will be deleted under a separate LAR with a projected submission date of November 30, 2017.

The No S~gnificant Hazards Consideration determination (NSHCD) provided in the original submittal is not altered by this submittal. This letter and its attachment contain no regulatory commitments.

If there are any questions or if additional information is needed, please contact Ms. L. L.

Williams, Licensing Supervisor, at 509-377-8148.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this I o-n.< day of m &'1 , 2016.

Respectfully, W.G. Hettel Vice President, Operations Attachments: As stated cc: On next page

GO2-16-071 Page 3 of 3 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPN1399 (email)

WA Horin - Winston & Strawn RR Cowley -WDOH (email)

EFSECutc.wa.gov-- EFSEC (email)

GO2-16-071 FINAL MARK-UP TECHNICAL SPECIFICATION

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 Program24 hours 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 the LPSP of the RWM.

Insert each partially withdrawn control rod at least In accordance one notch. with the Surveillance Frequency Control Program31 days SR 3.1.3.3 Verify each control rod scram time from fully In accordance withdrawn to notch position 5 is 7 seconds. with SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.4 Verify each control rod does not go to the withdrawn Each time the 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 Columbia Generating Station 3.1.3-4 Amendment No. 212,216 225

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the limits Prior to exceeding of Table 3.1.4-1 with reactor steam dome pressure 40% RTP after 800 psig. each reactor shutdown 120 days SR 3.1.4.2 Verify, for a representative sample, each tested In accordance control rod scram time is within the limits of with the Table 3.1.4-1 with reactor steam dome pressure Surveillance 800 psig. Frequency Control Program200 days cumulative operation in MODE 1 SR 3.1.4.3 Verify each affected control rod scram time is within Prior to declaring the limits of Table 3.1.4-1 with any reactor steam control rod dome pressure. OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after pressure 800 psig. fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Columbia Generating Station 3.1.4-2 Amendment No. 194,211 225

Control Rod Scram Accumulators 3.1.5 ACTION CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control rod C.1 Verify the associated Immediately upon scram accumulators control rod is fully inserted. discovery of charging inoperable with reactor water header steam dome pressure pressure < 940 psig

< 900 psig.

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

D. Required Action B.1 or D.1 ---------------NOTE--------------

C.1 and associated Not applicable if all Completion Time not inoperable control rod met. scram accumulators are associated with fully inserted control rods.

Place the reactor mode Immediately switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator pressure In accordance is 940 psig. with the Surveillance Frequency Control Program7 days Columbia Generating Station 3.1.5-3 Amendment No. 169,216 225

Rod Pattern Control 3.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B (continued) B.2 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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply with In accordance BPWS. with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.1.6-2 Amendment No. 149,169 225

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SLC subsystem A.1 Restore SLC subsystem to 7 days inoperable. OPERABLE status.

B. Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. subsystem to OPERABLE status.

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 not met. AND 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 3.1.7.1 Verify available volume of sodium pentaborate In accordance solution is 4587 gallons. with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.1.7-1 Amendment No. 169,199 225

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.2 Verify temperature of sodium pentaborate solution is In accordance within the limits of Figure 3.1.7-1. with the Surveillance Frequency Control Program24 hours SR 3.1.7.3 Verify continuity of explosive charge. In accordance with the Surveillance Frequency Control Program31 days SR 3.1.7.4 Verify the concentration of boron in solution is within In accordance the limits of Figure 3.1.7-1. with the Surveillance Frequency Control Program31 days 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 3.1.7-1 SR 3.1.7.5 Verify each SLC subsystem manual and power In accordance operated valve in the flow path that is not locked, with the sealed, or otherwise secured in position, is in the Surveillance correct position or can be aligned to the correct Frequency position. Control Columbia Generating Station 3.1.7-2 Amendment No. 169,199 225

SLC System 3.1.7 Program31 days Columbia Generating Station 3.1.7-3 Amendment No. 169,199 225

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each pump develops a flow rate 41.2 gpm In accordance at a discharge pressure 1220 psig. with the Inservice Testing Program SR 3.1.7.7 Verify flow through one SLC subsystem from pump In accordance into reactor pressure vessel. with the Surveillance Frequency Control Program24 month s on a STAGGERED TEST BASIS SR 3.1.7.8 Verify all heat traced piping between storage tank In accordance and pump suction valve is unblocked. with the Surveillance Frequency Control Program24 month s

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 3.1.7-1 SR 3.1.7.9 Verify sodium pentaborate enrichment is 44.0 Prior to addition to atom percent B-10. SLC Tank Columbia Generating Station 3.1.7-4 Amendment No. 199,221 225

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 performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. In accordance with the Surveillance Frequency Control Program31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully In accordance closed and fully open position. with the Surveillance Frequency Control Program92 days SR 3.1.8.3 Verify each SDV vent and drain valve: In accordance with the

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

b. Opens when the actual or simulated scram Program24 month signal is reset. s Columbia Generating Station 3.1.8-2 Amendment No. 149,169 225

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 25% 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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND In accordance with the Surveillance Frequency Control Program24 hours thereafter Columbia Generating Station 3.2.1-1 Amendment No. 149,169 225

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 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. 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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND In accordance with the Surveillance Frequency Control Program24 hours thereafter Columbia Generating Station 3.2.2-1 Amendment No. 169,211 225

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. 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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the limits Once within specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafterIn accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.2.3-1 Amendment No. 149,169 225

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required I.1 Initiate alternate method to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and detect and suppress referenced in thermal hydraulic instability Table 3.3.1.1-1. oscillations.

AND

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

LCO 3.0.4 is not applicable.

I.2 Restore required channels 120 days to OPERABLE J. Required Action and J.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to less than the Time of Condition I not value specified in the met. COLR.

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. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sIn accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.1.1-11 Amendment No. 169 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 25% RTP.

Verify the absolute difference between the average 7 daysIn power range monitor (APRM) channels and the accordance with calculated power 2% RTP while operating at the Surveillance Frequency 25% RTP.

Control Program SR 3.3.1.1.3 -------------------------------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. 7 daysIn accordance with the Surveillance Frequency Control Program SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. 7 daysIn accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels overlap. withdrawing SRMs from the fully inserted position SR 3.3.1.1.6 -------------------------------NOTE------------------------------

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

Verify the IRM and APRM channels overlap. 7 daysIn accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.1.1-12 Amendment No. 169 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.7 Calibrate the local power range monitors. 1130 MWD/T average core exposureIn accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST. 92 daysIn accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Deleted.

SR 3.3.1.1.10 ------------------------------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.

3. For Functions 2.b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION. 18 months for Functions 1, 3, 4, 6, 7, and 9 through 11 AND 24 months for Functions 2, 5, and 8In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 Deleted.

SR 3.3.1.1.12 Verify Turbine Throttle Valve - Closure, and 18 monthsIn Columbia Generating Station 3.3.1.1-13 Amendment No. 179 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 Turbine Governor Valve Fast Closure Trip Oil accordance with the Pressure - Low Functions are not bypassed when Surveillance THERMAL POWER is 30% RTP. Frequency Control Program SR 3.3.1.1.13 Perform CHANNEL FUNCTIONAL TEST. 24 monthsIn accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.1.1-14 Amendment No. 179 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 monthsIn accordance with the Surveillance Frequency Control Program SR 3.3.1.1.15 ------------------------------NOTES-----------------------------

1. Neutron detectors are excluded.

2. Channel sensors for Functions 3 and 4 are excluded.

3. For Function 5, n equals 4 channels for the purpose of determining the STAGGARDED TEST BASIS Frequency. 24 months on a

4. For Function 2.e, "n" equals 8 channels for the STAGGERED purpose of determining the STAGGERED TEST TEST BASISIn BASIS Frequency. Testing of APRM and accordance with oscillation power range monitor (OPRM) the Surveillance outputs shall alternate. Frequency

Control Program Verify the RPS RESPONSE TIME is within limits.

SR 3.3.1.1.16 ------------------------------NOTES-----------------------------

1. 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.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST. 184 daysIn accordance with the Surveillance Frequency Control Program SR 3.3.1.1.17 Verify the OPRM is not bypassed when APRM 24 monthsIn Simulated Thermal Power is greater than or equal to accordance with the value specified in the COLR and recirculation the Surveillance drive flow is less than the value specified in the Frequency Columbia Generating Station 3.3.1.1-15 Amendment No. 169 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 COLR. Control Program Columbia Generating Station 3.3.1.1-16 Amendment No. 169 225 226

SRM Instrumentation 3.3.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except for MODE 5. control rod insertion.

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

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 Program12 hours Columbia Generating Station 3.3.1.2-2 Amendment No. 149,169 225

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 located in: In accordance with the

a. The fueled region; Surveillance Frequency

b. The core quadrant where CORE Control ALTERATIONS are being performed when the Program12 hours 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 Program24 hours 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.

Verify count rate is: In accordance with the

a. 3.0 cps with a signal to noise ratio 2:1 or Surveillance Frequency

b. 0.7 cps with a signal to noise ratio 20:1. Control Program12 hours during CORE ALTERATIONS Columbia Generating Station 3.3.1.2-3 Amendment No. 149,169 225

SRM Instrumentation 3.3.1.2 AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Columbia Generating Station 3.3.1.2-4 Amendment No. 149,169 225

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.2.5 -------------------------------NOTE------------------------------

The determination of signal to noise ratio is 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.

Perform CHANNEL FUNCTIONAL TEST and In accordance determination of signal to noise ratio. with the Surveillance Frequency Control Program7 days 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 and In accordance determination of signal to noise ratio. with the Surveillance Frequency Control Program31 days 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.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program18 month s

Columbia Generating Station 3.3.1.2-5 Amendment No. 149,169 225

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 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 184 days 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 Program92 days 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 Program92 days Columbia Generating Station 3.3.2.1-9 Amendment No. 169 225 226

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1.4 -------------------------------NOTE------------------------------

Neutron detectors are excluded.

Verify the RBM is not bypassed: In accordance with the

a. Low Power Range - Upscale Function is not Surveillance bypassed when APRM Simulated Thermal Frequency Power is 28% and < 63% RTP and peripheral Control control rod is not selected. Program24 months

b. Intermediate Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is 63% and < 83% RTP and peripheral control rod is not selected.

c. High Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is 83% and peripheral control rod is not selected.

SR 3.3.2.1.5 -------------------------------NOTE------------------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program24 months SR 3.3.2.1.6 Verify the RWM is not bypassed when THERMAL In accordance POWER is 10% RTP. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.2.1-10 Amendment No. 179 225 226

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1.7 -------------------------------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 Program24 month s

SR 3.3.2.1.8 Verify control rod sequences input to the RWM are Prior to declaring in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM Columbia Generating Station 3.3.2.1-11 Amendment No. 226

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 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 feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program24 hours SR 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program92 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The Allowable In accordance Value shall be 56.0 inches. with the Surveillance Frequency Control Program24 month s

SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, In accordance including valve actuation. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.2.2-2 Amendment No. 149,169 225

PAM Instrumentation 3.3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by Required F.1 Initiate action in accordance Immediately Action D.1 and with Specification 5.6.4.

referenced in Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS

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

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

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 other required channel(s) in the associated Function is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program31 days SR 3.3.3.1.2 Deleted SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for Functions 1, In accordance 2, 4, 5, and 10. with the Surveillance Frequency Control Program 18 months Columbia Generating Station 3.3.3.1-2 Amendment No.189,190 225

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1.4 Perform CHANNEL CALIBRATION for In accordance Functions 3, 6, and 7. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.3.1-3 Amendment No.189,208 225

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 Function 30 days Functions inoperable. 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

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 .

SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required In accordance instrumentation channel that is normally energized. with the Surveillance Frequency Control Program31 days Columbia Generating Station 3.3.3.2-1 Amendment No. 169,187 225

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.2 Perform CHANNEL CALIBRATION for each In accordance required instrumentation channel, except the with the suppression pool water level instrumentation Surveillance channel. Frequency Control Program18 month s

SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for the In accordance suppression pool water level instrumentation with the channel. Surveillance Frequency Control Program24 month s

SR 3.3.3.2.4 Verify each required control circuit and transfer In accordance switch is capable of performing the intended with the functions. Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.3.2-2 Amendment No. 149,169 225

EOC-RPT Instrumentation 3.3.4.1 ACTIONS 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 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable EOC-RPT as MCPR limit for specified in the COLR.

inoperable EOC-RPT not made applicable.

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

OR C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 30% 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 92 days Columbia Generating Station 3.3.4.1-2 Amendment No. 149,169 225

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1.2.a Perform CHANNEL CALIBRATION. The Allowable In accordance with Value shall be: the Surveillance Frequency Control TTV - Closure: 7% closed. Program24 months SR 3.3.4.1.2.b Perform CHANNEL CALIBRATION. The Allowable In accordance with Value shall be: the Surveillance Frequency Control TGV Fast Closure, Trip Oil Pressure - Low: Program18 months 1000 psig.

SR 3.3.4.1.3 Verify TTV - Closure and TGV Fast Closure, Trip In accordance with Oil Pressure - Low Functions are not bypassed the Surveillance when THERMAL POWER is 30% RTP. Frequency Control Program 18 months SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, In accordance with including breaker actuation. the Surveillance Frequency Control Program24 months SR 3.3.4.1.5 -------------------------------NOTE------------------------------

Breaker arc suppression time may be assumed from the most recent performance of SR 3.3.4.1.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME is In accordance with within limits. the Surveillance Frequency Control Program24 months on a STAGGERED TEST BASIS SR 3.3.4.1.6 Determine RPT breaker arc suppression time. In accordance with the Surveillance Frequency Control Program60 months Columbia Generating Station 3.3.4.1-3 Amendment No. 168,169 225

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability for one Function.

capability not maintained.

D. Required Action and D.1 Remove the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion recirculation pump from Time not met. service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK for Reactor Vessel In accordance Water Level - Low Low, Level 2 Function. with the Surveillance Frequency Control Program12 hours SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program92 days Columbia Generating Station 3.3.4.2-2 Amendment No. 149,169 225

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The Allowable In accordance Values shall be: with the Surveillance

a. Reactor Vessel Water Level - Low Low, Level 2: Frequency

-58 inches; and Control Program 18 months

b. Reactor Vessel Steam Dome Pressure - High:

1143 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, In accordance including breaker actuation. with the Surveillance Frequency Control Program 24 months Columbia Generating Station 3.3.4.2-3 Amendment No. 149,169 225

ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B, C, inoperable.

D, E, F, or G not met.

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 3.c, 3.f, and 3.g; 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 3.c, 3.f, and 3.g provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program12 hours SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program 92 days Columbia Generating Station 3.3.5.1-5 Amendment No. 150,169 225

ECCS Instrumentation 3.3.5.1 SURVEILLANCE FREQUENCY Columbia Generating Station 3.3.5.1-6 Amendment No. 150,169 225

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program 18 months SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program 24 months SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program 24 months Columbia Generating Station 3.3.5.1-7 Amendment No. 169 172, 225

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 4; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1 and 3 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 Program12 hours SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program18 month s

SR 3.3.5.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.5.2-3 Amendment No. 149,169 225

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required I.1 Declare associated standby 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and liquid control (SLC) referenced in subsystem inoperable.

Table 3.3.6.1-1.

OR I.2 Isolate the Reactor Water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Cleanup (RWCU) System.

J. As required by Required J.1 Initiate action to restore Immediately Action C.1 and channel to OPERABLE referenced in status.

Table 3.3.6.1-1.

OR J.2 Initiate action to isolate the Immediately Residual Heat Removal (RHR) Shutdown Cooling (SDC) System.

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 for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 Program12 hours Columbia Generating Station 3.3.6.1-3 Amendment No. 149,169 225

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program92 days SR 3.3.6.1.3 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program184 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program18 month s

SR 3.3.6.1.5 Perform CHANNEL CALIBRATION In accordance with the Surveillance Frequency Control Program24 month s

SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program24 month s

SR 3.3.6.1.7 -------------------------------NOTE------------------------------

Channel sensors for Functions 1.a, 1.b, and 1.c are excluded.

Columbia Generating Station 3.3.6.1-4 Amendment No. 150,169 225

Primary Containment Isolation Instrumentation 3.3.6.1 Verify the ISOLATION SYSTEM RESPONSE TIME In accordance is within limits. with the Surveillance Frequency Control Program24 month s on a STAGGERED TEST BASIS Columbia Generating Station 3.3.6.1-5 Amendment No. 150,169 225

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months standby gas treatment (SGT) subsystem in operation.

