Text

Tech Spec Pages for Amendment No. 177, Revise TS 3.3.2, ESFAS and TS 3.7.3, Main Feedwater Isolation Valves by Addition of Main Feedwater Regulating Valves and Associated Bypass Valves
	ML080370121
Person / Time
Site:	Wolf Creek
Issue date:	04/03/2008
From:	; NRC/NRR/ADRO/DORL/LPLIV
To:	;
	Donohew J N, NRR/DORL/LPL4, 415-1307
Shared Package
ML080370111	List: ML080370117; ML080370121;
References
	TAC MD4840
	Download: ML080370121 (42)
	v • d • e

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No., and the Environmental Protection Plan l

contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Antitrust Conditions Kansas Gas & Electric Company and Kansas City Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.

(4)

Environmental Qualification (Section 3.11, SSER #4, Section 3.11, SSER #5)*

Deleted per Amendment No. 141.

(5)

Fire Protection (Section 9.5.1, SER, Section 9.5.1.8, SSER #5)

(a)

The Operating Corporation shall maintain in effect all provisions of the approved fire protection program as described in the SNUPPs Final Safety Analysis Report for the facility through Revision 17, the Wolf Creek site addendum through Revision 15, and as approved in the SER through Supplement 5, subject to provisions b and c below.

(b)

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(c)

Deleted.

(6)

Qualification of Personnel (Section 13.1.2, SSER #5, Section 18, SSER

1)

Deleted per Amendment No. 141.

The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment No.

177 177

Wolf Creek - Unit 1 iii Amendment No. 123, 132, 134, 163, 171, 177 TABLE OF CONTENTS 3.7 PLANT SYSTEMS.................................................................................... 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs)................................................ 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs).............................................. 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves............ 3.7-8 3.7.4 Atmospheric Relief Valves (ARVs)................................................... 3.7-12 3.7.5 Auxiliary Feedwater (AFW) System.................................................. 3.7-14 3.7.6 Condensate Storage Tank (CST)..................................................... 3.7-17 3.7.7 Component Cooling Water (CCW) System...................................... 3.7-19 3.7.8 Essential Service Water System (ESW)........................................... 3.7-21 3.7.9 Ultimate Heat Sink (UHS)................................................................. 3.7-23 3.7.10 Control Room Emergency Ventilation System (CREVS)................. 3.7-25 3.7.11 Control Room Air Conditioning System (CRACS)............................ 3.7-28 3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System - Not Used................................................. 3.7-31 3.7.13 Emergency Exhaust System (EES).................................................. 3.7-32 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS) -

Not Used..................................................................................... 3.7-36 3.7.15 Fuel Storage Pool Water Level......................................................... 3.7-37 3.7.16 Fuel Storage Pool Boron Concentration........................................... 3.7-38 3.7.17 Spent Fuel Assembly Storage.......................................................... 3.7-40 3.7.18 Secondary Specific Activity............................................................... 3.7-42 3.8 ELECTRICAL POWER SYSTEMS........................................................... 3.8-1 3.8.1 AC Sources - Operating.................................................................... 3.8-1 3.8.2 AC Sources - Shutdown.................................................................... 3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air........................................ 3.8-21 3.8.4 DC Sources - Operating.................................................................... 3.8-24 3.8.5 DC Sources - Shutdown................................................................... 3.8-28 3.8.6 Battery Cell Parameters.................................................................... 3.8-30 3.8.7 Inverters - Operating......................................................................... 3.8-34 3.8.8 Inverters - Shutdown......................................................................... 3.8-35 3.8.9 Distribution Systems - Operating...................................................... 3.8-37 3.8.10 Distribution Systems - Shutdown...................................................... 3.8-39 3.9 REFUELING OPERATIONS..................................................................... 3.9-1 3.9.1 Boron Concentration......................................................................... 3.9-1 3.9.2 Unborated Water Source Isolation Valves....................................... 3.9-2 3.9.3 Nuclear Instrumentation.................................................................... 3.9-3 3.9.4 Containment Penetrations................................................................ 3.9-5 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level.................................................... 3.9-7 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level...................................................... 3.9-9

