GO2-17-124, Final Technical Specification Markup and Clean Pages for Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3

Final Technical Specification Markup and Clean Pages for Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3

ML17186A435
Person / Time
Site:	Columbia
Issue date:	07/05/2017
From:	Javorik A Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-17-124
Download: ML17186A435 (30)

Text

Alex L. Javorik Vice President, Engineering P.O. Box 968, Mail Drop PE04 Richland, WA 99352-0968 Ph. 509-377-8555 F. 509-377-2354 aljavorik@energy-northwest.com 10 CFR 50.90 10 CFR 50.55a GO2-17-124 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 FINAL TECHNICAL SPECIFICATION MARKUP AND CLEAN PAGES FOR APPLICATION TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-545, REVISION 3

Reference:

Letter A.L. Javorik, Energy Northwest to NRC, Application To Revise Technical Specifications To Adopt TSTF-545, Revision 3, GO2-16-076, (ADAMS Accession No. ML16196A419), Dated July 14, 2016.

Dear Sir or Madam:

By the referenced letter, Energy Northwest submitted for approval the License Amendment Request (LAR) to adopt TSTF-545, Revision 3.

This letter transmits the final markup and clean pages of the Technical Specifications (TS) for the LAR referenced above. 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. 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 Significant 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 you should have any questions regarding this submittal, please contact Ms. L. L.

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

July 5, 2017

G02-17-124 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on this 5 ~/,_ day of ~0,

2017.

Respectfully, A. L. Jav nk Vice President, Engineering Attachments: As stated cc:

NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPA - 1399 (w/o enclosures)

WA Horin - Winston & Strawn (email)

RR Cowley-WDOH (email)

EFSECutc.wa.gov-- EFSEC (email)

GO2-17-124 TECHNICAL SPECIFICATIONS CHANGES (MARK-UPS)

Definitions 1.1 Columbia Generating Station 1.1-3 Amendment No. 149,169 225 1.1 Definitions END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that time RECIRCULATION PUMP interval from initial signal generation by the associated turbine TRIP (EOC-RPT) SYSTEM throttle valve limit switch or from when the turbine governor RESPONSE TIME valve hydraulic control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a.

Identified LEAKAGE 1.

LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or 2.

LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b.

Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c.

Total LEAKAGE Sum of the identified and unidentified LEAKAGE; and d.

Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

SLC System 3.1.7 Columbia Generating Station 3.1.7-3 Amendment No. 199,221 225 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each pump develops a flow rate 41.2 gpm at a discharge pressure 1220 psig.

In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM SR 3.1.7.7 Verify flow through one SLC subsystem from pump into reactor pressure vessel.

In accordance with the Surveillance Frequency Control Program SR 3.1.7.8 Verify all heat traced piping between storage tank and pump suction valve is unblocked.

In accordance with the Surveillance Frequency Control Program AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 atom percent B-10.

Prior to addition to SLC Tank

SRVs - 25% RTP 3.4.3 Columbia Generating Station 3.4.3-1 Amendment No. 149,169 225 238, 240 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 SRVs inoperable.

A.1 Reduce THERMAL POWER to < 25% RTP.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 + 34.9

- 58.2 4

1175 + 35.2

- 58.7 4

1185 + 35.5

- 59.2 4

1195 + 35.8

- 59.7 4

1205 +/- 36.1

- 60.2 Following testing, lift settings shall be within +3%.

In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM

SRVs - < 25% RTP 3.4.4 Columbia Generating Station 3.4.4-2 Amendment No. 149,169,225,236,238,240 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 + 34.9

- 58.2 4

1175 + 35.2

- 58.7 4

1185 + 35.5

- 59.2 4

1195 + 35.8

- 59.7 4

1205 +/- 36.1

- 60.2 Following testing, lift settings shall be within +3%.

In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM SR 3.4.4.2

---

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

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

Verify each required SRV opens when manually actuated.

In accordance with the Surveillance Frequency Control Program

RCS PIV Leakage 3.4.6 Columbia Generating Station 3.4.6-2 Amendment No. 149,169 225 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1

---

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

Only required to be performed in MODES 1 and 2.

Verify equivalent leakage of each RCS PIV is 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at an RCS pressure of 1035 psig. The actual test pressure shall be 935 psig.

In accordance withInservice Testing Program the INSERVICE TESTING PROGRAM

ECCS - Operating 3.5.1 Columbia Generating Station 3.5.1-4 Amendment No. 169,205,225,229,236 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

In accordance with 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 manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.3 Verify ADS accumulator backup compressed gas system average pressure in the required bottles is 2200 psig.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.4 Verify each ECCS pump develops the specified flow rate with the specified differential pressure between reactor and suction source.