OR C.2.2 Declare associated SGT 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable.

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 isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program12 hours SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program92 days Columbia Generating Station 3.3.6.2-2 Amendment No. 149,169 225

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program18 month s

SR 3.3.6.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.6.2-3 Amendment No. 172,199 225

CREF System Instrumentation 3.3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place associated CREF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion subsystem in the Time of Condition B or C pressurization mode of not met. operation.

OR D.2 Declare associated CREF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable.

SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREF System 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 CREF initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program12 hours SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program92 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Columbia Generating Station 3.3.7.1-2 Amendment No. 187,199 225

CREF System Instrumentation 3.3.7.1 SURVEILLANCE FREQUENCY Control Program18 month s

Columbia Generating Station 3.3.7.1-3 Amendment No. 187,199 225

CREF System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.7.1-4 Amendment No. 169,199 225

LOP Instrumentation 3.3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition B or C not met. OR

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

Only applicable for Functions 1.c and 1.d.

D.2.1 Open offsite circuit supply Immediately breaker to associated 4.16 kV ESF bus.

AND D.2.2 Declare associated offsite Immediately circuit inoperable.

SURVEILLANCE REQUIREMENTS

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 initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program31 days Columbia Generating Station 3.3.8.1-2 Amendment No. 149,169 225

LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program18 month s

SR 3.3.8.1.3 Perform CHANNEL CALIBRATION In accordance with the Surveillance Frequency Control Program24 month s

SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.8.1-3 Amendment No. 149,169 225

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS

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

When an RPS electric power monitoring assembly is placed in an inoperable status solely for performance of required Surveillances, entry into the 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 RPS electric power monitoring assembly for the associated power supply maintains trip capability.

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program184 days SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The Allowable In accordance Values shall be: with the Surveillance

a. Overvoltage 133.8 V, with time delay Frequency 3.46 seconds; Control Program24 month

b. Undervoltage 110.8 V, with time delay s 3.46 seconds; and

c. Underfrequency 57 Hz, with time delay 3.46 seconds.

SR 3.3.8.2.3 Perform a system functional test. In accordance with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.3.8.2-3 Amendment No. 169,179 225

Recirculation Loops Operating (After Implementation of PRNM Upgrade) 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 Condition A or B not met.

OR No recirculation loops in operation.

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 loop drive flow mismatch with In accordance both recirculation loops in operation is: with the Surveillance

a. 10% of rated recirculation loop drive flow Frequency when operating at < 70% of rated core flow; and Control Program24 hours

b. 5% of rated recirculation loop drive flow when operating at 70% of rated core flow.

Columbia Generating Station 3.4.1-4 Amendment No. 171 225 226

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 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 > 25% RTP.

Verify at least two of the following criteria (a, b, In accordance and c) are satisfied for each operating recirculation with the loop: Surveillance Frequency

a. Recirculation loop drive flow versus Control recirculation pump speed differs by 10% from Program24 hours established patterns.

b. Recirculation loop drive flow versus total core flow differs by 10% from established patterns.

c. Each jet pump diffuser to lower plenum differential pressure differs by 20% from established patterns, or each jet pump flow differs by 10% from established patterns.

Columbia Generating Station 3.4.2-2 Amendment No. 149,169 225

SRVs - 25% RTP 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (SRVs) - 25% RTP LCO 3.4.3 The safety function of 12 SRVs shall be OPERABLE, with two SRVs in the lowest two lift setpoint groups OPERABLE.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRVs inoperable. POWER to < 25% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the required In accordance SRVs are as follows: with the Inservice Testing Program Number of Setpoint SRVs (psig) 2 1165 +/- 34.9 4 1175 +/- 35.2 4 1185 +/- 35.5 4 1195 +/- 35.8 4 1205 +/- 36.1 SR 3.4.3.2 Verify each required SRV opens when manually In accordance actuated. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.4.3-1 Amendment No. 149,169 225

SRVs - < 25% RTP 3.4.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify the safety function lift setpoints of the required In accordance with SRVs are as follows: the Inservice Testing Program Number of Setpoint SRVs (psig) 2 1165 +/- 34.9 4 1175 +/- 35.2 4 1185 +/- 35.5 4 1195 +/- 35.8 4 1205 +/- 36.1 SR 3.4.4.2 -------------------------------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 required SRV opens when manually In accordance with actuated. the Surveillance Frequency Control Program24 months Columbia Generating Station 3.4.4-2 Amendment No. 149,169,225,236

RCS Operational LEAKAGE 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 Condition A or B AND not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify RCS unidentified and total LEAKAGE and In accordance unidentified LEAKAGE increase are within limits. with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.4.5-2 Amendment No. 149,169 225

RCS Leakage Detection Instrumentation 3.4.7 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 required leakage detection instrumentation is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.4.7.1 Perform CHANNEL CHECK of required drywell In accordance atmospheric monitoring system. with the Surveillance Frequency Control Program12 hours SR 3.4.7.2 Perform CHANNEL FUNCTIONAL TEST of required In accordance leakage detection instrumentation. with the Surveillance Frequency Control Program31 days SR 3.4.7.3 Perform CHANNEL CALIBRATION of required In accordance leakage detection instrumentation. with the Surveillance Frequency Control Program18 month s

Columbia Generating Station 3.4.7-3 Amendment No. 149,169 225

RCS Specific Activity 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT I-131 In accordance specific activity is 0.2 µCi/gm. with the Surveillance Frequency Control Program7 days Columbia Generating Station 3.4.8-2 Amendment No. 149,169 225

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Initiate action to restore one Immediately cooling subsystem in RHR shutdown cooling operation. subsystem or one recirculation pump to AND operation.

No recirculation pump in AND operation.

B.2 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery circulation by an alternate of no reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.3 Monitor reactor coolant Once per hour temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -------------------------------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 less than 48 psig.

Verify one RHR shutdown cooling subsystem or In accordance recirculation pump is operating. with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.4.9-2 Amendment No. 164,169 225

RHR Shutdown Cooling System - Cold Shutdown 3.4.10 ACTIONS 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 discovery cooling subsystem in circulating by an alternate of no reactor coolant operation. method. circulation AND AND No recirculation pump in Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operation. thereafter AND B.2 Monitor reactor coolant Once per hour temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify one RHR shutdown cooling subsystem or In accordance recirculation pump is operating. with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.4.10-2 Amendment No. 149,169 225

RCS P/T Limits 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------------------------------NOTE------------------------------

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

Verify: In accordance with the

a. RCS pressure and RCS temperature are within Surveillance the applicable limits specified in Frequency Figures 3.4.11-1, 3.4.11-2, and 3.4.11-3; Control Program30 minut

b. RCS heatup and cooldown rates are 100°F in es any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period; and

c. RCS temperature change during inservice leak and hydrostatic testing is 20°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period when the RCS pressure and RCS temperature are not within the limits of Figure 3.4.11-2.

SR 3.4.11.2 Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in 15 minutes prior Figure 3.4.11-3. to control rod withdrawal for the purpose of achieving criticality SR 3.4.11.3 -------------------------------NOTE------------------------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump startup.

Verify the difference between the bottom head Once within coolant temperature and the reactor pressure vessel 15 minutes prior (RPV) coolant temperature is 145°F. to each startup of a recirculation pump Columbia Generating Station 3.4.11-2 Amendment No. 149,169 225

RCS P/T Limits 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.7 -------------------------------NOTE------------------------------

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

Verify reactor vessel flange and head flange In accordance temperatures are 80°F. with the Surveillance Frequency Control Program30 minut es SR 3.4.11.8 -------------------------------NOTE------------------------------

Not required to be performed until 30 minutes after RCS temperature 90°F in MODE 4.

Verify reactor vessel flange and head flange In accordance temperatures are 80°F. with the Surveillance Frequency Control Program30 minut es SR 3.4.11.9 -------------------------------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 100°F in MODE 4.

Verify reactor vessel flange and head flange In accordance temperatures are 80°F. with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.4.11-4 Amendment No. 149,169 225

Reactor Steam Dome Pressure 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Reactor Steam Dome Pressure LCO 3.4.12 The reactor steam dome pressure shall be 1035 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 3.4.12.1 Verify reactor steam dome pressure is 1035 psig. In accordance with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.4.12-1 Amendment No. 149,169 225

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, 31 daysIn the piping is filled with water from the pump accordance with discharge valve to the injection valve. the Surveillance Frequency Control Program SR 3.5.1.2 ------------------------------NOTE-------------------------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than 48 psig in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem 31 daysIn manual, power operated, and automatic valve in the accordance with flow path, that is not locked, sealed, or otherwise the Surveillance secured in position, is in the correct position. Frequency Control Program SR 3.5.1.3 Verify ADS accumulator backup compressed gas 31 daysIn system average pressure in the required bottles is accordance with 2200 psig. the Surveillance Frequency Control Program SR 3.5.1.4 Verify each ECCS pump develops the specified flow In accordance rate with the specified differential pressure between with the Inservice reactor and suction source. Testing Program DIFFERENTIAL PRESSURE BETWEEN REACTOR AND SYSTEM FLOW RATE SUCTION SOURCE LPCS 6200 gpm 128 psid LPCI 7200 gpm 26 psid HPCS 6350 gpm 200 psid Columbia Generating Station 3.5.1-4 Amendment No. 169,205,225,229,236

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.5 -------------------------------NOTE------------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 monthsIn actuates on an actual or simulated automatic accordance with initiation signal. the Surveillance Frequency Control Program SR 3.5.1.6 -------------------------------NOTE------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated 24 monthsIn automatic initiation signal. accordance with the Surveillance Frequency Control Program SR 3.5.1.7 -------------------------------NOTE------------------------------

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

Verify each required ADS valve opens when 24 months on a manually actuated. STAGGERED TEST BASIS for each valve solenoidIn accordance with the Surveillance Frequency Control Program SR 3.5.1.8 -------------------------------NOTE------------------------------

ECCS actuation instrumentation is excluded.

Verify the ECCS RESPONSE TIME for each ECCS 24 monthsIn injection/spray subsystem is within limits. accordance with the Surveillance Columbia Generating Station 3.5.1-5 Amendment No. 169,205,225,236

ECCS - Operating 3.5.1 Frequency Control Program Columbia Generating Station 3.5.1-6 Amendment No. 169,205,225,236

ECCS - Shutdown 3.5.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 Initiate action to restore Immediately associated Completion secondary containment to Time not met. OPERABLE status.

AND D.2 Initiate action to restore one Immediately standby gas treatment subsystem to OPERABLE status.

AND D.3 Initiate action to restore Immediately 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 ECCS In accordance injection/spray subsystem, the suppression pool with the water level is 18 ft 6 inches. Surveillance Frequency Control Program12 hours SR 3.5.2.2 Verify, for the required High Pressure Core Spray In accordance (HPCS) System, the: with the Surveillance

a. Suppression pool water level is 18 ft 6 inches; Frequency or Control Program12 hours

b. Condensate storage tank (CST) water level is 16.5 ft in a single CST or 10.5 ft in each CST.

Columbia Generating Station 3.5.2-2 Amendment No. 169,210 225

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for each required ECCS injection/spray In accordance subsystem, the piping is filled with water from the with the pump discharge valve to the injection valve. Surveillance Frequency Control Program31 days SR 3.5.2.4 ------------------------------NOTE-------------------------------

One low pressure coolant injection (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 injection/spray In accordance subsystem manual, power operated, and automatic with the valve in the flow path, that is not locked, sealed, or Surveillance otherwise secured in position, is in the correct Frequency position. Control Program31 days SR 3.5.2.5 Verify each required ECCS pump develops the In accordance specified flow rate with the specified differential with the Inservice pressure between reactor and suction source. Testing Program DIFFERENTIAL PRESSURE BETWEEN REACTOR AND SYSTEM FLOW RATE SUCTION SOURCE LPCS 6200 gpm 128 psid LPCI 7200 gpm 26 psid HPCS 6350 gpm 200 psid Columbia Generating Station 3.5.2-3 Amendment No. 169,205 225 229

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.6 -------------------------------NOTE------------------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray In accordance subsystem actuates on an actual or simulated with the automatic initiation signal. Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.5.2-4 Amendment No.

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with water In accordance from the pump discharge valve to the injection with the valve. Surveillance Frequency Control Program31 days SR 3.5.3.2 Verify each RCIC System manual, power operated, In accordance and automatic valve in the flow path, that is not with the locked, sealed, or otherwise secured in position, is Surveillance in the correct position. Frequency Control Program31 days 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 1035 psig and In accordance 935 psig, the RCIC pump can develop a flow rate with the 600 gpm against a system head corresponding to Surveillance reactor pressure. Frequency Control Program92 days 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 165 psig, the RCIC In accordance pump can develop a flow rate 600 gpm against a with the system head corresponding to reactor pressure. Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.5.3-2 Amendment No. 150,169 225

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.5 -------------------------------NOTE------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or In accordance simulated automatic initiation signal. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.5.3-3 Amendment No.

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.2 Verify drywell to suppression chamber bypass In accordance leakage is 10% of the acceptable A / K design with the value of 0.050 ft2 at an initial differential pressure of Surveillance 1.5 psid. Frequency Control Program120 mont hs AND 48 months following a test with bypass leakage greater than the bypass leakage limit AND 24 months following two consecutive tests with bypass leakage greater than the bypass leakage limit until two consecutive tests are less than or equal to the bypass leakage limit SR 3.6.1.1.3 -------------------------------NOTE------------------------------

Performance of SR 3.6.1.1.2 satisfies this surveillance.

Verify individual drywell to suppression chamber In accordance vacuum relief valve bypass pathway leakage is with the 1.2% of the acceptable A / K design value of Surveillance 0.050 ft2 at an initial differential pressure of Frequency 1.5 psid. Control Program24 month s

Columbia Generating Station 3.6.1.1-2 Amendment No. 169,201 225

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.4 -------------------------------NOTE------------------------------

Performance of SR 3.6.1.1.2 satisfies this surveillance.

Verify total drywell to suppression chamber vacuum In accordance relief valve bypass leakage is 3.0% of the with the acceptable A / K design value of 0.050 ft2 at an Surveillance initial differential pressure of 1.5 psid. Frequency Control Program 24 months Columbia Generating Station 3.6.1.1-3 Amendment No. 201 225

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 leakage rate testing in accordance with the Primary with the Primary Containment Leakage Rate Testing Program. Containment Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary containment air In accordance lock can be opened at a time. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.6.1.2-4 Amendment No. 149,169 225

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

Not required to be met when the 24 inch and 30 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 24 inch and 30 inch primary In accordance containment purge valve is closed. with the Surveillance Frequency Control Program31 days SR 3.6.1.3.2 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance valve and blind flange that is located outside primary with the containment and not locked, sealed, or otherwise Surveillance secured and is required to be closed during accident Frequency conditions is closed. Control Program31 days Columbia Generating Station 3.6.1.3-6 Amendment No. 169,208 225

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.3 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual Prior to entering valve and blind flange that is located inside primary MODE 2 or 3 from containment and not locked, sealed, or otherwise MODE 4 if secured and is required to be closed during accident primary conditions is closed. containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) In accordance shear isolation valve explosive charge. with the Surveillance Frequency Control Program31 days SR 3.6.1.3.5 Verify the isolation time of each power operated, In accordance automatic PCIV, except for MSIVs, is within limits. with the Inservice Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance 3 seconds and 5 seconds. with the Inservice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation In accordance position on an actual or simulated isolation signal. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.6.1.3-7 Amendment No. 199,208 225

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.8 Verify a representative sample of reactor instrument In accordance line EFCVs actuate to the isolation position on an with the actual or simulated instrument line break signal. Surveillance Frequency Control Program24 month s

SR 3.6.1.3.9 Remove and test the explosive squib from each In accordance shear isolation valve of the TIP System. with the Surveillance Frequency Control Program24 month s on a STAGGERED TEST BASIS SR 3.6.1.3.10 Verify the combined leakage rate for all secondary In accordance containment bypass leakage paths is 0.04% with the Primary primary containment volume/day when pressurized Containment to Pa. Leakage Rate Testing Program SR 3.6.1.3.11 Verify leakage rate through each MSIV is In accordance 16.0 scfh when tested at 25.0 psig. with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify combined leakage rate through hydrostatically In accordance tested lines that penetrate the primary containment with the Primary is within limits. Containment Leakage Rate Testing Program Columbia Generating Station 3.6.1.3-8 Amendment No. 199,208 225

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°F.