Wolf Creek - UnIt 1 iv Amendment No. 123, 142, 158, 164 TABLE OF CONTENTS 3.9 REFUELING OPERATIONS (continued) 3.9.7 Refueling Pool Water Level...................................................................... 3.9-11 4.0 DESIGN FEATURES........................................................................................ 4.0-1 4.1 Site Location............................................................................................ 4.0-1 4.2 Reactor Core............................................................................................. 4.0-1 4.3 Fuel Storage.............................................................................................. 4.0-1 5.0 ADMINISTRATIVE CONTROLS...................................................................... 5.0-1 5.1 Responsibility............................................................................................ 5.0-1 5.2 Organization.............................................................................................. 5.0-2 5.3 Unit Staff Qualifications............................................................................. 5.0-4 5.4 Procedures................................................................................................ 5.0-5 5.5 Programs and Manuals............................................................................. 5.0-6 5.6 Reporting Requirements........................................................................... 5.0-22 5.7 High Radiation Area.................................................................................. 5.0-27

ESFAS Instrumentation 3.3.2 Wolf Creek - Unit 1 3.3-34 Amendment No. 123, 132, 175, 177 Table 3.3.2-1 (page 3 of 5)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE (a)

4.

Steam Line Isolation (continued)

e.

Steam Line Pressure (1) Low 1,2(i),3(b)(i) 3 per steam line D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 t 571 psig(c)

(2) Negative Rate -

High 3(g)(i) 3 per steam line D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 d 125(h) psi

5.

Turbine Trip and Feedwater Isolation

a.

Automatic Actuation Logic and Actuation Relays (SSPS) 1,2(j),3(j) 2 trains G

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 SR 3.3.2.14 NA

b.

Automatic Actuation Logic (MSFIS) 1,2(k),3(k) 2 trains G

SR 3.3.2.6 NA

c.

SG Water Level -High High (P-14) 1,2(j) 4 per SG I

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 d 79.7% of Narrow Range Instrument Span

d.

Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(continued)

(a) The Allowable Value defines the Limiting Safety System Setting. See the Bases for the Trip Setpoints.

(b) Above the P-11 (Pressurizer Pressure) Interlock and below P-11 unless the Function is blocked.

(c) Time constants used in the lead/lag controller are t1 t 50 seconds and t2 d 5 seconds.

(g) Below the P-11 (Pressurizer Pressure) Interlock; however, may be blocked below P-11 when safety injection on low steam line pressure is not blocked.

(h) Time constant utilized in the rate/lag controller is t 50 seconds.

(i) Except when all MSIVs are closed.

(j) Except when all MFIVs are closed and de-activated; and all MFRVs are closed and de-activated or closed and isolated by a closed manual valve; and all MFRV bypass valves are closed and de-activated, or closed and isolated by a closed manual valve, or isolated by two closed manual valves.

(k) Except when all MFIVs are closed and de-activated.

ESFAS Instrumentation 3.3.2 Wolf Creek - Unit 1 3.3-35 Amendment No. 123, 136 Table 3.3.2-1 (page 4 of 5)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE (a)

6.

Auxiliary Feedwater a.

Manual Initiation 1,2,3 1 per pump O

SR 3.3.2.8 NA b.

Automatic Actuation Logic and Actuation Relays (Solid State Protection System) 1,2,3 2 trains G

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA c.

Automatic Actuation Logic and Actuation Relays (Balance of Plant ESFAS) 1,2,3 2 trains N

SR 3.3.2.3 NA d.

SG Water Level Low -

Low 1,2,3 4 per SG D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 22.3% of Narrow Range Instrument Span e.

Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

f.

Loss of Offsite Power 1,2,3 2 trains P

SR 3.3.2.7 SR 3.3.2.10 NA g.

Trip of all Main Feedwater Pumps 1

2 per pump J

SR 3.3.2.8 NA

h.

Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low 1,2,3 3

M SR 3.3.2.1 SR 3.3.2.9 SR 3.3.2.10 SR 3.3.2.12 20.53 psia (continued)

(a)

The Allowable Value defines the Limiting Safety System Setting. See the Bases for the Trip Setpoints.

MSIVs 3.7.2 Wolf Creek - Unit 1 3.7-7 Amendment No. 123, 171, 174 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1

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

Only required to be performed in MODES 1 and 2.

Verify the isolation time of each MSIV is within limits.

In accordance with the Inservice Testing Program SR 3.7.2.2

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

Only required to be performed in MODES 1 and 2.

Verify each actuator train actuates the MSIV to the isolation position on an actual or simulated actuation signal.