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 In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM

ECCS - Shutdown 3.5.2 Columbia Generating Station 3.5.2-3 Amendment No. 169,205 225 229 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for each required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

In accordance with the 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 subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.5 Verify each required ECCS pump develops the specified flow rate with the specified differential pressure between reactor and suction source.

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 In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM

PCIVs 3.6.1.3 Columbia Generating Station 3.6.1.3-7 Amendment No. 199,208 225 238 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 valve and blind flange that is located inside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

Prior to entering MODE 2 or 3 from MODE 4 if primary 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) shear isolation valve explosive charge.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated, automatic PCIV, except for MSIVs, is within limits.

In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 5 seconds.

In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM

PCIVs 3.6.1.3 Columbia Generating Station 3.6.1.3-8 Amendment No. 199,208 225 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.8 Verify a representative sample of reactor instrument line EFCVs actuate to the isolation position on an actual or simulated instrument line break signal.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.9 Remove and test the explosive squib from each shear isolation valve of the TIP System.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.10 Verify the combined leakage rate for all secondary containment bypass leakage paths is 0.04%

primary containment volume/day when pressurized to Pa.

In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.11 Verify leakage rate through each MSIV is 16.0 scfh when tested at 25.0 psig.

In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify combined leakage rate through hydrostatically tested lines that penetrate the primary containment is within limits.

In accordance with the Primary Containment Leakage Rate Testing Program

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 Columbia Generating Station 3.6.1.6-2 Amendment No. 149,169,225,236 238 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two or more lines with one or more reactor building-to-suppression chamber vacuum breakers inoperable for opening.

E.1 Restore all vacuum breakers in two lines to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> F. Required Action and associated Completion Time of Condition A, B or E not met.

F.1 Be in MODE 3.

AND F.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours 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 INSERVICE TESTING PROGRAM

RHR Suppression Pool Cooling 3.6.2.3 Columbia Generating Station 3.6.2.3-2 Amendment No. 169 225 230 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.6.2.3.2 Verify each RHR pump develops a flow rate 7100 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.

In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM

SCIVs 3.6.4.2 Columbia Generating Station 3.6.4.2-3 Amendment No. 208 225 238 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 valve and blind flange that is not locked, sealed, or otherwise secured, and is required to be closed during accident conditions is closed.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.2.2 Verify the isolation time of each power operated, automatic SCIV is within limits.

In accordance with the Inservice Testing Program INSERVICE TESTING PROGRAM SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation position on an actual or simulated automatic isolation signal.

In accordance with the Surveillance Frequency Control Program

Programs and Manuals 5.5 Columbia Generating Station 5.5-4 Amendment 182,205 225 5.5 Programs and Manuals 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Table 3.9-1, Note 1, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 DeletedInservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves.

a.

Testing Frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:

ASME OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days b.

The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities; c.

The provisions of SR 3.0.3 are applicable to inservice testing activities; and d.

Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

GO2-17-124 TECHNICAL SPECIFICATIONS CLEAN PAGES

Definitions 1.1 Columbia Generating Station 1.1-3 Amendment No. 149,169 225 1.1 Definitions END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that time RECIRCULATION PUMP interval from initial signal generation by the associated turbine TRIP (EOC-RPT) SYSTEM throttle valve limit switch or from when the turbine governor RESPONSE TIME valve hydraulic control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a.

Identified LEAKAGE

1.

LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2.

LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b.

Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c.

Total LEAKAGE Sum of the identified and unidentified LEAKAGE; and

d.

Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

SLC System 3.1.7 Columbia Generating Station 3.1.7-3 Amendment No. 199,221 225 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each pump develops a flow rate 41.2 gpm at a discharge pressure 1220 psig.

In accordance with the INSERVICE TESTING PROGRAM SR 3.1.7.7 Verify flow through one SLC subsystem from pump into reactor pressure vessel.

In accordance with the Surveillance Frequency Control Program SR 3.1.7.8 Verify all heat traced piping between storage tank and pump suction valve is unblocked.

In accordance with the Surveillance Frequency Control Program AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 atom percent B-10.

Prior to addition to SLC Tank

SRVs - 25% RTP 3.4.3 Columbia Generating Station 3.4.3-1 Amendment No. 149,169 225 238, 240 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 SRVs inoperable.