APPLICABILITY: MODES 1, 2, and 3.

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

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. 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 within limit. In accordance with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.6.1.4-1 Amendment No. 149,169 225

RHR Drywell Spray 3.6.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify each RHR drywell spray subsystem manual, 31 daysIn power operated, and automatic valve in the flow accordance with path that is not locked, sealed, or otherwise secured the Surveillance in position, is in the correct position or can be Frequency aligned to the correct position. Control Program SR 3.6.1.5.2 Verify each spray nozzle is unobstructed. 10 yearsIn accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.5-2 Amendment No. 230

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two or more lines with E.1 Restore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one or more reactor breakers in two lines to building-to-suppression OPERABLE status.

chamber vacuum breakers inoperable for opening.

F. Required Action and F.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 Condition A, B AND or E not met.

F.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 breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. 14 daysIn accordance with the Surveillance Frequency Control Program SR 3.6.1.6.2 Perform a functional test of each vacuum breaker. In accordance with the Inservice Testing Program Columbia Generating Station 3.6.1.6-2 Amendment No. 149,169,225,236

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.3 Verify the full open setpoint of each vacuum breaker 24 monthsIn is 0.5 psid. accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.6-3 Amendment No.

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. One or more D.1 Close one open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months suppression chamber-to- breaker disk.

drywell vacuum breakers with two disks not closed.

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 of Condition C or D AND not met.

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 3.6.1.7.1 -------------------------------NOTE------------------------------

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

Verify each vacuum breaker is closed. 14 daysIn accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.7-2 Amendment No. 169,202,225,236

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.2 Perform a functional test of each required vacuum 31 daysIn breaker. accordance with the Surveillance Frequency Control Program AND Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after any discharge of steam to the suppression chamber from the safety/relief valves SR 3.6.1.7.3 Verify the full open setpoint of each required 24 monthsIn vacuum breaker is 0.5 psid. accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.7-3 Amendment No.

Suppression Pool Average Temperature 3.6.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is In accordance within the applicable limits. with the Surveillance Frequency Control Program24 hours AND 5 minutes when performing testing that adds heat to the suppression pool Columbia Generating Station 3.6.2.1-3 Amendment No. 149,169 225

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 30 ft 9.75 inches and 31 ft 1.75 inches.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression pool 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within limits. 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 within limits. In accordance with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.6.2.2-1 Amendment No. 149,169 225

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 daysIn subsystem manual, power operated, and automatic accordance with valve in the flow path that is not locked, sealed, or the Surveillance otherwise secured in position, is in the correct Frequency position or can be aligned to the correct position. Control Program SR 3.6.2.3.2 Verify each RHR pump develops a flow rate In accordance 7100 gpm through the associated heat exchanger with the Inservice while operating in the suppression pool cooling Testing Program mode.

Columbia Generating Station 3.6.2.3-2 Amendment No. 169 225 230

Primary Containment Atmosphere Mixing System 3.6.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Operate each head area return fan for 15 minutes. In accordance with the Surveillance Frequency Control Program92 days Columbia Generating Station 3.6.3.2-2 Amendment No.

Primary Containment Oxygen Concentration 3.6.3.3 3.6 CONTAINMENT SYSTEMS 3.6.3.3 Primary Containment Oxygen Concentration LCO 3.6.3.3 The primary containment oxygen concentration shall be < 3.5 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 the next scheduled 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 concentration to within limit.

not within 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% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.3.1 Verify primary containment oxygen concentration is In accordance within limits. with the Surveillance Frequency Control Program7 days Columbia Generating Station 3.6.3.3-1 Amendment No. 149,169 225

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch In accordance of vacuum water gauge. with the Surveillance Frequency Control Program24 hours SR 3.6.4.1.2 Verify all secondary containment equipment hatches In accordance are closed and sealed. with the Surveillance Frequency Control Program31 days SR 3.6.4.1.3 Verify each secondary containment access inner In accordance door or each secondary containment access outer with the door in each access opening is closed. Surveillance Frequency Control Program31 days SR 3.6.4.1.4 Verify each standby gas treatment (SGT) subsystem In accordance will draw down the secondary containment to with the 0.25 inch of vacuum water gauge in Surveillance 120 seconds. Frequency Control Program24 month s on a STAGGERED TEST BASIS SR 3.6.4.1.5 Verify each SGT subsystem can maintain In accordance 0.25 inch of vacuum water gauge in the secondary with the containment for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a flow rate 2240 cfm. Surveillance Frequency Control Program24 month s on a STAGGERED TEST BASIS Columbia Generating Station 3.6.4.1-2 Amendment No. 169,199 225

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation manual In accordance valve and blind flange that is not locked, sealed, or with the otherwise secured, and is required to be closed Surveillance during accident conditions is closed. Frequency Control Program 31 days SR 3.6.4.2.2 Verify the isolation time of each power operated, In accordance automatic SCIV is within limits. with the Inservice Testing Program SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation In accordance position on an actual or simulated automatic with the isolation signal. Surveillance Frequency Control Program 24 months Columbia Generating Station 3.6.4.2-3 Amendment No. 208 225

SGT System 3.6.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two SGT subsystems E.1 Initiate action to suspend Immediately inoperable during OPDRVs.

OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 10 continuous In accordance hours with heaters operating. with the Surveillance Frequency Control Program31 days SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual In accordance or simulated initiation signal. with the Surveillance Frequency Control Program24 month s

SR 3.6.4.3.4 Verify each SGT filter cooling recirculation valve can In accordance be opened and the fan started. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.6.4.3-2 Amendment No. 169,199 225

SW System and UHS 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 --------------NOTE---------------

associated Completion LCO 3.0.4.a is not Time of Condition B not applicable when entering met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Required Action and D.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 Condition A not AND met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Both SW subsystems inoperable.

OR UHS inoperable for reasons other than Condition A.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify the average water level in the UHS spray 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sIn ponds is 432 feet 9 inches mean sea level. accordance with the Surveillance Frequency Control Program SR 3.7.1.2 Verify the average water temperature of each UHS 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sIn spray pond is 77°F. accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.7.1-2 Amendment No. 149,169,225,233,236

SW System and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.3 -------------------------------NOTE------------------------------

Isolation of flow to individual components does not render SW subsystem inoperable.

Verify each SW subsystem manual, power 31 daysIn operated, and automatic valve in the flow path accordance with servicing safety related systems or components, the Surveillance that is not locked, sealed, or otherwise secured in Frequency position, is in the correct position. Control Program SR 3.7.1.4 Verify average sediment depth in each UHS spray 92 daysIn pond is < 0.5 ft. accordance with the Surveillance Frequency Control Program SR 3.7.1.5 Verify each SW subsystem actuates on an actual or 24 monthsIn simulated initiation signal. accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.7.1-3 Amendment No. 149,169,225,236

HPCS SW System 3.7.2 3.7 PLANT SYSTEMS 3.7.2 High Pressure Core Spray (HPCS) Service Water (SW) System LCO 3.7.2 The HPCS SW System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. HPCS SW System A.1 Declare HPCS System Immediately inoperable. inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 -------------------------------NOTE------------------------------

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

Verify each HPCS SW System manual, power In accordance operated, and automatic valve in the flow path, that with the is not locked, sealed, or otherwise secured in Surveillance position, is in the correct position. Frequency Control Program31 days SR 3.7.2.2 Verify the HPCS SW System actuates on an actual In accordance or simulated initiation signal. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.7.2-1 Amendment No. 149,169 225

CREF System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREF subsystem for 10 continuous 31 daysIn hours with the heaters operating. accordance with the Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREF filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.7.3.3 Verify each CREF subsystem actuates on an actual 24 monthsIn or simulated initiation signal. accordance with the Surveillance Frequency Control Program SR 3.7.3.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program Columbia Generating Station 3.7.3-3 Amendment No. 199,207 225

Control Room AC System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place OPERABLE control Immediately associated Completion room AC subsystem in Time of Condition A not operation.

met during OPDRVs.

OR D.2 Initiate action to suspend Immediately OPDRVs.

E. Required Action and E.1 Initiate action to suspend Immediately associated Completion OPDRVs.

Time of Condition B not met during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the 24 monthsIn capability to remove the assumed heat load. accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.7.4-2 Amendment No. 169,199,225,227,236

Main Condenser Offgas 3.7.5 SURVEILLANCE REQUIR5EMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 -------------------------------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 noble gases is 332 mCi/second after decay of 31 daysIn 30 minutes. accordance with the Surveillance 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 Columbia Generating Station 3.7.5-2 Amendment No. 149,169 225

Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are made applicable.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the requirements of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO not met. the LCO.

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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each main turbine In accordance bypass valve. with the Surveillance Frequency Control Program31 days Columbia Generating Station 3.7.6-1 Amendment No. 149,169 225

Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.2 Perform a system functional test. In accordance with the Surveillance Frequency Control Program24 month s

SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM In accordance RESPONSE TIME is within limits. with the Surveillance Frequency Control Program24 month s

Columbia Generating Station 3.7.6-2 Amendment No.

Spent Fuel Storage Pool Water Level 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be 22 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

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

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

water level not within LCO 3.0.3 is not applicable.

limit. -------------------------------------

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water level is 7 daysIn 22 ft over the top of irradiated fuel assemblies accordance with seated in the spent fuel storage pool racks. the Surveillance Frequency Control Program Columbia Generating Station 3.7.7-1 Amendment No. 149,169 225

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 ---------------NOTE--------------

associated Completion LCO 3.0.4.a is not Time of Condition A, B, applicable when entering C, D, or E not met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months G. Three or more required G.1 Enter LCO 3.0.3. Immediately AC sources inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated 7 daysIn power availability for each offsite circuit. accordance with 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.

Verify each required DG starts from standby 31 daysIn conditions and achieves steady state: accordance with the Surveillance

a. Voltage 3910 V and 4400 V and frequency Frequency Control 58.8 Hz and 61.2 Hz for DG-1 and DG-2; and Program

b. Voltage 3910 V and 4400 V and frequency Columbia Generating Station 3.8.1-5 Amendment No. 169,181,225,236

AC Sources - Operating 3.8.1 SURVEILLANCE FREQUENCY 58.8 Hz and 61.2 Hz for DG-3.

Columbia Generating Station 3.8.1-6 Amendment No. 169,181,225,236

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS 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.

5. The endurance test of SR 3.8.1.14 may be performed in lieu of the load-run test in SR 3.8.1.3 provided the requirements, except the upper load limits, of SR 3.8.1.3 are met.

Verify each required DG is synchronized and loaded 31 daysIn and operates for 60 minutes at a load 4000 kW accordance with and 4400 kW for DG-1 and DG-2, and 2340 kW the Surveillance and 2600 kW for DG-3. Frequency Control Program SR 3.8.1.4 Verify each required day tank contains fuel oil to 31 daysIn support greater than or equal to one hour of accordance with operation at full load plus 10%. the Surveillance Frequency Control Program SR 3.8.1.5 Check for and remove accumulated water from each 31 daysIn required day tank. accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.8.1-7 Amendment No. 173,215 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify each required fuel oil transfer subsystem 92 daysIn operates to automatically transfer fuel oil from the accordance with storage tank to the day tank. the Surveillance Frequency Control Program SR 3.8.1.7 -------------------------------NOTE------------------------------

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

Verify each required DG starts from standby 184 daysIn condition and achieves: accordance with the Surveillance

a. For DG-1 and DG-2 in 15 seconds, voltage Frequency 3910 V and frequency 58.8 Hz, and after Control Program steady state conditions are reached, maintains voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz; and

b. For DG-3, in 15 seconds, voltage 3910 V and frequency 58.8 Hz, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz.

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

The automatic transfer function of this Surveillance shall not normally be performed in MODE 1 or 2.

However, this Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of the power 24 monthsIn supply to safety related buses from the startup accordance with offsite circuit to the backup offsite circuit. the Surveillance Frequency Control Program Columbia Generating Station 3.8.1-8 Amendment No. 181,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.9 ------------------------------NOTES-----------------------------

1. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor as close to the power factor of the single largest post-accident load as practicable.

However, if grid conditions do not permit, the power factor limit is not required to be met.

Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each required DG rejects a load greater than 24 monthsIn or equal to its associated single largest post- accordance with accident load, and following load rejection, the the Surveillance frequency is 66.75 Hz. Frequency Control Program SR 3.8.1.10 ------------------------------NOTES-----------------------------

1. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor of 0.9 for DG-1 and DG-2, and 0.91 for DG-3. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each required DG does not trip and voltage is 24 monthsIn maintained 4784 V during and following a load accordance with rejection of a load 4400 kW for DG-1 and DG-2 the Surveillance and 2600 kW for DG-3. Frequency Control Program Columbia Generating Station 3.8.1-9 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.11 ------------------------------NOTES-----------------------------

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

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3 (not applicable to DG-3). However, portions of the Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 24 monthsIn signal: accordance with the Surveillance

a. De-energization of emergency buses; Frequency Control Program

b. Load shedding from emergency buses for Divisions 1 and 2; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 15 seconds for DG-1 and DG-2, and in 18 seconds for DG-3,

2. energizes auto-connected shutdown loads,

3. maintains steady state voltage 3910 V and 4400 V,

4. maintains steady state frequency 58.8 Hz and 61.2 Hz, and

5. supplies permanently connected and auto-connected shutdown loads for 5 minutes.

Columbia Generating Station 3.8.1-10 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.12 ------------------------------NOTES-----------------------------

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

2. This Surveillance shall not normally be performed in MODE 1 or 2 (not applicable to DG-3). However, portions of the Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Emergency Core 24 monthsIn Cooling System (ECCS) initiation signal each accordance with required DG auto-starts from standby condition and: the Surveillance Frequency

a. For DG-1 and DG-2, in 15 seconds achieves Control Program voltage 3910 V, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V and, for DG-3, in 15 seconds achieves voltage 3910 V, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V;

b. In 15 seconds, achieves frequency 58.8 Hz and after steady state conditions are achieved, maintains frequency 58.8 Hz and 61.2 Hz;

c. Operates for 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are auto-connected to the offsite power system.

Columbia Generating Station 3.8.1-11 Amendment No. 173,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.13 -------------------------------NOTE------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify each required DG's automatic trips are 24 monthsIn bypassed on an actual or simulated ECCS initiation accordance with signal except: the Surveillance Frequency

a. Engine overspeed; Control Program

b. Generator differential current; and

c. Incomplete starting sequence.

SR 3.8.1.14 ------------------------------NOTES-----------------------------

1. Momentary transients outside the load, excitation current, and power factor ranges do not invalidate this test.

2. Credit may be taken for unplanned events that satisfy this SR.

3. If performed with the DG synchronized with offsite power, it shall be performed at a power factor of 0.9 for DG-1 and DG-2, and 0.91 for DG-3. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each required DG operates for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: 24 monthsIn accordance with

a. For 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 4650 kW for DG-1 and the Surveillance DG-2, and 2850 kW for DG-3; and Frequency Control Program

b. For the remaining hours of the test loaded 4400 kW for DG-1 and DG-2, and 2600 kW for DG-3.

Columbia Generating Station 3.8.1-12 Amendment No. 181,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.15 ------------------------------NOTES-----------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months loaded 4000 kW for DG-1 and DG-2, and 2340 kW for DG-3.

Momentary transients outside of load range do not invalidate this test.

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

Verify each required DG starts and achieves: 24 monthsIn accordance with

a. For DG-1 and DG-2, in 15 seconds, voltage the Surveillance 3910 V and frequency 58.8 Hz, and after Frequency steady state conditions are reached, maintains Control Program voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz; and

b. For DG-3, in 15 seconds, voltage 3910 V and frequency 58.8 Hz, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz.

Columbia Generating Station 3.8.1-13 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.16 -------------------------------NOTE------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3 (not applicable to DG-3). However, this Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Credit may be taken for unplanned events that satisfy this SR.

Verify each required DG: 24 monthsIn accordance with

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

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

SR 3.8.1.17 -------------------------------NOTE------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify, with a DG operating in test mode and 24 monthsIn connected to its bus, an actual or simulated ECCS accordance with initiation signal overrides the test mode by: the Surveillance Frequency

a. Returning DG to ready-to-load operation; and Control Program

b. Automatically energizing the emergency load from offsite power.