18 months

MFIVs and MFRVs and MFRV Bypass Valves 3.7.3 Wolf Creek - Unit 1 3.7-8 Amendment No. 123, 171, 177 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves LCO 3.7.3 Each MFIV and its associated actuator trains, MFRV and MFRV bypass valve for the four main feedwater lines shall be OPERABLE.

APPLICABILITY:

MODE 1 MODES 2 and 3, except for each affected main feedwater line when:

a.

The MFIS is closed and deactivated; or

b.

The MFRV is closed and deactivated or closed and isolated by a closed manual valve; and the MFRV bypass valve is either closed and deactivated, closed and isolated by a closed manual valve, or isolated by two closed manual valves.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One MFIV actuator train inoperable.

A.1 Restore MFIV actuator train to OPERABLE status.

7 days B.

Two MFIV actuator trains inoperable for different MFIVs when the inoperable actuator trains are not in the same separation group.

B.1 Restore one MFIV actuator train to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C.

Two MFIV actuator trains inoperable when the inoperable actuator trains are in the same separation group.

C.1 Restore one MFIV actuator train to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

MFIVs and MFRVs and MFRV Bypass Valves 3.7.3 Wolf Creek - Unit 1 3.7-9 Amendment No. 123, 171, 174, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Two actuator trains for one MFIV inoperable.

D.1 Declare the affected MFIV inoperable.

Immediately E.

Three or more MFIV actuator trains inoperable.

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

E.1 Declare each affected MFIV inoperable.

Immediately F.

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

Separate Condition entry is allowed for each MFIV.

One or more MFIVs inoperable.

F.1 Close MFIV.

AND F.2 Verify MFIV is closed.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Once per 7 days G.

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

Separate Condition entry is allowed for each MFRV.

One or more MFRVs inoperable.

G.1 Close or isolate MFRV.

AND G.2 Verify MFRV is closed or isolated.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Once per 7 days (continued)

MFIVs and MFRVs and MFRV Bypass Valves 3.7.3 Wolf Creek - Unit 1 3.7-10 Amendment No. 123, 171, 174, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

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

Separate Condition entry is allowed for each MFRV bypass valve.

One or more MFRV bypass valves is inoperable.

H.1 Close or isolate MFRV bypass valve.

AND H.2 Verify MFRV bypass valve is closed or isolated.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Once per 7 days I.

Two valves in the same flow path inoperable.

I.1 Isolate affected flow path.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months J.

Required Action and associated Completion Time of Condition F, G, H, or I not met.

J.1 Be in MODE 3.

AND J.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1

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

Only required to be performed in MODES 1 and 2.

Verify the isolation time of each MFIV, MFRV and MFRV bypass valve is within limits.

In accordance with the Inservice Testing Program (continued)

MFIVs and MFRVs and MFRV Bypass Valves 3.7.3 Wolf Creek - Unit 1 3.7-11 Amendment No. 123, 171, 177 SURVEILLANCE REQUIRMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.3.2

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

Only required to be performed in MODES 1 and 2.

Verify each actuator train actuates the MFIV to the isolation position on an actual or simulated actuation signal.

18 months SR 3.7.3.2

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

Only required to be performed in MODES 1 and 2.

Verify each MFRV and MFRV bypass valve actuates to the isolation position on an actual or simulated actuation signal.

18 months

ARVs 3.7.4 Wolf Creek - Unit 1 3.7-12 Amendment No. 123, 127, 155, 171, 177 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Relief Valves (ARVs)

LCO 3.7.4 Four ARV lines shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One ARV line inoperable for reasons other than excessive leakage.

A.1 Restore required ARV line to OPERABLE status.

7 days B.

Two ARV lines inoperable for reasons other than excessive leakage.

B.1 Restore all but one required ARV line to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C.

Three or more ARV lines inoperable for reasons other than excessive leakage.

C.1 Restore all but two ARV lines to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

ARVs 3.7.4 Wolf Creek - Unit 1 3.7-13 Amendment No. 123, 127, 155, 171, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

With one or more of the ARVs inoperable because of excessive seat leakage.

D.1 Initiate action to close the associated block valve(s).

AND D.2 Restore ARV(s) to OPERABLE staus.

Immediately 30 days E.

Required Action and associated Completion Time not met.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ARV.

In accordance with the Inservice Testing Program SR 3.7.4.2 Verify one complete cycle of each ARV block valve.

18 months

AFW System 3.7.5 Wolf Creek - Unit 1 3.7-14 Amendment No. 123, 155, 171, 177 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS

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

LCO 3.0.4b. is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One steam supply to turbine driven AFW pump inoperable.

