ML17054C221

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License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Revised Technical Specification Pages
ML17054C221
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/17/2017
From:
Wolf Creek
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17054C103 List:
References
ET 17-0001
Download: ML17054C221 (13)
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Text

SLs 2.0 Wolf Creek - Unit 1 2.0-1 Amendment No. 123, 144, 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded:

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained 1.17 for the WRB-2 DNB correlation, and 1.13 for the ABB-NV DNB correlation, and 1.18 for the WLOP DNB.

2.1.1.2 The peak centerline temperature shall be maintained 5080 °F, decreasing by 58 °F per 10,000 MWD/MTU of burnup.

2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

RCS Boron Limitations < 500°F 3.1.9 Wolf Creek - Unit 1 3.1-21 Amendment No.

3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 RCS Boron Limitations < 500°F LCO 3.1.9 The boron concentration of the Reactor Coolant System (RCS) shall be greater than the all rods out (ARO) critical boron concentration.

APPLICABILITY:

MODE 2 with keff < 1.0 with any RCS cold leg temperature < 500°F and with Rod Control System capable of rod withdrawal, MODE 3 with any RCS cold leg temperature < 500°F and with Rod Control System capable of rod withdrawal, MODES 4 and 5 with Rod Control System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RCS boron concentration not within limit.

A.1 Initiate boration to restore RCS boron concentration to within limit.

OR A.2 Initiate action to place the Rod Control System in a condition incapable of rod withdrawal.

OR A.3

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

Not applicable in MODES 4 and 5.

Initiate action to increase all RCS cold leg temperatures to 500°F.

Immediately Immediately Immediately

RCS Boron Limitations < 500°F 3.1.9 Wolf Creek - Unit 1 3.1-22 Amendment No.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify RCS boron concentration is greater than the ARO critical boron concentration.

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

RTS Instrumentation 3.3.1 Wolf Creek - Unit 1 3.3-9 Amendment No. 123, ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T.

One or more required channel(s) or train inoperable.

T.1 Verify interlock is in required state for existing unit conditions.

OR T.2 Be in MODE 2.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours U.

One trip mechanism inoperable for one RTB.

U.1 Restore inoperable trip mechanism to OPERABLE status.

OR U.2 Be in MODE 3.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 54 hours (continued)

RTS Instrumentation 3.3.1 Wolf Creek - Unit 1 3.3-10 Amendment No.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME V.

One channel inoperable.

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

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

V.1 Place channel in trip.

OR V.2.1 Be in MODE 2 with keff < 1.0.

AND V.2.2.1 Initiate action to fully insert all rods.

AND V.2.2.2 Initiate action to place the Rod Control System in a condition incapable of rod withdrawal.

OR V.2.3 Initiate action to borate the RCS to greater than all rods out (ARO) critical boron concentration.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> 78 hours 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> (continued)

RTS Instrumentation 3.3.1 Wolf Creek - Unit 1 3.3-11 Amendment No. 123, ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME W. One channel inoperable.

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

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

W.1 Place channel in trip.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> X.

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

OR Two or more channels inoperable.

X.1.1 Initiate action to fully insert all rods.

AND X.1.2 Initiate action to place the Rod Control System in a condition incapable of rod withdrawal.

OR X.2 Initiate action to borate the RCS to greater than all rods out (ARO) critical boron concentration.

Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

RTS Instrumentation 3.3.1 Wolf Creek - Unit 1 3.3-17 Amendment No. 123, 131, 132, 165, Table 3.3.1-1 (page 1 of 6)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE (a)

1. Manual Reactor Trip 1,2 3(b), 4(b), 5(b) 2 2

B C

SR 3.3.1.14 SR 3.3.1.14 NA NA

2. Power Range Neutron Flux
a.

High

b.

Low 1,2 1(c), 2(f) 2(h), 3(i) 4 4

4 D

V W, X SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 112.3% RTP 28.3% RTP 28.3% RTP

3. Power Range Neutron Flux Rate
a.

High Positive Rate

b.

High Negative Rate 1,2 1,2 4

4 E

E SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 6.3% RTP with time constant 2 sec 6.3% RTP with time constant 2 sec

4. Intermediate Range Neutron Flux 1(c), 2(d) 2 F,G SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 35.3% RTP (continued)

(a)

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

(b)

With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(c)

Below the P-10 (Power Range Neutron Flux) interlock.

(d)

Above the P-6 (Intermediate Range Neutron Flux) interlock.

(e)

Below the P-6 (Intermediate Range Neutron Flux) interlock.

(f)

With Keff 1.0.