Columbia Generating Station 3.8.1-14 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.18 -------------------------------NOTE------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load block 24 monthsIn is within +/- 10% of design interval for each time delay accordance with relay. the Surveillance Frequency Control Program Columbia Generating Station 3.8.1-15 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.19 ------------------------------NOTES-----------------------------

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

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3 (not applicable to DG-3). However, portions of the Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite 24 monthsIn power signal in conjunction with an actual or accordance with simulated ECCS initiation signal: the Surveillance Frequency

a. De-energization of emergency buses; Control Program

b. Load shedding from emergency buses for DG-1 and DG-2; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 15 seconds,

2. energizes auto-connected emergency loads,

3. maintains steady state voltage 3910 V and 4400 V,

4. maintains steady state frequency 58.8 Hz and 61.2 Hz, and

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

Columbia Generating Station 3.8.1-16 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.20 -------------------------------NOTE------------------------------

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

Verify, when started simultaneously from standby 10 yearsIn condition, DG-1 and DG-2 achieves, in accordance with 15 seconds, voltage 3910 V and frequency the Surveillance 58.8 Hz, and DG-3 achieves, in 15 seconds, Frequency voltage 3910 V and frequency 58.8 Hz. Control Program Columbia Generating Station 3.8.1-17 Amendment No. 204 225

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One or more DGs with E.1 Restore required starting air 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months required starting air receiver pressure to within receiver pressure: limit.

1. For DG-1 and DG-2,

< 230 psig and 150 psig; and

2. For DG-3, < 223 psig and 150 psig.

F. Required Action and F.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition A, B, C, D, or E not met.

OR One or more DGs with stored diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage subsystem contains In accordance greater than or equal to a seven day supply of fuel. with the Surveillance Frequency Control Program31 days Columbia Generating Station 3.8.3-2 Amendment No. 169,215 225

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.2 Verify lube oil inventory is greater than or equal to a In accordance seven day supply. with the Surveillance Frequency Control Program31 days SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program SR 3.8.3.4 Verify each required DG air start receiver pressure In accordance is: with the Surveillance

a. 230 psig for DG-1 and DG-2; and Frequency Control

b. 223 psig for DG-3. Program31 days SR 3.8.3.5 Check for and remove accumulated water from each In accordance fuel oil storage tank. with the Surveillance Frequency Control Program92 days Columbia Generating Station 3.8.3-3 Amendment No. 169,215 225

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or In accordance equal to the minimum established float voltage. with the Surveillance Frequency Control Program7 days SR 3.8.4.2 Verify each required battery charger supplies the In accordance required load for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months at: with the Surveillance

a. 126 V for the 125 V battery chargers; and Frequency Control

b. 252 V for the 250 V battery charger. Program24 month s

SR 3.8.4.3 ------------------------------NOTES-----------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not be performed in MODE 1, 2, or 3 for the Division 1 and 2 125 V DC batteries. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and In accordance maintain in OPERABLE status, the required with the emergency loads for the design duty cycle when Surveillance subjected to a battery service test. Frequency Control Program 24 months Columbia Generating Station 3.8.4-4 Amendment 169,204 225

Battery Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. One or more batteries F.1 Declare associated battery Immediately with a required battery inoperable.

parameter not met for reasons other than Condition A, B, C, D, or E.

OR Required Action and associated Completion Time of Condition A, B, C, D, or E not met.

OR One or more batteries with one or more battery cell(s) float voltage

< 2.07 V and float current > 2 amps.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 -------------------------------NOTE------------------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is 2 amps. In accordance with the Surveillance Frequency Control Program7 days Columbia Generating Station 3.8.6-3 Amendment 169,204 225

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify each battery pilot cell voltage is 2.07 V. In accordance with the Surveillance Frequency Control Program31 days SR 3.8.6.3 Verify each battery connected cell electrolyte level is In accordance greater than or equal to minimum established with the design limits. Surveillance Frequency Control Program31 days SR 3.8.6.4 Verify each battery pilot cell temperature is greater In accordance than or equal to minimum established design limits. with the Surveillance Frequency Control Program31 days SR 3.8.6.5 Verify each battery connected cell voltage is In accordance 2.07 V. with the Surveillance Frequency Control Program92 days Columbia Generating Station 3.8.6-4 Amendment 169,204 225

Battery Parameters 3.8.6 SURVEILLANCE FREQUENCY SR 3.8.6.6 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, or 3 for the Division 1 and 2 125 V DC batteries. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is 80% of the In accordance manufacturer's rating for the 125 V batteries and with the 83.4% of the manufacturer's rating for the 250 V Surveillance battery, when subjected to a performance discharge Frequency test or a modified performance discharge test. Control Program60 month s

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 Columbia Generating Station 3.8.6-5 Amendment

Distribution Systems - Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 ---------------NOTE--------------

associated Completion LCO 3.0.4.a is not Time of Condition A or B applicable when entering not met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Division 1 250 V DC D.1 Declare associated Immediately electrical power supported feature(s) distribution subsystem inoperable.

inoperable.

E. One or more Division 3 E.1 Declare High Pressure Immediately AC or DC electrical Core Spray System power distribution inoperable.

subsystems inoperable.

F. Two or more divisions F.1 Enter LCO 3.0.3. Immediately with inoperable electrical power distribution subsystems that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and indicated 7 daysIn power availability to required AC and DC electrical accordance with power distribution subsystems. the Surveillance Frequency Control Program Columbia Generating Station 3.8.7-2 Amendment No. 149,169,225,236

Distribution Systems - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and indicated In accordance power availability to required AC and DC electrical with the power distribution subsystems. Surveillance Frequency Control Program7 days Columbia Generating Station 3.8.8-2 Amendment 169,199 225

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks associated with the refuel position shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable. associated with the inoperable interlock(s).

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

a. All-rods-in, Control Program7 days

b. Refueling platform position,

c. Refueling platform fuel grapple fuel-loaded,

d. Refueling platform frame-mounted hoist fuel-loaded, and

e. Refueling platform trolley-mounted hoist fuel-loaded.

Columbia Generating Station 3.9.1-1 Amendment 149,169 225

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 insert Immediately 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 position. In accordance with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.9.2-1 Amendment 149,169 225

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 Program7 days Columbia Generating Station 3.9.2-2 Amendment

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 Program12 hours Columbia Generating Station 3.9.3-1 Amendment 149,169 225

Control Rod OPERABILITY - Refueling 3.9.5 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 insert Immediately control rods inoperable. 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 notch. In accordance with the Surveillance Frequency Control Program7 days SR 3.9.5.2 Verify each withdrawn control rod scram In accordance accumulator pressure is 940 psig. with the Surveillance Frequency Control Program7 days Columbia Generating Station 3.9.5-1 Amendment 149,169 225

RPV Water Level - Irradiated Fuel 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level - Irradiated Fuel LCO 3.9.6 RPV water level shall be 22 ft above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of Immediately within limit. irradiated fuel assemblies within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 22 ft above the top of the In accordance RPV flange. with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.9.6-1 Amendment 149,169 225

RPV Water Level - New Fuel or Control Rods 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Reactor Pressure Vessel (RPV) Water Level - New Fuel or Control Rods LCO 3.9.7 RPV water level shall be 23 ft above the top of irradiated fuel assemblies seated within the RPV.

APPLICABILITY: 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 new Immediately within limit. fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify RPV water level is 23 ft above the top of In accordance irradiated fuel assemblies seated within the RPV. with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.9.7-1 Amendment 169,199 225

RHR - High Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore one Immediately standby gas treatment subsystem to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

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 discovery cooling subsystem in circulation by an alternate of no reactor coolant operation. method. circulation 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 3.9.8.1 Verify one RHR shutdown cooling subsystem is In accordance operating. with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.9.8-2 Amendment 149,169 225

RHR - Low Water Level 3.9.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

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 discovery cooling subsystem in circulation by an alternate of no reactor coolant operation. method. circulation 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 3.9.9.1 Verify one RHR shutdown cooling subsystem is In accordance operating. with the Surveillance Frequency Control Program12 hours Columbia Generating Station 3.9.9-2 Amendment 149,169 225

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) 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 cells In accordance containing one or more fuel assemblies. with the Surveillance Frequency Control Program12 hours SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. In accordance with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.10.2-2 Amendment 149,169 225

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 being withdrawn, in a five by five array centered on with the the control rod being withdrawn, are disarmed. Surveillance Frequency Control Program24 hours SR 3.10.3.3 Verify all control rods, other than the control rod In accordance being withdrawn, are fully inserted. with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.10.3-3 Amendment 149,169 225

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2 Initiate action to satisfy the Immediately requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required LCOs. According to the 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 rod In accordance being withdrawn, in a five by five array centered on with the the control rod being withdrawn, are disarmed. Surveillance Frequency Control Program24 hours SR 3.10.4.3 Verify all control rods, other than the control rod In accordance being withdrawn, are fully inserted. with the Surveillance Frequency Control Program24 hours 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 inserted. In accordance with the Surveillance Frequency Control Columbia Generating Station 3.10.4-3 Amendment 149,169 225

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 SURVEILLANCE FREQUENCY Program24 hours Columbia Generating Station 3.10.4-4 Amendment 149,169 225

Single CRD Removal - Refueling 3.10.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control rod In accordance withdrawn for the removal of the associated CRD, with the are fully inserted. Surveillance Frequency Control Program24 hours SR 3.10.5.2 Verify all control rods, other than the control rod In accordance withdrawn for the removal of the associated CRD, in with the a five by five array centered on the control rod Surveillance withdrawn for the removal of the associated CRD, Frequency are disarmed. Control Program24 hours SR 3.10.5.3 Verify a control rod withdrawal block is inserted. In accordance with the Surveillance Frequency Control Program24 hours SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 SR 3.10.5.5 Verify no other CORE ALTERATIONS are in In accordance progress. with the Surveillance Frequency Control Program24 hours Columbia Generating Station 3.10.5-2 Amendment 149,169 225

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

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed from In accordance core cells associated with each control rod or CRD with the removed. Surveillance Frequency Control Program24 hours SR 3.10.6.2 Verify all other control rods in core cells containing In accordance one or more fuel assemblies are fully inserted. with the Surveillance Frequency Control Program24 hours SR 3.10.6.3 -------------------------------NOTE------------------------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in In accordance compliance with an approved spiral reload with the sequence. Surveillance Frequency Control Program24 hours Columbia Generating Station 3.10.6-2 Amendment 149,169 225

SDM Test - Refueling (After Implementation of PRNM Upgrade) 3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 compliance During control rod with the approved control rod sequence for the SDM movement 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 progress. with the Surveillance Frequency Control Program12 hours SR 3.10.8.5 Verify each withdrawn control rod does not go to the Each time 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 940 psig. with the Surveillance Frequency Control Program7 days Columbia Generating Station 3.10.8-7 Amendment No. 169 225 226

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Filtration (CREF) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE 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 CRE habitability at Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the CREF 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 CRE boundary.

e. The quantitative limits on unfiltered air inleakage into the CRE. 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 for DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE 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 CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Columbia Generating Station 5.5-11 Amendment 207,216 225

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 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.

Columbia Generating Station 5.5-12 Amendment

GO2-16-071 FINAL CLEAN TECHNICAL SPECIFICATION

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 the LPSP of the RWM.

Insert each partially withdrawn control rod at least In accordance one notch. with the Surveillance Frequency Control Program SR 3.1.3.3 Verify each control rod scram time from fully In accordance withdrawn to notch position 5 is 7 seconds. with SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.4 Verify each control rod does not go to the withdrawn Each time the 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 Columbia Generating Station 3.1.3-4 Amendment No. 212,216 225

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the limits Prior to exceeding of Table 3.1.4-1 with reactor steam dome pressure 40% RTP after 800 psig. each reactor shutdown 120 days SR 3.1.4.2 Verify, for a representative sample, each tested In accordance control rod scram time is within the limits of with the Table 3.1.4-1 with reactor steam dome pressure Surveillance 800 psig. Frequency Control Program SR 3.1.4.3 Verify each affected control rod scram time is within Prior to declaring the limits of Table 3.1.4-1 with any reactor steam control rod dome pressure. OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after pressure 800 psig. fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Columbia Generating Station 3.1.4-2 Amendment No. 194,211 225

Control Rod Scram Accumulators 3.1.5 ACTION CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control rod C.1 Verify the associated Immediately upon scram accumulators control rod is fully inserted. discovery of charging inoperable with reactor water header steam dome pressure pressure < 940 psig

< 900 psig.

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

D. Required Action B.1 or D.1 ---------------NOTE--------------

C.1 and associated Not applicable if all Completion Time not inoperable control rod met. scram accumulators are associated with fully inserted control rods.

Place the reactor mode Immediately switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator pressure In accordance is 940 psig. with the Surveillance Frequency Control Program Columbia Generating Station 3.1.5-3 Amendment No. 169,216 225

Rod Pattern Control 3.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B (continued) B.2 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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply with In accordance BPWS. with the Surveillance Frequency Control Program Columbia Generating Station 3.1.6-2 Amendment No. 149,169 225

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SLC subsystem A.1 Restore SLC subsystem to 7 days inoperable. OPERABLE status.

B. Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. subsystem to OPERABLE status.

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 not met. AND 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 3.1.7.1 Verify available volume of sodium pentaborate In accordance solution is 4587 gallons. with the Surveillance Frequency Control Program Columbia Generating Station 3.1.7-1 Amendment No. 169,199 225

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.2 Verify temperature of sodium pentaborate solution is In accordance within the limits of Figure 3.1.7-1. with the Surveillance Frequency Control Program SR 3.1.7.3 Verify continuity of explosive charge. In accordance with the Surveillance Frequency Control Program SR 3.1.7.4 Verify the concentration of boron in solution is within In accordance the limits of Figure 3.1.7-1. with 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 3.1.7-1 SR 3.1.7.5 Verify each SLC subsystem manual and power In accordance operated valve in the flow path that is not locked, with the sealed, or otherwise secured in position, is in the Surveillance correct position or can be aligned to the correct Frequency position. Control Program Columbia Generating Station 3.1.7-2 Amendment No. 169,199 225

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each pump develops a flow rate 41.2 gpm In accordance at a discharge pressure 1220 psig. with the Inservice Testing Program SR 3.1.7.7 Verify flow through one SLC subsystem from pump In accordance into reactor pressure vessel. with the Surveillance Frequency Control Program SR 3.1.7.8 Verify all heat traced piping between storage tank In accordance and pump suction valve is unblocked. with 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 3.1.7-1 SR 3.1.7.9 Verify sodium pentaborate enrichment is 44.0 Prior to addition to atom percent B-10. SLC Tank Columbia Generating Station 3.1.7-3 Amendment No. 199,221 225

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 performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. In accordance with 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 Surveillance Frequency Control Program SR 3.1.8.3 Verify each SDV vent and drain valve: In accordance with the

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

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

Columbia Generating Station 3.1.8-2 Amendment No. 149,169 225

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 25% 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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.2.1-1 Amendment No. 149,169 225

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 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. 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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.2.2-1 Amendment No. 169,211 225

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. 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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the limits Once within specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.2.3-1 Amendment No. 149,169 225

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required I.1 Initiate alternate method to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and detect and suppress referenced in thermal hydraulic instability Table 3.3.1.1-1. oscillations.

AND

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

LCO 3.0.4 is not applicable.

I.2 Restore required channels 120 days to OPERABLE J. Required Action and J.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to less than the Time of Condition I not value specified in the met. COLR.

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 Columbia Generating Station 3.3.1.1-11 Amendment No. 169 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 25% RTP.

Verify the absolute difference between the average In accordance power range monitor (APRM) channels and the with the calculated power 2% RTP while operating at Surveillance Frequency 25% RTP.

Control Program SR 3.3.1.1.3 -------------------------------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 SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels overlap. withdrawing SRMs from the fully inserted position SR 3.3.1.1.6 -------------------------------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 Columbia Generating Station 3.3.1.1-12 Amendment No. 169 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.7 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Deleted.

SR 3.3.1.1.10 ------------------------------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.