A.1 Restore steam supply to OPERABLE status.

7 days AND 10 days from discovery of failure to meet the LCO B.

One AFW train inoperable for reasons other than Condition A.

B.1 Restore AFW train to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 10 days from discovery of failure to meet the LCO (continued)

AFW System 3.7.5 Wolf Creek - Unit 1 3.7-15 Amendment No. 123, 171, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and associated Completion Time for Condition A or B not met.

OR Two AFW trains inoperable.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours D.

Three AFW trains inoperable.

D.1

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

LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore one AFW train to OPERABLE status.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1

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

Not required to be performed for the AFW flow control valves until the system is placed in standby or THERMAL POWER is > 10% RTP.

Verify each AFW manual, power operated, and automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days (continued)

AFW System 3.7.5 Wolf Creek - Unit 1 3.7-16 Amendment No. 123, 171, 177 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.2

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

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after t 900 psig in the steam generator.

Verify the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head.

In accordance with the Inservice Test Program SR 3.7.5.3 Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

18 months SR 3.7.5.4

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

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after t 900 psig in the steam generator.

Verify each AFW pump starts automatically on an actual or simulated actuation signal.

18 months SR 3.7.5.5 Verify proper alignment of the required AFW flow paths by verifying flow from the condensate storage tank to each steam generator.

Prior to entering MODE 2 whenever unit has been in MODE 5 or 6 for > 30 days

CST 3.7.6 Wolf Creek - Unit 1 3.7-17 Amendment No. 123, 171, 177 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST)

LCO 3.7.6 The CST contained water volume shall be t 281,000 gal.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

CST contained water volume not within limit.

A.1 Verify by administrative means OPERABILITY of backup water supply.

AND A.2 Restore CST contained water volume to within limit.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter 7 days B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours

CST 3.7.6 Wolf Creek - Unit 1 3.7-18 Amendment No. 123, 171, 177 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST contained water volume is t 281,000 gal.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

CCW System 3.7.7 Wolf Creek - Unit 1 3.7-19 Amendment No. 123, 171, 177 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One CCW train inoperable.

A.1

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

Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops - MODE 4,"

for residual heat removal loops made inoperable by CCW.

Restore CCW train to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours

CCW System 3.7.7 Wolf Creek - Unit 1 3.7-20 Amendment No. 123, 171, 177 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1

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

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

Verify each CCW manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days SR 3.7.7.2 Verify each CCW automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

18 months SR 3.7.7.3 Verify each CCW pump starts automatically on an actual or simulated actuation signal.

18 months

ESW System 3.7.8 Wolf Creek - Unit 1 3.7-21 Amendment No. 123, 171, 177 3.7 PLANT SYSTEMS 3.7.8 Essential Service Water (ESW) System LCO 3.7.8 Two ESW trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One ESW train inoperable.

A.1

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

1.

Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating,"

for emergency diesel generator made inoperable by ESW System.

2.

Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops - MODE 4," for residual heat removal loops made inoperable by ESW System.

Restore ESW train to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

ESW System 3.7.8 Wolf Creek - Unit 1 3.7-22 Amendment No. 123, 171, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1

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

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

Verify each ESW manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days SR 3.7.8.2 Verify each ESW automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

18 months SR 3.7.8.3 Verify each ESW pump starts automatically on an actual or simulated actuation signal.

18 months

UHS 3.7.9 Wolf Creek - Unit 1 3.7-23 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Plant inlet water temperature of UHS not within limit.

A.1 Verify water level of main cooling lake t 1075 ft.

mean sea level.

AND A.2 Verify plant inlet water temperature of UHS is d 94qF.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour B.

Required Action and associated Completion Time not met.

OR UHS inoperable for reasons other than Condition A.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours

UHS 3.7.9 Wolf Creek - Unit 1 3.7-24 Amendment No. 123, 134, 171, 177 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is t 1070 ft mean sea level.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.7.9.2 Verify plant inlet water temperature of UHS is d 90qF.

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

CREVS 3.7.10 Wolf Creek - Unit 1 3.7-25 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Ventilation System (CREVS)

LCO 3.7.10 Two CREVS trains shall be OPERABLE.

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

The control room boundary may be opened intermittently under administrative controls.

APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One CREVS train inoperable.

A.1 Restore CREVS train to OPERABLE status.