(h)

With Keff < 1.0, and all RCS cold leg temperatures 500°F, and RCS boron concentration the all rods out (ARO) critical boron concentration, and Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(i)

With all RCS cold leg temperatures 500°F, and RCS boron concentration the ARO critical boron concentration, and Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

RTS Instrumentation 3.3.1 Wolf Creek - Unit 1 3.3-18 Amendment No. 123, 140, Table 3.3.1-1 (page 2 of 6)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE (a)

5. Source Range Neutron Flux 2(e) 3(b), 4(b), 5(b) 2 2

I,J J,K SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.11 1.6 E5 cps 1.6 E5 cps

6.

Overtemperature T 1,2 4

E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 Refer to Note 1 (Page 3.3-19)

7.

Overpower T 1,2 4

E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 Refer to Note 2 (Page 3.3-20)

8.

Pressurizer Pressure

a.

Low

b.

High 1(g) 1,2 4

4 M

E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 1930 psig 2395 psig

9.

Pressurizer Water Level - High 1(g) 3 M

SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 93.9% of instrument span

10.

Reactor Coolant Flow -

Low 1(g) 3 per loop M

SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 88.9% of normalized flow (continued)

(a)

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

(b)

With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(e)

Below the P-6 (Intermediate Range Neutron Flux) interlock.

(g)

Above the P-7 (Low Power Reactor Trips Block) interlock.

RCS Pressure, Temperature and Flow DNB Limits 3.4.1 Wolf Creek - Unit 1 3.4-1 Amendment No. 123, 144, 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a.

Pressurizer pressure is greater than or equal to the limit specified in the COLR;

b.

RCS average temperature is less than or equal to the limit specified in the COLR; and

c.

RCS total flow rate 361,200 gpm and greater than or equal to the limit specified in the COLR.

APPLICABILITY:

MODE 1.

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

Pressurizer pressure limit does not apply during :

a. THERMAL POWER ramp > 5% RTP per minute; or
b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

Not applicable to RCS total flow rate.

One or more RCS DNB parameters not within limits.

A.1 Restore RCS DNB parameter(s) to within limit.

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (continued)

RCS Pressure, Temperature and Flow DNB Limits 3.4.1 Wolf Creek - Unit 1 3.4-4 Amendment No. 123, 144, SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.1.2 Verify RCS average temperature is less than or equal to the limit specified in the COLR.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.1.3 Verify RCS total flow rate is 361,200 gpm and greater than or equal to the limit specified in the COLR.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.1.4

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

Not required to be performed until 7 days after 95% RTP.

Verify by precision heat balance that RCS total flow rate is 361,200 gpm and greater than or equal to the limit specified in the COLR.

18 months

MSSVs 3.7.1 Wolf Creek - Unit 1 3.7-3 Amendment No. 123, Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs PER STEAM GENERATOR MAXIMUM ALLOWABLE POWER

(% RTP) 4 3

2 70 51 31

Reporting Requirements 5.6 Wolf Creek - Unit 1 5.0-25 Amendment No. 123, 142, 144, 158, 159, 164, 179, 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1.

Specification 3.1.3: Moderator Temperature Coefficient (MTC),

2.

Specification 3.1.5: Shutdown Bank Insertion Limits,

3.

Specification 3.1.6: Control Bank Insertion Limits,

4.

Specification 3.2.3: Axial Flux Difference,

5.

Specification 3.2.1: Heat Flux Hot Channel Factor, FQ(Z),

6.

Specification 3.2.2: Nuclear Enthalpy Rise Hot Channel Factor (FNH),

7.

Specification 3.9.1: Boron Concentration,

8.

SHUTDOWN MARGIN for Specification 3.1.1 and 3.1.4, 3.1.5, 3.1.6, and 3.1.8,

9.

Specification 3.3.1: Overtemperature T and Overpower T Trip Setpoints,

10.

Specification 3.4.1: Reactor Coolant System pressure, temperature, and flow DNB limits, and

11.

Specification 2.1.1: Reactor Core Safety Limits.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1.

WCAP-11397-P-A, Revised Thermal Design Procedure.

2.

WCAP-10216-P-A, Relaxation of Constant Axial Offset Control -

FQ Surveillance Technical Specification.

3.

WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology.

(continued)

Reporting Requirements 5.6 Wolf Creek - Unit 1 5.0-26 Amendment No. 123, 142, 144, 158, 164, 179, 209, 213, 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4.

WCAP-16009-P-A, Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM).

5.

WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON.

6.

WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology.

7.

WCAP 10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code.

8.

WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report.

9.

WCAP-8745-P-A, Design Bases for the Thermal Power T and Thermal Overtemperature T Trip Functions.

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

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