3. For Functions 2.b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 Deleted.

SR 3.3.1.1.12 Verify Turbine Throttle Valve - Closure, and In accordance with Turbine Governor Valve Fast Closure Trip Oil the Surveillance Pressure - Low Functions are not bypassed when Frequency Control THERMAL POWER is 30% RTP. Program SR 3.3.1.1.13 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.1.1-13 Amendment No. 179 225 226

RPS Instrumentation (After Implementation of PRNM Upgrade) 3.3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.15 ------------------------------NOTES-----------------------------

1. Neutron detectors are excluded.

2. Channel sensors for Functions 3 and 4 are excluded.

Verify the RPS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.16 ------------------------------NOTES-----------------------------

1. 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.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.17 Verify the OPRM is not bypassed when APRM In accordance Simulated Thermal Power is greater than or equal to with the the value specified in the COLR and recirculation Surveillance drive flow is less than the value specified in the Frequency COLR. Control Program Columbia Generating Station 3.3.1.1-14 Amendment No. 169 225 226

SRM Instrumentation 3.3.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except for MODE 5. control rod insertion.

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

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 Columbia Generating Station 3.3.1.2-2 Amendment No. 149,169 225

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 located in: In accordance with the

a. The fueled region; Surveillance Frequency

b. The core quadrant where CORE Control Program 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 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.

Verify count rate is: In accordance with the

a. 3.0 cps with a signal to noise ratio 2:1 or Surveillance Frequency

b. 0.7 cps with a signal to noise ratio 20:1. Control Program Columbia Generating Station 3.3.1.2-3 Amendment No. 149,169 225

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.2.5 -------------------------------NOTE------------------------------

The determination of signal to noise ratio is 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.

Perform CHANNEL FUNCTIONAL TEST and In accordance determination of signal to noise ratio. 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 and In accordance determination of signal to noise ratio. 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.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.1.2-4 Amendment No. 149,169 225

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 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 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 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 Columbia Generating Station 3.3.2.1-9 Amendment No. 169 225 226

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1.4 -------------------------------NOTE------------------------------

Neutron detectors are excluded.

Verify the RBM is not bypassed: In accordance with the

a. Low Power Range - Upscale Function is not Surveillance bypassed when APRM Simulated Thermal Frequency Power is 28% and < 63% RTP and peripheral Control Program control rod is not selected.

b. Intermediate Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is 63% and < 83% RTP and peripheral control rod is not selected.

c. High Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is 83% and peripheral control rod is not selected.

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 Verify the RWM is not bypassed when THERMAL In accordance POWER is 10% RTP. with the Surveillance Frequency Control Program Columbia Generating Station 3.3.2.1-10 Amendment No. 179 225 226

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1.7 -------------------------------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 3.3.2.1.8 Verify control rod sequences input to the RWM are Prior to declaring in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM Columbia Generating Station 3.3.2.1-11 Amendment No. 226

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 Table 3.3.2.1-1 (page 1 of 2)

Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1. Rod Block Monitor

a. Low Power Range - Upscale (a) 2 SR 3.3.2.1.1 (f)

SR 3.3.2.1.4 (d),(e)

SR 3.3.2.1.5

b. Intermediate Power Range - (b) 2 SR 3.3.2.1.1 (f)

Upscale SR 3.3.2.1.4 SR 3.3.2.1.5(d),(e)

c. High Power Range - Upscale (c) 2 SR 3.3.2.1.1 (f)

SR 3.3.2.1.4 SR 3.3.2.1.5(d),(e)

d. Inop (a),(b),(c) 2 SR 3.3.2.1.1 NA (a) APRM Simulated Thermal Power is 28% and < 63% RTP and MCPR is less than the limit specified in the COLR and no peripheral control rod selected.

(b) APRM Simulated Thermal Power is 63% and < 83% RTP and MCPR is less than the limit specified in the COLR and no peripheral control rod selected.

(c) APRM Simulated Thermal Power is 83% and MCPR is less than the limit specified in the COLR and no peripheral control rod selected.

(d) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(e) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable.

Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The LTSP and the methodologies used to determine the as-found and as-left tolerances are specified in the Licensee Controlled Specifications.

(f) Allowable Value Specified in the COLR.

Columbia Generating Station 3.3.2.1-12 Amendment No. 226

Control Rod Block Instrumentation (After Implementation of PRNM Upgrade) 3.3.2.1 Table 3.3.2.1-1 (page 2 of 2)

Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

2. Rod Worth Minimizer 1(g), 2(g) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.8

3. Reactor Mode Switch - Shutdown (h) 2 SR 3.3.2.1.7 NA Position (g) With THERMAL POWER 10% RTP.

(h) Reactor mode switch in the shutdown position.

Columbia Generating Station 3.3.2.1-13 Amendment No.

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 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 feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The Allowable In accordance Value shall be 56.0 inches. with the Surveillance Frequency Control Program SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, In accordance including valve actuation. with the Surveillance Frequency Control Program Columbia Generating Station 3.3.2.2-2 Amendment No. 149,169 225

PAM Instrumentation 3.3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by Required F.1 Initiate action in accordance Immediately Action D.1 and with Specification 5.6.4.

referenced in Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS

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

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

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 other required channel(s) in the associated Function is OPERABLE.

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 Deleted SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for Functions 1, In accordance 2, 4, 5, and 10. with the Surveillance Frequency Control Program Columbia Generating Station 3.3.3.1-2 Amendment No.189,190 225

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1.4 Perform CHANNEL CALIBRATION for In accordance Functions 3, 6, and 7. with the Surveillance Frequency Control Program Columbia Generating Station 3.3.3.1-3 Amendment No.189,208 225

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1

1. Reactor Vessel Pressure 2 E

2. Reactor Vessel Water Level

a. -150 inches to +60 inches 2 E

b. -310 inches to -110 inches 2 E

3. Suppression Pool Water Level

a. -25 inches to +25 inches 2 E

b. 2 ft to 52 ft 2 E

4. Suppression Chamber Pressure 2 E

5. Drywell Pressure

a. -5 psig to +3 psig 2 E

b. 0 psig to 25 psig 2 E

c. 0 psig to 180 psig 2 E

6. Primary Containment Area Radiation 2 F

7. Penetration Flow Path PCIV Position 2 per penetration flow E path(a) (b)

8. Deleted

9. Deleted

10. ECCS Pump Room Flood Level 5 E (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

Columbia Generating Station 3.3.3.1-4 Amendment No.

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 Function 30 days Functions inoperable. 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

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 .

SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required In accordance instrumentation channel that is normally energized. with the Surveillance Frequency Control Program Columbia Generating Station 3.3.3.2-1 Amendment No. 169,187 225

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.2 Perform CHANNEL CALIBRATION for each In accordance required instrumentation channel, except the with the suppression pool water level instrumentation Surveillance channel. Frequency Control Program SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for the In accordance suppression pool water level instrumentation with the channel. Surveillance Frequency Control Program SR 3.3.3.2.4 Verify each required control circuit and transfer In accordance switch is capable of performing the intended with the functions. Surveillance Frequency Control Program Columbia Generating Station 3.3.3.2-2 Amendment No. 149,169 225

EOC-RPT Instrumentation 3.3.4.1 ACTIONS 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 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable EOC-RPT as MCPR limit for specified in the COLR.

inoperable EOC-RPT not made applicable.

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

OR C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 30% 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 Columbia Generating Station 3.3.4.1-2 Amendment No. 149,169 225

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1.2.a Perform CHANNEL CALIBRATION. The Allowable In accordance with Value shall be: the Surveillance Frequency Control TTV - Closure: 7% closed. Program SR 3.3.4.1.2.b Perform CHANNEL CALIBRATION. The Allowable In accordance with Value shall be: the Surveillance Frequency Control TGV Fast Closure, Trip Oil Pressure - Low: Program 1000 psig.

SR 3.3.4.1.3 Verify TTV - Closure and TGV Fast Closure, Trip In accordance with Oil Pressure - Low Functions are not bypassed the Surveillance when THERMAL POWER is 30% RTP. Frequency Control Program SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, In accordance with including breaker actuation. the Surveillance Frequency Control Program SR 3.3.4.1.5 -------------------------------NOTE------------------------------

Breaker arc suppression time may be assumed from the most recent performance of SR 3.3.4.1.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME is In accordance with within limits. the Surveillance Frequency Control Program SR 3.3.4.1.6 Determine RPT breaker arc suppression time. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.4.1-3 Amendment No. 168,169 225

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability for one Function.

capability not maintained.

D. Required Action and D.1 Remove the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion recirculation pump from Time not met. service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK for Reactor Vessel In accordance Water Level - Low Low, Level 2 Function. with the Surveillance Frequency Control Program SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.4.2-2 Amendment No. 149,169 225

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The Allowable In accordance Values shall be: with the Surveillance

a. Reactor Vessel Water Level - Low Low, Level 2: Frequency

-58 inches; and Control Program

b. Reactor Vessel Steam Dome Pressure - High:

1143 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, In accordance including breaker actuation. with the Surveillance Frequency Control Program Columbia Generating Station 3.3.4.2-3 Amendment No. 149,169 225

ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B, C, inoperable.

D, E, F, or G not met.

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 3.c, 3.f, and 3.g; 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 3.c, 3.f, and 3.g provided the associated Function or the redundant Function maintains ECCS initiation 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 TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.5.1-5 Amendment No. 150,169 225

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.5.1-6 Amendment No. 169 172, 225

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)

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

1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems (b)

a. Reactor Vessel 1, 2, 3, 2 B SR 3.3.5.1.1 -142.3 inches Water Level - Low 4(a), 5(a) SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6

b. Drywell Pressure - 1, 2, 3 2(b) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.4 SR 3.3.5.1.6

c. LPCS Pump Start - 1, 2, 3, 1(e) C SR 3.3.5.1.5 8.53 seconds LOCA Time Delay 4(a), 5(a) SR 3.3.5.1.6 and Relay 10.64 seconds

d. LPCI Pump A Start - 1, 2, 3, 1(e) C SR 3.3.5.1.5 17.24 seconds LOCA Time Delay 4(a), 5(a) SR 3.3.5.1.6 and 21.53 Relay seconds

e. LPCI Pump A Start - 1, 2, 3, 1 C SR 3.3.5.1.2 3.04 seconds LOCA/LOOP Time 4(a), 5(a) SR 3.3.5.1.3 and Delay Relay SR 3.3.5.1.6 6.00 seconds

f. Reactor Vessel 1, 2, 3 1 per valve C SR 3.3.5.1.2 448 psig and Pressure - Low SR 3.3.5.1.4 492 psig (Injection SR 3.3.5.1.6 Permissive) 4(a), 5(a) 1 per valve B SR 3.3.5.1.2 448 psig and SR 3.3.5.1.4 492 psig SR 3.3.5.1.6 (a) When associated subsystem(s) are required to be OPERABLE.

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

(e) Also supports OPERABILITY of 230 kV offsite power circuit pursuant to LCO 3.8.1 and LCO 3.8.2.

Columbia Generating Station 3.3.5.1-7 Amendment No. 169,172 225

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

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

1. LPCI and LPCS Subsystems

g. LPCS Pump 1, 2, 3, 1 E SR 3.3.5.1.2 668 gpm and Discharge Flow - 4(a), 5(a) SR 3.3.5.1.4 1067 gpm Low (Minimum Flow) SR 3.3.5.1.6

h. LPCI Pump A 1, 2, 3, 1 E SR 3.3.5.1.2 605 gpm and Discharge Flow - 4(a), 5(a) SR 3.3.5.1.4 984 gpm Low (Minimum Flow) SR 3.3.5.1.6

i. Manual Initiation 1, 2, 3, 2 C SR 3.3.5.1.6 NA (a) 4(a), 5

2. LPCI B and LPCI C Subsystems

a. Reactor Vessel 1, 2, 3, 2(b) B SR 3.3.5.1.1 -142.3 inches Water Level - Low 4(a), 5(a) SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6

b. Drywell Pressure - 1, 2, 3 2(b) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.4 SR 3.3.5.1.6

c. LPCI Pump B Start - 1, 2, 3, 1(e) C SR 3.3.5.1.5 17.24 seconds LOCA Time Delay 4(a), 5(a) SR 3.3.5.1.6 and Relay 21.53 seconds (e)

d. LPCI Pump C Start - 1, 2, 3, 1 C SR 3.3.5.1.5 8.53 seconds LOCA Time Delay 4(a), 5(a) SR 3.3.5.1.6 and Relay 10.64 seconds

e. LPCI Pump B Start - 1, 2, 3, 1 C SR 3.3.5.1.2 3.04 seconds LOCA/LOOP Time 4(a), 5(a) SR 3.3.5.1.3 and Delay Relay SR 3.3.5.1.6 6.00 seconds (a) When associated subsystem(s) are required to be OPERABLE.

(b) Also required to initiate the associated DG.

(e) Also supports OPERABILITY of 230 kV offsite power circuit pursuant to LCO 3.8.1 and LCO 3.8.2.

Columbia Generating Station 3.3.5.1-8 Amendment No.166,169 225

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)

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

2. LPCI B and LPCI C Subsystems

f. Reactor Vessel 1, 2, 3, 1 per valve C SR 3.3.5.1.2 448 psig Pressure - Low SR 3.3.5.1.4 and (Injection SR 3.3.5.1.6 492 psig Permissive)

(a) (a) 4 ,5 1 per valve B SR 3.3.5.1.2 448 psig SR 3.3.5.1.4 and SR 3.3.5.1.6 492 psig

g. LPCI Pumps B & C 1, 2, 3, 1 per pump E SR 3.3.5.1.2 605 gpm (a) (a)

Discharge Flow - 4 ,5 SR 3.3.5.1.4 and Low (Minimum flow) SR 3.3.5.1.6 984 gpm

h. Manual Initiation 1, 2, 3, 2 C SR 3.3.5.1.6 NA (a) (a) 4 ,5

3. High Pressure Core Spray (HPCS) System (b)

a. Reactor Vessel 1, 2, 3, 4 B SR 3.3.5.1.1 -58 inches (a) (a)

Water Level - Low 4 ,5 SR 3.3.5.1.2 Low, Level 2 SR 3.3.5.1.4 SR 3.3.5.1.6 (b)

b. Drywell Pressure - 1, 2, 3 4 B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.4 SR 3.3.5.1.6

c. Reactor Vessel 1, 2, 3, 2 C SR 3.3.5.1.1 56.0 inches (a) (a)

Water Level - High, 4 ,5 SR 3.3.5.1.2 Level 8 SR 3.3.5.1.4 SR 3.3.5.1.6

d. Condensate Storage 1, 2, 3, 2 D SR 3.3.5.1.2 448 ft 1 inch (c) (c)

Tank Level - Low 4 ,5 SR 3.3.5.1.4 elevation SR 3.3.5.1.6 (a) When associated subsystem(s) are required to be OPERABLE.

(b) Also required to initiate the associated DG.

(c) When HPCS is OPERABLE for compliance with LCO 3.5.2, "ECCS - Shutdown," and aligned to the condensate storage tank while tank water level is not within the limit of SR 3.5.2.2.

Columbia Generating Station 3.3.5.1-9 Amendment No. 166,169 225

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)

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

3. HPCS System

e. Suppression Pool 1, 2, 3 2 D SR 3.3.5.1.2 466 ft Water Level - High SR 3.3.5.1.4 11 inches SR 3.3.5.1.6 elevation

f. HPCS System Flow 1, 2, 3, 1 E SR 3.3.5.1.2 1200 gpm and Rate - Low 4(a), 5(a) SR 3.3.5.1.4 1512 gpm (Minimum Flow) SR 3.3.5.1.6

g. Manual Initiation 1, 2, 3, 2 C SR 3.3.5.1.6 NA 4(a), 5(a)

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 -142.3 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6

b. ADS Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.2 115.0 seconds SR 3.3.5.1.3 SR 3.3.5.1.6

c. Reactor Vessel 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 9.5 inches Water Level - Low, SR 3.3.5.1.2 Level 3 (Permissive) SR 3.3.5.1.4 SR 3.3.5.1.6 (d) (d)

d. LPCS Pump 1, 2 , 3 2 G SR 3.3.5.1.2 119 psig and Discharge Pressure SR 3.3.5.1.4 171 psig

- High SR 3.3.5.1.6

e. LPCI Pump A 1, 2(d), 3(d) 2 G SR 3.3.5.1.2 116 psig and Discharge Pressure SR 3.3.5.1.4 134 psig

- High SR 3.3.5.1.6 (a) When associated subsystem(s) are required to be OPERABLE.