7 days B.

Two CREVS trains inoperable due to inoperable control room boundary in MODES 1, 2, 3, and 4.

B.1 Restore control room boundary to OPERABLE status.

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

Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, 3, or 4.

C.1 Be in MODE 3.

AND C.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours (continued)

CREVS 3.7.10 Wolf Creek - Unit 1 3.7-26 Amendment No. 123, 131, 134, 171, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.

D.1.1 Place OPERABLE CREVS train in CRVIS mode.

AND D.1.2 Verify OPERABLE CREVS train is capable of being powered by an emergency power source.

OR D.2.1 Suspend CORE ALTERATIONS.

AND D.2.2 Suspend movement of irradiated fuel assemblies.

Immediately Immediately Immediately Immediately E. Two CREVS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.

E.1 Suspend CORE ALTERATIONS.

AND E.2 Suspend movement of irradiated fuel assemblies.

Immediately Immediately F.

Two CREVS trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

F.1 Enter LCO 3.0.3.

Immediately

CREVS 3.7.10 Wolf Creek - Unit 1 3.7-27 Amendment No. 123, 134, 171, 177 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train pressurization filter unit for t 10 continuous hours with the heaters operating and each CREVS train filtration filter unit for t 15 minutes.

31 days SR 3.7.10.2 Perform required CREVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or simulated actuation signal.

18 months SR 3.7.10.4 Verify one CREVS train can maintain a positive pressure of t 0.25 inches water gauge, relative to the outside atmosphere during the CRVIS mode of operation.

18 months on a STAGGERED TEST BASIS

CRACS 3.7.11 Wolf Creek - Unit 1 3.7-28 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning System (CRACS)

LCO 3.7.11 Two CRACS trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One CRACS train inoperable.

A.1 Restore CRACS train to OPERABLE status.

30 days B.

Required Action and associated Completion Time of Condition A not met in MODE 1, 2, 3, or 4.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours (continued)

CRACS 3.7.11 Wolf Creek - Unit 1 3.7-29 Amendment No. 123, 134, 171, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.

C.1.1 Place OPERABLE CRACS train in operation.

AND C.1.2 Verify OPERABLE CRACS train is capable of being powered by an emergency power source.

OR C.2.1 Suspend CORE ALTERATIONS.

AND C.2.2 Suspend movement of irradiated fuel assemblies.

Immediately Immediately Immediately Immediately D.

Two CRACS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.

D.1 Suspend CORE ALTERATIONS.

AND D.2 Suspend movement of irradiated fuel assemblies.

Immediately Immediately E.

Two CRACS trains inoperable in MODE 1, 2, 3, or 4.

E.1 Enter LCO 3.0.3.

Immediately

CRACS 3.7.11 Wolf Creek - Unit 1 3.7-30 Amendment No. 123, 134, 171, 177 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CRACS train has the capability to remove the assumed heat load.

18 months

Wolf Creek - Unit 1 3.7-31 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System (PREACS)

NOT USED

EES 3.7.13 Wolf Creek - Unit 1 3.7-32 Amendment No. 123, 132, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.13 Emergency Exhaust System (EES)

LCO 3.7.13 Two EES trains shall be OPERABLE.

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

The auxiliary building or fuel building boundary may be opened intermittently under administrative controls.

APPLICABILITY:

MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies in the fuel building.

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

The SIS mode of operation is required only in MODES 1, 2, 3, and 4. The FBVIS mode of operation is required only during movement of irradiated fuel assemblies in the fuel building.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One EES train inoperable in MODE 1, 2, 3, or 4.

A.1 Restore EES train to OPERABLE status.

7 days B.

Two EES trains inoperable due to inoperable auxiliary building boundary in MODE 1, 2, 3, or 4.

B.1 Restore auxiliary building boundary to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

EES 3.7.13 Wolf Creek - Unit 1 3.7-33 Amendment No. 123, 132, 134, 171, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, 3, or 4.

OR Two EES trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

C.1 Be in MODE 3.

AND C.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours D.

One EES train inoperable during movement of irradiated fuel assemblies in the fuel building.

D.1 Place OPERABLE EES train in operation in FBVIS mode.

OR D.2 Suspend movement of irradiated fuel assemblies in the fuel building.

Immediately Immediately E.

Two EES trains inoperable due to inoperable fuel building boundary during movement of irradiated fuel assemblies in the fuel building.