A.1 Reduce THERMAL POWER to < 25% RTP.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 + 34.9

- 58.2 4

1175 + 35.2

- 58.7 4

1185 + 35.5

- 59.2 4

1195 + 35.8

- 59.7 4

1205 +/- 36.1

- 60.2 Following testing, lift settings shall be within +3%.

In accordance with the INSERVICE TESTING PROGRAM

SRVs - < 25% RTP 3.4.4 Columbia Generating Station 3.4.4-2 Amendment No. 149,169,225,236,238,240 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 + 34.9

- 58.2 4

1175 + 35.2

- 58.7 4

1185 + 35.5

- 59.2 4

1195 + 35.8

- 59.7 4

1205 +/- 36.1

- 60.2 Following testing, lift settings shall be within +3%.

In accordance with the INSERVICE TESTING PROGRAM SR 3.4.4.2

---

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

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

Verify each required SRV opens when manually actuated.

In accordance with the Surveillance Frequency Control Program

RCS PIV Leakage 3.4.6 Columbia Generating Station 3.4.6-2 Amendment No. 149,169 225 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1

---

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

Only required to be performed in MODES 1 and 2.

Verify equivalent leakage of each RCS PIV is 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at an RCS pressure of 1035 psig. The actual test pressure shall be 935 psig.

In accordance with the INSERVICE TESTING PROGRAM

ECCS - Operating 3.5.1 Columbia Generating Station 3.5.1-4 Amendment No. 169,205,225,229,236 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

In accordance with 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 manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.3 Verify ADS accumulator backup compressed gas system average pressure in the required bottles is 2200 psig.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.4 Verify each ECCS pump develops the specified flow rate with the specified differential pressure between reactor and suction source.

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 In accordance with the INSERVICE TESTING PROGRAM

ECCS - Shutdown 3.5.2 Columbia Generating Station 3.5.2-3 Amendment No. 169,205 225 229 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for each required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

In accordance with the 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 subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.5 Verify each required ECCS pump develops the specified flow rate with the specified differential pressure between reactor and suction source.

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 In accordance with the INSERVICE TESTING PROGRAM

PCIVs 3.6.1.3 Columbia Generating Station 3.6.1.3-7 Amendment No. 199,208 225 238 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 valve and blind flange that is located inside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

Prior to entering MODE 2 or 3 from MODE 4 if primary 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) shear isolation valve explosive charge.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated, automatic PCIV, except for MSIVs, is within limits.

In accordance with the INSERVICE TESTING PROGRAM SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 5 seconds.

In accordance with the INSERVICE TESTING PROGRAM

PCIVs 3.6.1.3 Columbia Generating Station 3.6.1.3-8 Amendment No. 199,208 225 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.8 Verify a representative sample of reactor instrument line EFCVs actuate to the isolation position on an actual or simulated instrument line break signal.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.9 Remove and test the explosive squib from each shear isolation valve of the TIP System.

In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.10 Verify the combined leakage rate for all secondary containment bypass leakage paths is 0.04%

primary containment volume/day when pressurized to Pa.

In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.11 Verify leakage rate through each MSIV is 16.0 scfh when tested at 25.0 psig.

In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify combined leakage rate through hydrostatically tested lines that penetrate the primary containment is within limits.

In accordance with the Primary Containment Leakage Rate Testing Program

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 Columbia Generating Station 3.6.1.6-2 Amendment No. 149,169,225,236 238 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two or more lines with one or more reactor building-to-suppression chamber vacuum breakers inoperable for opening.

E.1 Restore all vacuum breakers in two lines to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> F. Required Action and associated Completion Time of Condition A, B or E not met.

F.1 Be in MODE 3.

AND F.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1

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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

RHR Suppression Pool Cooling 3.6.2.3 Columbia Generating Station 3.6.2.3-2 Amendment No. 169 225 230 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.6.2.3.2 Verify each RHR pump develops a flow rate 7100 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.

In accordance with the INSERVICE TESTING PROGRAM

SCIVs 3.6.4.2 Columbia Generating Station 3.6.4.2-3 Amendment No. 208 225 238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1

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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 valve and blind flange that is not locked, sealed, or otherwise secured, and is required to be closed during accident conditions is closed.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.2.2 Verify the isolation time of each power operated, automatic SCIV is within limits.

In accordance with the INSERVICE TESTING PROGRAM SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation position on an actual or simulated automatic isolation signal.

In accordance with the Surveillance Frequency Control Program

Programs and Manuals 5.5 Columbia Generating Station 5.5-4 Amendment 182,205 225 5.5 Programs and Manuals 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Table 3.9-1, Note 1, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Deleted