(d) With reactor steam dome pressure > 150 psig.

Columbia Generating Station 3.3.5.1-10 Amendment No. 166,169 225

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)

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

4. ADS Trip System A (d) (d)

f. Accumulator Backup 1, 2 , 3 3 F SR 3.3.5.1.2 151.4 psig Compressed Gas SR 3.3.5.1.4 System Pressure - SR 3.3.5.1.6 Low

g. Manual Initiation 1, 2(d), 3(d) 4 G SR 3.3.5.1.6 NA

5. ADS Trip System B

a. Reactor Vessel 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 -142.3 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6

b. ADS Initiation Timer 1, 2(d), 3(d) 1 G SR 3.3.5.1.2 115.0 seconds SR 3.3.5.1.3 SR 3.3.5.1.6

c. Reactor Vessel 1, 2(d), 3(d) 1 F SR 3.3.5.1.1 9.5 inches Water Level - SR 3.3.5.1.2 Low, Level 3 SR 3.3.5.1.4 (Permissive) SR 3.3.5.1.6

d. LPCI Pumps B & C 1, 2(d), 3(d) 2 per pump G SR 3.3.5.1.2 116 psig and Discharge Pressure SR 3.3.5.1.4 134 psig

- High SR 3.3.5.1.6

e. Accumulator Backup 1, 2(d), 3(d) 3 F SR 3.3.5.1.2 151.4 psig Compressed Gas SR 3.3.5.1.4 System Pressure - SR 3.3.5.1.6 Low

f. Manual Initiation 1, 2(d), 3(d) 4 G SR 3.3.5.1.6 NA (d) With reactor steam dome pressure > 150 psig.

Columbia Generating Station 3.3.5.1-11 Amendment No.

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 4; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1 and 3 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 LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.5.2-3 Amendment No. 149,169 225

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required I.1 Declare associated standby 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and liquid control (SLC) referenced in subsystem inoperable.

Table 3.3.6.1-1.

OR I.2 Isolate the Reactor Water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Cleanup (RWCU) System.

J. As required by Required J.1 Initiate action to restore Immediately Action C.1 and channel to OPERABLE referenced in status.

Table 3.3.6.1-1.

OR J.2 Initiate action to isolate the Immediately Residual Heat Removal (RHR) Shutdown Cooling (SDC) System.

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 for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 Columbia Generating Station 3.3.6.1-3 Amendment No. 149,169 225

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 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 CALIBRATION. 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 SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7 -------------------------------NOTE------------------------------

Channel sensors for Functions 1.a, 1.b, and 1.c are excluded.

Verify the ISOLATION SYSTEM RESPONSE TIME In accordance is within limits. with the Surveillance Frequency Control Program Columbia Generating Station 3.3.6.1-4 Amendment No. 150,169 225

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months standby gas treatment (SGT) subsystem in operation.

OR C.2.2 Declare associated SGT 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable.

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 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 FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.6.2-2 Amendment No. 149,169 225

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.6.2-3 Amendment No. 172,199 225

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE REQUIRED MODES OR CHANNELS OTHER PER SPECIFIED TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE (c)

1. Reactor Vessel Water Level - Low 1, 2, 3, (a) 2 SR 3.3.6.2.2 -58 inches Low, Level 2 SR 3.3.6.2.3 SR 3.3.6.2.4 (c)

2. Drywell Pressure - High 1, 2, 3 2 SR 3.3.6.2.2 1.88 psig SR 3.3.6.2.3 SR 3.3.6.2.4

3. Reactor Building Vent Exhaust 1, 2, 3, (a) 2 SR 3.3.6.2.1 16.0 mR/hr Plenum Radiation - High SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4

4. Manual Initiation 1, 2, 3, (a) 4 SR 3.3.6.2.4 NA (a) During operations with a potential for draining the reactor vessel.

(b) Deleted (c) Also required to initiate the associated LOCA Time Delay Relay Function pursuant to LCO 3.3.5.1.

Columbia Generating Station 3.3.6.2-4 Amendment No.

CREF System Instrumentation 3.3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place associated CREF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion subsystem in the Time of Condition B or C pressurization mode of not met. operation.

OR D.2 Declare associated CREF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable.

SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREF System 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 CREF initiation capability.

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. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.7.1-2 Amendment No. 187,199 225

CREF System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.7.1-3 Amendment No. 169,199 225

CREF System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)

Control Room Emergency Filtration System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION A.1 REQUIREMENTS VALUE

1. Reactor Vessel Water 1, 2, 3, (a) 2 B SR 3.3.7.1.1 -58 inches Level - Low Low, Level 2 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4

2. Drywell Pressure - High 1, 2, 3 2 C SR 3.3.7.1.1 1.88 psig SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4

3. Reactor Building Vent 1, 2, 3, (a) 2 B SR 3.3.7.1.1 16.0 mR/hr Exhaust Plenum SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.3 SR 3.3.7.1.4 (a) During operations with a potential for draining the reactor vessel.

Columbia Generating Station 3.3.7.1-4 Amendment No.

LOP Instrumentation 3.3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition B or C not met. OR

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

Only applicable for Functions 1.c and 1.d.

D.2.1 Open offsite circuit supply Immediately breaker to associated 4.16 kV ESF bus.

AND D.2.2 Declare associated offsite Immediately circuit inoperable.

SURVEILLANCE REQUIREMENTS

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 initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.8.1-2 Amendment No. 149,169 225

LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. 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 LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.8.1-3 Amendment No. 149,169 225

LOP Instrumentation 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)

Loss of Power Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION DIVISION ACTION A.1 REQUIREMENTS VALUE

1. Divisions 1 and 2 - 4.16 kV Emergency Bus Undervoltage

a. TR-S Loss of Voltage - 2 B SR 3.3.8.1.2 2450 V and 3135 V 4.16 kV Basis SR 3.3.8.1.4

b. TR-S Loss of Voltage - 2 B SR 3.3.8.1.3 2.95 seconds and Time Delay SR 3.3.8.1.4 7.1 seconds

c. TR-B Loss of Voltage - 1 C SR 3.3.8.1.3 2450 V and 3135 V 4.16 kV Basis SR 3.3.8.1.4

d. TR-B Loss of Voltage - 1 C SR 3.3.8.1.3 3.06 seconds and Time Delay SR 3.3.8.1.4 9.28 seconds

e. Degraded Voltage - 2(a) C SR 3.3.8.1.1 3685 V and 3755 V 4.16 kV Basis SR 3.3.8.1.2 SR 3.3.8.1.4

f. Degraded Voltage - 2(a) C SR 3.3.8.1.1 5.0 seconds and Primary Time Delay SR 3.3.8.1.2 5.3 seconds SR 3.3.8.1.4

g. Degraded Voltage - 1 C SR 3.3.8.1.2 2.63 seconds and Secondary Time Delay SR 3.3.8.1.4 3.39 seconds

2. Division 3 - 4.16 kV Emergency Bus Undervoltage

a. Los of Voltage - 2 B SR 3.3.8.1.2 2450 V and 3135 V 4.16 kV Basis SR 3.3.8.1.4

b. Loss of voltage - 2 B SR 3.3.8.1.3 1.87 seconds and Time Delay SR 3.3.8.1.4 3.73 seconds

c. Degraded Voltage - 2 C SR 3.3.8.1.2 3685 V and 3755 V 4.16 kV Basis SR 3.3.8.1.4

d. Degraded Voltage - 2 C SR 3.3.8.1.2 7.36 seconds and Time Delay SR 3.3.8.1.4 8.34 seconds (a) The Degraded Voltage - 4.16 kV Basis and - Primary Time Delay Functions must be associated with one another.

Columbia Generating Station 3.3.8.1-4 Amendment No.

RPS Electric Power Monitoring 3.3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to restore one Immediately associated Completion electric power monitoring Time of Condition A or B assembly to OPERABLE not met in MODE 4 or 5 status for inservice power with both RHR SDC supply(s) supplying suction isolation valves required instrumentation.

open.

OR D.2 Initiate action to isolate the Immediately RHR SDC System.

E. Required Action and E.1 Initiate action to fully insert Immediately associated Completion all insertable control rods in Time of Condition A or B core cells containing one or not met in MODE 5 with more fuel assemblies.

any control rod withdrawn from a core cell containing one or more fuel assemblies.

Columbia Generating Station 3.3.8.2-2 Amendment No. 149,169 225

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS

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

When an RPS electric power monitoring assembly is placed in an inoperable status solely for performance of required Surveillances, entry into the 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 RPS electric power monitoring assembly for the associated power supply maintains trip capability.

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

a. Overvoltage 133.8 V, with time delay Frequency 3.46 seconds; Control Program

b. Undervoltage 110.8 V, with time delay 3.46 seconds; and

c. Underfrequency 57 Hz, with time delay 3.46 seconds.

SR 3.3.8.2.3 Perform a system functional test. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.3.8.2-3 Amendment No. 169,179 225

Recirculation Loops Operating (After Implementation of PRNM Upgrade) 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 Condition A or B not met.

OR No recirculation loops in operation.

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 loop drive flow mismatch with In accordance both recirculation loops in operation is: with the Surveillance

a. 10% of rated recirculation loop drive flow Frequency when operating at < 70% of rated core flow; and Control Program

b. 5% of rated recirculation loop drive flow when operating at 70% of rated core flow.

Columbia Generating Station 3.4.1-4 Amendment No. 171 225 226

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 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 > 25% RTP.

Verify at least two of the following criteria (a, b, In accordance and c) are satisfied for each operating recirculation with the loop: Surveillance Frequency

a. Recirculation loop drive flow versus Control Program recirculation pump speed differs by 10% from established patterns.

b. Recirculation loop drive flow versus total core flow differs by 10% from established patterns.

c. Each jet pump diffuser to lower plenum differential pressure differs by 20% from established patterns, or each jet pump flow differs by 10% from established patterns.

Columbia Generating Station 3.4.2-2 Amendment No. 149,169 225

SRVs - 25% RTP 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (SRVs) - 25% RTP LCO 3.4.3 The safety function of 12 SRVs shall be OPERABLE, with two SRVs in the lowest two lift setpoint groups OPERABLE.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRVs inoperable. POWER to < 25% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the required In accordance SRVs are as follows: with the Inservice Testing Program Number of Setpoint SRVs (psig) 2 1165 +/- 34.9 4 1175 +/- 35.2 4 1185 +/- 35.5 4 1195 +/- 35.8 4 1205 +/- 36.1 SR 3.4.3.2 Verify each required SRV opens when manually In accordance actuated. with the Surveillance Frequency Control Program Columbia Generating Station 3.4.3-1 Amendment No. 149,169 225

SRVs - < 25% RTP 3.4.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify the safety function lift setpoints of the required In accordance with SRVs are as follows: the Inservice Testing Program Number of Setpoint SRVs (psig) 2 1165 +/- 34.9 4 1175 +/- 35.2 4 1185 +/- 35.5 4 1195 +/- 35.8 4 1205 +/- 36.1 SR 3.4.4.2 -------------------------------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 required SRV opens when manually In accordance with actuated. the Surveillance Frequency Control Program Columbia Generating Station 3.4.4-2 Amendment No. 149,169,225,236

RCS Operational LEAKAGE 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 Condition A or B AND not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify RCS unidentified and total LEAKAGE and In accordance unidentified LEAKAGE increase are within limits. with the Surveillance Frequency Control Program Columbia Generating Station 3.4.5-2 Amendment No. 149,169 225

RCS Leakage Detection Instrumentation 3.4.7 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 required leakage detection instrumentation is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.4.7.1 Perform CHANNEL CHECK of required drywell In accordance atmospheric monitoring system. with the Surveillance Frequency Control Program SR 3.4.7.2 Perform CHANNEL FUNCTIONAL TEST of required In accordance leakage detection instrumentation. with the Surveillance Frequency Control Program SR 3.4.7.3 Perform CHANNEL CALIBRATION of required In accordance leakage detection instrumentation. with the Surveillance Frequency Control Program Columbia Generating Station 3.4.7-3 Amendment No. 149,169 225

RCS Specific Activity 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT I-131 In accordance specific activity is 0.2 µCi/gm. with the Surveillance Frequency Control Program Columbia Generating Station 3.4.8-2 Amendment No. 149,169 225

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Initiate action to restore one Immediately cooling subsystem in RHR shutdown cooling operation. subsystem or one recirculation pump to AND operation.

No recirculation pump in AND operation.

B.2 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery circulation by an alternate of no reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.3 Monitor reactor coolant Once per hour temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -------------------------------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 less than 48 psig.

Verify one RHR shutdown cooling subsystem or In accordance recirculation pump is operating. with the Surveillance Frequency Control Program Columbia Generating Station 3.4.9-2 Amendment No. 164,169 225

RHR Shutdown Cooling System - Cold Shutdown 3.4.10 ACTIONS 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 discovery cooling subsystem in circulating by an alternate of no reactor coolant operation. method. circulation AND AND No recirculation pump in Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operation. thereafter AND B.2 Monitor reactor coolant Once per hour temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify one RHR shutdown cooling subsystem or In accordance recirculation pump is operating. with the Surveillance Frequency Control Program Columbia Generating Station 3.4.10-2 Amendment No. 149,169 225

RCS P/T Limits 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------------------------------NOTE------------------------------

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

Verify: In accordance with the

a. RCS pressure and RCS temperature are within Surveillance the applicable limits specified in Frequency Figures 3.4.11-1, 3.4.11-2, and 3.4.11-3; Control Program

b. RCS heatup and cooldown rates are 100°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period; and

c. RCS temperature change during inservice leak and hydrostatic testing is 20°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period when the RCS pressure and RCS temperature are not within the limits of Figure 3.4.11-2.

SR 3.4.11.2 Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in 15 minutes prior Figure 3.4.11-3. to control rod withdrawal for the purpose of achieving criticality SR 3.4.11.3 -------------------------------NOTE------------------------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump startup.

Verify the difference between the bottom head Once within coolant temperature and the reactor pressure vessel 15 minutes prior (RPV) coolant temperature is 145°F. to each startup of a recirculation pump Columbia Generating Station 3.4.11-2 Amendment No. 149,169 225

RCS P/T Limits 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.7 -------------------------------NOTE------------------------------

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

Verify reactor vessel flange and head flange In accordance temperatures are 80°F. with the Surveillance Frequency Control Program SR 3.4.11.8 -------------------------------NOTE------------------------------

Not required to be performed until 30 minutes after RCS temperature 90°F in MODE 4.

Verify reactor vessel flange and head flange In accordance temperatures are 80°F. with the Surveillance Frequency Control Program SR 3.4.11.9 -------------------------------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 100°F in MODE 4.

Verify reactor vessel flange and head flange In accordance temperatures are 80°F. with the Surveillance Frequency Control Program Columbia Generating Station 3.4.11-4 Amendment No. 149,169 225

Reactor Steam Dome Pressure 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Reactor Steam Dome Pressure LCO 3.4.12 The reactor steam dome pressure shall be 1035 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 3.4.12.1 Verify reactor steam dome pressure is 1035 psig. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.4.12-1 Amendment No. 149,169 225

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, In accordance the piping is filled with water from the pump with the discharge valve to the injection valve. Surveillance Frequency Control Program SR 3.5.1.2 ------------------------------NOTE-------------------------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than 48 psig in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem In accordance manual, power operated, and automatic valve in the with the flow path, that is not locked, sealed, or otherwise Surveillance secured in position, is in the correct position. Frequency Control Program SR 3.5.1.3 Verify ADS accumulator backup compressed gas In accordance system average pressure in the required bottles is with the 2200 psig. Surveillance Frequency Control Program SR 3.5.1.4 Verify each ECCS pump develops the specified flow In accordance rate with the specified differential pressure between with the Inservice reactor and suction source. Testing Program DIFFERENTIAL PRESSURE BETWEEN REACTOR AND SYSTEM FLOW RATE SUCTION SOURCE LPCS 6200 gpm 128 psid LPCI 7200 gpm 26 psid HPCS 6350 gpm 200 psid Columbia Generating Station 3.5.1-4 Amendment No. 169,205,225,229,236

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.5 -------------------------------NOTE------------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance actuates on an actual or simulated automatic with the initiation signal. Surveillance Frequency Control Program SR 3.5.1.6 -------------------------------NOTE------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated In accordance automatic initiation signal. with the Surveillance Frequency Control Program SR 3.5.1.7 -------------------------------NOTE------------------------------

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

Verify each required ADS valve opens when In accordance manually actuated. with the Surveillance Frequency Control Program SR 3.5.1.8 -------------------------------NOTE------------------------------

ECCS actuation instrumentation is excluded.