E.1 Restore fuel building boundary to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

EES 3.7.13 Wolf Creek - Unit 1 3.7-34 Amendment No. 123, 132, 134, 171, 177 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

Required Action and associated Completion Time of Condition E not met.

OR Two EES trains inoperable during movement of irradiated fuel assemblies in the fuel building for reasons other than Condition E.

F.1 Suspend movement of irradiated fuel assemblies in the fuel building.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each EES train for t 10 continuous hours with the heaters operating.

31 days SR 3.7.13.2 Perform required EES filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.13.3 Verify each EES train actuates on an actual or simulated actuation signal.

18 months (continued)

EES 3.7.13 Wolf Creek - Unit 1 3.7-35 Amendment No. 123, 132, 134, 171, 177 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.13.4 Verify one EES train can maintain a negative pressure t 0.25 inches water gauge with respect to atmospheric pressure in the auxiliary building during the SIS mode of operation.

18 months on a STAGGERED TEST BASIS SR 3.7.13.5 Verify one EES train can maintain a negative pressure t 0.25 inches water gauge with respect to atmospheric pressure in the fuel building during the FBVIS mode of operation.

18 months on a STAGGERED TEST BASIS

Wolf Creek - Unit 1 3.7-36 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS)

NOT USED

Fuel Storage Pool Water Level 3.7.15 Wolf Creek - Unit 1 3.7-37 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.15 Fuel Storage Pool Water Level LCO 3.7.15 The fuel storage pool water level shall be t 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY:

During movement of irradiated fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool water level not within limit.

A.1

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

LCO 3.0.3 is not applicable.

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

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the fuel storage pool water level is t 23 ft above the top of the irradiated fuel assemblies seated in the storage racks.

7 days

Fuel Storage Pool Boron Concentration 3.7.16 Wolf Creek - Unit 1 3.7-38 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Boron Concentration LCO 3.7.16 The fuel storage pool boron concentration shall be t 2165 ppm.

APPLICABILITY:

When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool boron concentration not within limit.

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

LCO 3.0.3 is not applicable.

A.1 Suspend movement of fuel assemblies in the fuel storage pool.

AND A.2.1 Initiate action to restore fuel storage pool boron concentration to within limit.

OR A.2.2 Verify by administrative means that a non-Region 1 fuel storage pool verification has been performed since the last movement of fuel assemblies in the fuel storage pool.

Immediately Immediately Immediately

Fuel Storage Pool Boron Concentration 3.7.16 Wolf Creek - Unit 1 3.7-39 Amendment No. 123, 134, 171, 177 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool boron concentration is within limit.

7 days

Spent Fuel Assembly Storage 3.7.17 Wolf Creek - Unit 1 3.7-40 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.17 Spent Fuel Assembly Storage LCO 3.7.17 The combination of initial enrichment and burnup of each spent fuel assembly stored in Region 2 or 3 shall be within the Acceptable Domain of Figure 3.7.17-1 or in accordance with Specification 4.3.1.1.

APPLICABILITY:

Whenever any fuel assembly is stored in Region 2 or 3 of the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the LCO not met.

A.1

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

LCO 3.0.3 is not applicable.

Initiate action to move the noncomplying fuel assembly to Region 1.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify by administrative means the initial enrichment and burnup of the fuel assembly is in accordance with Figure 3.7.17-1 or Specification 4.3.1.1.

Prior to storing the fuel assembly in Region 2 or 3

Secondary Specific Activity 3.7.18 Wolf Creek - Unit 1 3.7-42 Amendment No. 123, 134, 171, 177 3.7 PLANT SYSTEMS 3.7.18 Secondary Specific Activity LCO 3.7.18 The specific activity of the secondary coolant shall be d 0.10 PCi/gm DOSE EQUIVALENT I-131.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Specific activity not within limit.

A.1 Be in MODE 3.

AND A.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify the specific activity of the secondary coolant is d 0.10 PCi/gm DOSE EQUIVALENT I-131.

31 days

v t e Letter Sequence Other
TAC:MD4840, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications (Approved, Closed)
Initiation Request, Request Acceptance... Administration Withholding Request Acceptance, Withholding Request Acceptance Questions Answers 12 September 2007 16 October 2007 18 January 2008 Results Approval, Approval Other: ET 08-0004, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification, ML080370121, ML081070277, ML081120149
MONTHYEAR2008-02-26 [Table View]

ML080370121

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