Verify the ECCS RESPONSE TIME for each ECCS In accordance injection/spray subsystem is within limits. with the Surveillance Frequency Control Program Columbia Generating Station 3.5.1-5 Amendment No. 169,205,225,236

ECCS - Shutdown 3.5.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 Initiate action to restore Immediately associated Completion secondary containment to Time not met. OPERABLE status.

AND D.2 Initiate action to restore one Immediately standby gas treatment subsystem to OPERABLE status.

AND D.3 Initiate action to restore Immediately 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 ECCS In accordance injection/spray subsystem, the suppression pool with the water level is 18 ft 6 inches. Surveillance Frequency Control Program SR 3.5.2.2 Verify, for the required High Pressure Core Spray In accordance (HPCS) System, the: with the Surveillance

a. Suppression pool water level is 18 ft 6 inches; Frequency or Control Program

b. Condensate storage tank (CST) water level is 16.5 ft in a single CST or 10.5 ft in each CST.

Columbia Generating Station 3.5.2-2 Amendment No. 169,210 225

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for each required ECCS injection/spray In accordance subsystem, the piping is filled with water from the with the pump discharge valve to the injection valve. Surveillance Frequency Control Program SR 3.5.2.4 ------------------------------NOTE-------------------------------

One low pressure coolant injection (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 injection/spray In accordance subsystem manual, power operated, and automatic with the valve in the flow path, that is not locked, sealed, or Surveillance otherwise secured in position, is in the correct Frequency position. Control Program SR 3.5.2.5 Verify each required ECCS pump develops the In accordance specified flow rate with the specified differential with the Inservice pressure between reactor and suction source. Testing Program DIFFERENTIAL PRESSURE BETWEEN REACTOR AND SYSTEM FLOW RATE SUCTION SOURCE LPCS 6200 gpm 128 psid LPCI 7200 gpm 26 psid HPCS 6350 gpm 200 psid Columbia Generating Station 3.5.2-3 Amendment No. 169,205 225 229

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.6 -------------------------------NOTE------------------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray In accordance subsystem actuates on an actual or simulated with the automatic initiation signal. Surveillance Frequency Control Program Columbia Generating Station 3.5.2-4 Amendment No.

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with water In accordance from the pump discharge valve to the injection with the valve. Surveillance Frequency Control Program SR 3.5.3.2 Verify each RCIC System manual, power operated, In accordance and automatic valve in the flow path, that is not with the locked, sealed, or otherwise secured in position, is Surveillance in the correct position. Frequency Control 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 1035 psig and In accordance 935 psig, the RCIC pump can develop a flow rate with the 600 gpm against a system head corresponding to Surveillance reactor pressure. Frequency Control Program 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 165 psig, the RCIC In accordance pump can develop a flow rate 600 gpm against a with the system head corresponding to reactor pressure. Surveillance Frequency Control Program Columbia Generating Station 3.5.3-2 Amendment No. 150,169 225

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.5 -------------------------------NOTE------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or In accordance simulated automatic initiation signal. with the Surveillance Frequency Control Program Columbia Generating Station 3.5.3-3 Amendment No.

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.2 Verify drywell to suppression chamber bypass In accordance leakage is 10% of the acceptable A / K design with the value of 0.050 ft2 at an initial differential pressure of Surveillance 1.5 psid. Frequency Control Program AND 48 months following a test with bypass leakage greater than the bypass leakage limit AND 24 months following two consecutive tests with bypass leakage greater than the bypass leakage limit until two consecutive tests are less than or equal to the bypass leakage limit SR 3.6.1.1.3 -------------------------------NOTE------------------------------

Performance of SR 3.6.1.1.2 satisfies this surveillance.

Verify individual drywell to suppression chamber In accordance vacuum relief valve bypass pathway leakage is with the 1.2% of the acceptable A / K design value of Surveillance 0.050 ft2 at an initial differential pressure of Frequency 1.5 psid. Control Program Columbia Generating Station 3.6.1.1-2 Amendment No. 169,201 225

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.4 -------------------------------NOTE------------------------------

Performance of SR 3.6.1.1.2 satisfies this surveillance.

Verify total drywell to suppression chamber vacuum In accordance relief valve bypass leakage is 3.0% of the with the acceptable A / K design value of 0.050 ft2 at an Surveillance initial differential pressure of 1.5 psid. Frequency Control Program Columbia Generating Station 3.6.1.1-3 Amendment No. 201 225

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 leakage rate testing in accordance with the Primary with the Primary Containment Leakage Rate Testing Program. Containment Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary containment air In accordance lock can be opened at a time. with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.2-4 Amendment No. 149,169 225

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

Not required to be met when the 24 inch and 30 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 24 inch and 30 inch primary In accordance containment purge valve is closed. with the Surveillance Frequency Control Program SR 3.6.1.3.2 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance valve and blind flange that is located outside primary with the containment and not locked, sealed, or otherwise Surveillance secured and is required to be closed during accident Frequency conditions is closed. Control Program Columbia Generating Station 3.6.1.3-6 Amendment No. 169,208 225

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.3 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual Prior to entering valve and blind flange that is located inside primary MODE 2 or 3 from containment and not locked, sealed, or otherwise MODE 4 if secured and is required to be closed during accident primary conditions is closed. containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) In accordance shear isolation valve explosive charge. with the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated, In accordance automatic PCIV, except for MSIVs, is within limits. with the Inservice Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance 3 seconds and 5 seconds. with the Inservice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation In accordance position on an actual or simulated isolation signal. with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.3-7 Amendment No. 199,208 225

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.8 Verify a representative sample of reactor instrument In accordance line EFCVs actuate to the isolation position on an with the actual or simulated instrument line break signal. Surveillance Frequency Control Program SR 3.6.1.3.9 Remove and test the explosive squib from each In accordance shear isolation valve of the TIP System. with the Surveillance Frequency Control Program SR 3.6.1.3.10 Verify the combined leakage rate for all secondary In accordance containment bypass leakage paths is 0.04% with the Primary primary containment volume/day when pressurized Containment to Pa. Leakage Rate Testing Program SR 3.6.1.3.11 Verify leakage rate through each MSIV is In accordance 16.0 scfh when tested at 25.0 psig. with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify combined leakage rate through hydrostatically In accordance tested lines that penetrate the primary containment with the Primary is within limits. Containment Leakage Rate Testing Program Columbia Generating Station 3.6.1.3-8 Amendment No. 199,208 225

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°F.

APPLICABILITY: MODES 1, 2, and 3.

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

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. 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 within limit. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.4-1 Amendment No. 149,169 225

RHR Drywell Spray 3.6.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify each RHR drywell spray subsystem manual, In accordance power operated, and automatic valve in the flow with the path that is not locked, sealed, or otherwise secured Surveillance in position, is in the correct position or can be Frequency aligned to the correct position. Control Program SR 3.6.1.5.2 Verify each spray nozzle is unobstructed. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.5-2 Amendment No. 230

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two or more lines with E.1 Restore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one or more reactor breakers in two lines to building-to-suppression OPERABLE status.

chamber vacuum breakers inoperable for opening.

F. Required Action and F.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 Condition A, B AND or E not met.

F.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 breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. In accordance with the Surveillance Frequency Control Program SR 3.6.1.6.2 Perform a functional test of each vacuum breaker. In accordance with the Inservice Testing Program Columbia Generating Station 3.6.1.6-2 Amendment No. 149,169,225,236

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.3 Verify the full open setpoint of each vacuum breaker In accordance is 0.5 psid. with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.6-3 Amendment No.

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. One or more D.1 Close one open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months suppression chamber-to- breaker disk.

drywell vacuum breakers with two disks not closed.

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 of Condition C or D AND not met.

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 3.6.1.7.1 -------------------------------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 Columbia Generating Station 3.6.1.7-2 Amendment No. 169,202,225,236

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.2 Perform a functional test of each required vacuum In accordance breaker. with the Surveillance Frequency Control Program AND Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after any discharge of steam to the suppression chamber from the safety/relief valves SR 3.6.1.7.3 Verify the full open setpoint of each required In accordance vacuum breaker is 0.5 psid. with the Surveillance Frequency Control Program Columbia Generating Station 3.6.1.7-3 Amendment No.

Suppression Pool Average Temperature 3.6.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is In accordance within the applicable limits. with the Surveillance Frequency Control Program AND 5 minutes when performing testing that adds heat to the suppression pool Columbia Generating Station 3.6.2.1-3 Amendment No. 149,169 225

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 30 ft 9.75 inches and 31 ft 1.75 inches.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression pool 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within limits. 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 within limits. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.2.2-1 Amendment No. 149,169 225

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance subsystem manual, power operated, and automatic with the valve in the flow path that is not locked, sealed, or Surveillance otherwise secured in position, is in the correct Frequency position or can be aligned to the correct position. Control Program SR 3.6.2.3.2 Verify each RHR pump develops a flow rate In accordance 7100 gpm through the associated heat exchanger with the Inservice while operating in the suppression pool cooling Testing Program mode.

Columbia Generating Station 3.6.2.3-2 Amendment No. 169 225 230

Primary Containment Atmosphere Mixing System 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Primary Containment Atmosphere Mixing System LCO 3.6.3.2 Two head area return fans shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One head area return A.1 Restore head area return 30 days fan inoperable. fan to OPERABLE status.

B. Two head area return B.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months fans inoperable. means that the hydrogen and oxygen control function is maintained.

AND B.2 Restore one head area 7 days return fan to OPERABLE status.

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 not met.

Columbia Generating Station 3.6.3.2-1 Amendment No. 169,187 225

Primary Containment Atmosphere Mixing System 3.6.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Operate each head area return fan for 15 minutes. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.6.3.2-2 Amendment No.

Primary Containment Oxygen Concentration 3.6.3.3 3.6 CONTAINMENT SYSTEMS 3.6.3.3 Primary Containment Oxygen Concentration LCO 3.6.3.3 The primary containment oxygen concentration shall be < 3.5 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 the next scheduled 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 concentration to within limit.

not within 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% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.3.1 Verify primary containment oxygen concentration is In accordance within limits. with the Surveillance Frequency Control Program Columbia Generating Station 3.6.3.3-1 Amendment No. 149,169 225

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch In accordance of vacuum water gauge. with the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify all secondary containment equipment hatches In accordance are closed and sealed. with the Surveillance Frequency Control Program SR 3.6.4.1.3 Verify each secondary containment access inner In accordance door or each secondary containment access outer with the door in each access opening is closed. Surveillance Frequency Control Program SR 3.6.4.1.4 Verify each standby gas treatment (SGT) subsystem In accordance will draw down the secondary containment to with the 0.25 inch of vacuum water gauge in Surveillance 120 seconds. Frequency Control Program SR 3.6.4.1.5 Verify each SGT subsystem can maintain In accordance 0.25 inch of vacuum water gauge in the secondary with the containment for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a flow rate 2240 cfm. Surveillance Frequency Control Program Columbia Generating Station 3.6.4.1-2 Amendment No. 169,199 225

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation manual In accordance valve and blind flange that is not locked, sealed, or with the otherwise secured, and is required to be closed Surveillance during accident conditions is closed. Frequency Control Program SR 3.6.4.2.2 Verify the isolation time of each power operated, In accordance automatic SCIV is within limits. with the Inservice Testing Program SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation In accordance position on an actual or simulated automatic with the isolation signal. Surveillance Frequency Control Program Columbia Generating Station 3.6.4.2-3 Amendment No. 208 225

SGT System 3.6.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two SGT subsystems E.1 Initiate action to suspend Immediately inoperable during OPDRVs.

OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 10 continuous In accordance hours with heaters operating. with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual In accordance or simulated initiation signal. with the Surveillance Frequency Control Program SR 3.6.4.3.4 Verify each SGT filter cooling recirculation valve can In accordance be opened and the fan started. with the Surveillance Frequency Control Program Columbia Generating Station 3.6.4.3-2 Amendment No. 169,199 225

SW System and UHS 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 --------------NOTE---------------

associated Completion LCO 3.0.4.a is not Time of Condition B not applicable when entering met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Required Action and D.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 Condition A not AND met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Both SW subsystems inoperable.

OR UHS inoperable for reasons other than Condition A.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify the average water level in the UHS spray In accordance ponds is 432 feet 9 inches mean sea level. with the Surveillance Frequency Control Program SR 3.7.1.2 Verify the average water temperature of each UHS In accordance spray pond is 77°F. with the Surveillance Frequency Control Program Columbia Generating Station 3.7.1-2 Amendment No. 149,169,225,233,236

SW System and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.3 -------------------------------NOTE------------------------------

Isolation of flow to individual components does not render SW subsystem inoperable.

Verify each SW subsystem manual, power In accordance operated, and automatic valve in the flow path with the servicing safety related systems or components, Surveillance that is not locked, sealed, or otherwise secured in Frequency position, is in the correct position. Control Program SR 3.7.1.4 Verify average sediment depth in each UHS spray In accordance pond is < 0.5 ft. with the Surveillance Frequency Control Program SR 3.7.1.5 Verify each SW subsystem actuates on an actual or In accordance simulated initiation signal. with the Surveillance Frequency Control Program Columbia Generating Station 3.7.1-3 Amendment No. 149,169,225,236

HPCS SW System 3.7.2 3.7 PLANT SYSTEMS 3.7.2 High Pressure Core Spray (HPCS) Service Water (SW) System LCO 3.7.2 The HPCS SW System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. HPCS SW System A.1 Declare HPCS System Immediately inoperable. inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 -------------------------------NOTE------------------------------

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

Verify each HPCS SW System manual, power In accordance operated, and automatic valve in the flow path, that with the is not locked, sealed, or otherwise secured in Surveillance position, is in the correct position. Frequency Control Program SR 3.7.2.2 Verify the HPCS SW System actuates on an actual In accordance or simulated initiation signal. with the Surveillance Frequency Control Program Columbia Generating Station 3.7.2-1 Amendment No. 149,169 225

CREF System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREF subsystem for 10 continuous In accordance hours with the heaters operating. with the Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREF filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.7.3.3 Verify each CREF subsystem actuates on an actual In accordance or simulated initiation signal. with the Surveillance Frequency Control Program SR 3.7.3.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program Columbia Generating Station 3.7.3-3 Amendment No. 199,207 225

Control Room AC System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place OPERABLE control Immediately associated Completion room AC subsystem in Time of Condition A not operation.

met during OPDRVs.

OR D.2 Initiate action to suspend Immediately OPDRVs.

E. Required Action and E.1 Initiate action to suspend Immediately associated Completion OPDRVs.

Time of Condition B not met during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the In accordance capability to remove the assumed heat load. with the Surveillance Frequency Control Program Columbia Generating Station 3.7.4-2 Amendment No. 169,199,225,227,236

Main Condenser Offgas 3.7.5 SURVEILLANCE REQUIR5EMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 -------------------------------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 noble gases is 332 mCi/second after decay of In accordance 30 minutes. with the Surveillance 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 Columbia Generating Station 3.7.5-2 Amendment No. 149,169 225

Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are made applicable.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the requirements of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO not met. the LCO.

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 < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each main turbine In accordance bypass valve. with the Surveillance Frequency Control Program Columbia Generating Station 3.7.6-1 Amendment No. 149,169 225

Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.2 Perform a system functional test. In accordance with the Surveillance Frequency Control Program SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM In accordance RESPONSE TIME is within limits. with the Surveillance Frequency Control Program Columbia Generating Station 3.7.6-2 Amendment No.

Spent Fuel Storage Pool Water Level 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be 22 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

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

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

water level not within LCO 3.0.3 is not applicable.

limit. -------------------------------------

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water level is In accordance 22 ft over the top of irradiated fuel assemblies with the seated in the spent fuel storage pool racks. Surveillance Frequency Control Program Columbia Generating Station 3.7.7-1 Amendment No. 149,169 225

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 ---------------NOTE--------------

associated Completion LCO 3.0.4.a is not Time of Condition A, B, applicable when entering C, D, or E not met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months G. Three or more required G.1 Enter LCO 3.0.3. Immediately AC sources inoperable.

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.

Verify each required DG starts from standby In accordance with conditions and achieves steady state: the Surveillance Frequency Control

a. Voltage 3910 V and 4400 V and frequency Program 58.8 Hz and 61.2 Hz for DG-1 and DG-2; and

b. Voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz for DG-3.

Columbia Generating Station 3.8.1-5 Amendment No. 169,181,225,236

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS 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.

5. The endurance test of SR 3.8.1.14 may be performed in lieu of the load-run test in SR 3.8.1.3 provided the requirements, except the upper load limits, of SR 3.8.1.3 are met.

Verify each required DG is synchronized and loaded In accordance and operates for 60 minutes at a load 4000 kW with the and 4400 kW for DG-1 and DG-2, and 2340 kW Surveillance and 2600 kW for DG-3. Frequency Control Program SR 3.8.1.4 Verify each required day tank contains fuel oil to In accordance support greater than or equal to one hour of with the operation at full load plus 10%. Surveillance Frequency Control Program SR 3.8.1.5 Check for and remove accumulated water from each In accordance required day tank. with the Surveillance Frequency Control Program Columbia Generating Station 3.8.1-6 Amendment No. 173,215 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify each required fuel oil transfer subsystem In accordance operates to automatically transfer fuel oil from the with the storage tank to the day tank. Surveillance Frequency Control Program SR 3.8.1.7 -------------------------------NOTE------------------------------

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

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

a. For DG-1 and DG-2 in 15 seconds, voltage Frequency 3910 V and frequency 58.8 Hz, and after Control Program steady state conditions are reached, maintains voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz; and

b. For DG-3, in 15 seconds, voltage 3910 V and frequency 58.8 Hz, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz.

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

The automatic transfer function of this Surveillance shall not normally be performed in MODE 1 or 2.

However, this Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of the power In accordance supply to safety related buses from the startup with the offsite circuit to the backup offsite circuit. Surveillance Frequency Control Program Columbia Generating Station 3.8.1-7 Amendment No. 181,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.9 ------------------------------NOTES-----------------------------

1. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor as close to the power factor of the single largest post-accident load as practicable.

However, if grid conditions do not permit, the power factor limit is not required to be met.

Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each required DG rejects a load greater than In accordance or equal to its associated single largest post- with the accident load, and following load rejection, the Surveillance frequency is 66.75 Hz. Frequency Control Program SR 3.8.1.10 ------------------------------NOTES-----------------------------

1. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor of 0.9 for DG-1 and DG-2, and 0.91 for DG-3. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each required DG does not trip and voltage is In accordance maintained 4784 V during and following a load with the rejection of a load 4400 kW for DG-1 and DG-2 Surveillance and 2600 kW for DG-3. Frequency Control Program Columbia Generating Station 3.8.1-8 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.11 ------------------------------NOTES-----------------------------

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

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3 (not applicable to DG-3). However, portions of the Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power In accordance signal: with the Surveillance

a. De-energization of emergency buses; Frequency Control Program

b. Load shedding from emergency buses for Divisions 1 and 2; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 15 seconds for DG-1 and DG-2, and in 18 seconds for DG-3,

2. energizes auto-connected shutdown loads,

3. maintains steady state voltage 3910 V and 4400 V,

4. maintains steady state frequency 58.8 Hz and 61.2 Hz, and

5. supplies permanently connected and auto-connected shutdown loads for 5 minutes.

Columbia Generating Station 3.8.1-9 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.12 ------------------------------NOTES-----------------------------

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

2. This Surveillance shall not normally be performed in MODE 1 or 2 (not applicable to DG-3). However, portions of the Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Emergency Core In accordance Cooling System (ECCS) initiation signal each with the required DG auto-starts from standby condition and: Surveillance Frequency

a. For DG-1 and DG-2, in 15 seconds achieves Control Program voltage 3910 V, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V and, for DG-3, in 15 seconds achieves voltage 3910 V, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V;

b. In 15 seconds, achieves frequency 58.8 Hz and after steady state conditions are achieved, maintains frequency 58.8 Hz and 61.2 Hz;

c. Operates for 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are auto-connected to the offsite power system.

Columbia Generating Station 3.8.1-10 Amendment No. 173,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.13 -------------------------------NOTE------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify each required DG's automatic trips are In accordance bypassed on an actual or simulated ECCS initiation with the signal except: Surveillance Frequency

a. Engine overspeed; Control Program

b. Generator differential current; and

c. Incomplete starting sequence.

SR 3.8.1.14 ------------------------------NOTES-----------------------------

1. Momentary transients outside the load, excitation current, and power factor ranges do not invalidate this test.

2. Credit may be taken for unplanned events that satisfy this SR.

3. If performed with the DG synchronized with offsite power, it shall be performed at a power factor of 0.9 for DG-1 and DG-2, and 0.91 for DG-3. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each required DG operates for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: In accordance with the

a. For 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 4650 kW for DG-1 and Surveillance DG-2, and 2850 kW for DG-3; and Frequency Control Program

b. For the remaining hours of the test loaded 4400 kW for DG-1 and DG-2, and 2600 kW for DG-3.

Columbia Generating Station 3.8.1-11 Amendment No. 181,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.15 ------------------------------NOTES-----------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months loaded 4000 kW for DG-1 and DG-2, and 2340 kW for DG-3.

Momentary transients outside of load range do not invalidate this test.

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

Verify each required DG starts and achieves: In accordance with the

a. For DG-1 and DG-2, in 15 seconds, voltage Surveillance 3910 V and frequency 58.8 Hz, and after Frequency steady state conditions are reached, maintains Control Program voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz; and

b. For DG-3, in 15 seconds, voltage 3910 V and frequency 58.8 Hz, and after steady state conditions are reached, maintains voltage 3910 V and 4400 V and frequency 58.8 Hz and 61.2 Hz.

Columbia Generating Station 3.8.1-12 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.16 -------------------------------NOTE------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3 (not applicable to DG-3). However, this Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Credit may be taken for unplanned events that satisfy this SR.

Verify each required DG: In accordance with the

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

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

SR 3.8.1.17 -------------------------------NOTE------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify, with a DG operating in test mode and In accordance connected to its bus, an actual or simulated ECCS with the initiation signal overrides the test mode by: Surveillance Frequency

a. Returning DG to ready-to-load operation; and Control Program

b. Automatically energizing the emergency load from offsite power.

Columbia Generating Station 3.8.1-13 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.18 -------------------------------NOTE------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load block In accordance is within +/- 10% of design interval for each time delay with the relay. Surveillance Frequency Control Program Columbia Generating Station 3.8.1-14 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.19 ------------------------------NOTES-----------------------------

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

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3 (not applicable to DG-3). However, portions of the Surveillance may be performed to re-establish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

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

a. De-energization of emergency buses; Control Program

b. Load shedding from emergency buses for DG-1 and DG-2; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 15 seconds,

2. energizes auto-connected emergency loads,

3. maintains steady state voltage 3910 V and 4400 V,

4. maintains steady state frequency 58.8 Hz and 61.2 Hz, and

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

Columbia Generating Station 3.8.1-15 Amendment No. 203,204 225

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.20 -------------------------------NOTE------------------------------

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

Verify, when started simultaneously from standby In accordance condition, DG-1 and DG-2 achieves, in with the 15 seconds, voltage 3910 V and frequency Surveillance 58.8 Hz, and DG-3 achieves, in 15 seconds, Frequency voltage 3910 V and frequency 58.8 Hz. Control Program Columbia Generating Station 3.8.1-16 Amendment No. 204 225

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One or more DGs with E.1 Restore required starting air 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months required starting air receiver pressure to within receiver pressure: limit.

1. For DG-1 and DG-2,

< 230 psig and 150 psig; and

2. For DG-3, < 223 psig and 150 psig.

F. Required Action and F.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition A, B, C, D, or E not met.

OR One or more DGs with stored diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage subsystem contains In accordance greater than or equal to a seven day supply of fuel. with the Surveillance Frequency Control Program Columbia Generating Station 3.8.3-2 Amendment No. 169,215 225

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.2 Verify lube oil inventory is greater than or equal to a In accordance seven day supply. with the Surveillance Frequency Control Program SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program SR 3.8.3.4 Verify each required DG air start receiver pressure In accordance is: with the Surveillance

a. 230 psig for DG-1 and DG-2; and Frequency Control Program

b. 223 psig for DG-3.

SR 3.8.3.5 Check for and remove accumulated water from each In accordance fuel oil storage tank. with the Surveillance Frequency Control Program Columbia Generating Station 3.8.3-3 Amendment No. 169,215 225

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or In accordance equal to the minimum established float voltage. with the Surveillance Frequency Control Program SR 3.8.4.2 Verify each required battery charger supplies the In accordance required load for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months at: with the Surveillance

a. 126 V for the 125 V battery chargers; and Frequency Control Program

b. 252 V for the 250 V battery charger.

SR 3.8.4.3 ------------------------------NOTES-----------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not be performed in MODE 1, 2, or 3 for the Division 1 and 2 125 V DC batteries. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and In accordance maintain in OPERABLE status, the required with the emergency loads for the design duty cycle when Surveillance subjected to a battery service test. Frequency Control Program Columbia Generating Station 3.8.4-4 Amendment 169,204 225

Battery Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. One or more batteries F.1 Declare associated battery Immediately with a required battery inoperable.

parameter not met for reasons other than Condition A, B, C, D, or E.

OR Required Action and associated Completion Time of Condition A, B, C, D, or E not met.

OR One or more batteries with one or more battery cell(s) float voltage

< 2.07 V and float current > 2 amps.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 -------------------------------NOTE------------------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is 2 amps. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.8.6-3 Amendment 169,204 225

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify each battery pilot cell voltage is 2.07 V. In accordance with the Surveillance Frequency Control Program SR 3.8.6.3 Verify each battery connected cell electrolyte level is In accordance greater than or equal to minimum established with the design limits. Surveillance Frequency Control Program SR 3.8.6.4 Verify each battery pilot cell temperature is greater In accordance than or equal to minimum established design limits. with the Surveillance Frequency Control Program SR 3.8.6.5 Verify each battery connected cell voltage is In accordance 2.07 V. with the Surveillance Frequency Control Program Columbia Generating Station 3.8.6-4 Amendment 169,204 225

Battery Parameters 3.8.6 SURVEILLANCE FREQUENCY SR 3.8.6.6 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, or 3 for the Division 1 and 2 125 V DC batteries. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is 80% of the In accordance manufacturer's rating for the 125 V batteries and with the 83.4% of the manufacturer's rating for the 250 V Surveillance battery, when subjected to a performance discharge Frequency test or a modified performance discharge test. Control 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 Columbia Generating Station 3.8.6-5 Amendment

Distribution Systems - Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 ---------------NOTE--------------

associated Completion LCO 3.0.4.a is not Time of Condition A or B applicable when entering not met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Division 1 250 V DC D.1 Declare associated Immediately electrical power supported feature(s) distribution subsystem inoperable.

inoperable.

E. One or more Division 3 E.1 Declare High Pressure Immediately AC or DC electrical Core Spray System power distribution inoperable.

subsystems inoperable.

F. Two or more divisions F.1 Enter LCO 3.0.3. Immediately with inoperable electrical power distribution subsystems that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and indicated In accordance power availability to required AC and DC electrical with the power distribution subsystems. Surveillance Frequency Control Program Columbia Generating Station 3.8.7-2 Amendment No. 149,169,225,236

Distribution Systems - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and indicated In accordance power availability to required AC and DC electrical with the power distribution subsystems. Surveillance Frequency Control Program Columbia Generating Station 3.8.8-2 Amendment 169,199 225

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks associated with the refuel position shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable. associated with the inoperable interlock(s).

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

a. All-rods-in, Control Program

b. Refueling platform position,

c. Refueling platform fuel grapple fuel-loaded,

d. Refueling platform frame-mounted hoist fuel-loaded, and

e. Refueling platform trolley-mounted hoist fuel-loaded.

Columbia Generating Station 3.9.1-1 Amendment 149,169 225

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 insert Immediately 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 position. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.9.2-1 Amendment 149,169 225

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 Columbia Generating Station 3.9.2-2 Amendment

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 Columbia Generating Station 3.9.3-1 Amendment 149,169 225

Control Rod OPERABILITY - Refueling 3.9.5 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 insert Immediately control rods inoperable. 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 notch. In accordance with the Surveillance Frequency Control Program SR 3.9.5.2 Verify each withdrawn control rod scram In accordance accumulator pressure is 940 psig. with the Surveillance Frequency Control Program Columbia Generating Station 3.9.5-1 Amendment 149,169 225

RPV Water Level - Irradiated Fuel 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level - Irradiated Fuel LCO 3.9.6 RPV water level shall be 22 ft above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of Immediately within limit. irradiated fuel assemblies within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 22 ft above the top of the In accordance RPV flange. with the Surveillance Frequency Control Program Columbia Generating Station 3.9.6-1 Amendment 149,169 225

RPV Water Level - New Fuel or Control Rods 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Reactor Pressure Vessel (RPV) Water Level - New Fuel or Control Rods LCO 3.9.7 RPV water level shall be 23 ft above the top of irradiated fuel assemblies seated within the RPV.

APPLICABILITY: 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 new Immediately within limit. fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify RPV water level is 23 ft above the top of In accordance irradiated fuel assemblies seated within the RPV. with the Surveillance Frequency Control Program Columbia Generating Station 3.9.7-1 Amendment 169,199 225

RHR - High Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore one Immediately standby gas treatment subsystem to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

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 discovery cooling subsystem in circulation by an alternate of no reactor coolant operation. method. circulation 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 3.9.8.1 Verify one RHR shutdown cooling subsystem is In accordance operating. with the Surveillance Frequency Control Program Columbia Generating Station 3.9.8-2 Amendment 149,169 225

RHR - Low Water Level 3.9.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

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 discovery cooling subsystem in circulation by an alternate of no reactor coolant operation. method. circulation 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 3.9.9.1 Verify one RHR shutdown cooling subsystem is In accordance operating. with the Surveillance Frequency Control Program Columbia Generating Station 3.9.9-2 Amendment 149,169 225

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) 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 cells In accordance containing one or more fuel assemblies. with 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 Columbia Generating Station 3.10.2-2 Amendment 149,169 225

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 being withdrawn, in a five by five array centered on with the the control rod being withdrawn, are disarmed. Surveillance Frequency Control Program SR 3.10.3.3 Verify all control rods, other than the control rod In accordance being withdrawn, are fully inserted. with the Surveillance Frequency Control Program Columbia Generating Station 3.10.3-3 Amendment 149,169 225

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2 Initiate action to satisfy the Immediately requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required LCOs. According to the 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 rod In accordance being withdrawn, in a five by five array centered on with the the control rod being withdrawn, are disarmed. Surveillance Frequency Control Program SR 3.10.4.3 Verify all control rods, other than the control rod In accordance being withdrawn, are fully inserted. with 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 inserted. In accordance with the Surveillance Frequency Control Program Columbia Generating Station 3.10.4-3 Amendment 149,169 225

Single CRD Removal - Refueling 3.10.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control rod In accordance withdrawn for the removal of the associated CRD, with the are fully inserted. Surveillance Frequency Control Program SR 3.10.5.2 Verify all control rods, other than the control rod In accordance withdrawn for the removal of the associated CRD, in with the a five by five array centered on the control rod Surveillance withdrawn for the removal of the associated CRD, Frequency are disarmed. Control Program 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 SR 3.10.5.5 Verify no other CORE ALTERATIONS are in In accordance progress. with the Surveillance Frequency Control Program Columbia Generating Station 3.10.5-2 Amendment 149,169 225

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

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed from In accordance core cells associated with each control rod or CRD with the removed. Surveillance Frequency Control Program SR 3.10.6.2 Verify all other control rods in core cells containing In accordance one or more fuel assemblies are fully inserted. with the Surveillance 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 compliance with an approved spiral reload with the sequence. Surveillance Frequency Control Program Columbia Generating Station 3.10.6-2 Amendment 149,169 225

SDM Test - Refueling (After Implementation of PRNM Upgrade) 3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 compliance During control rod with the approved control rod sequence for the SDM movement 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 progress. with the Surveillance Frequency Control Program SR 3.10.8.5 Verify each withdrawn control rod does not go to the Each time 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 940 psig. with the Surveillance Frequency Control Program Columbia Generating Station 3.10.8-7 Amendment No. 169 225 226