ML17054C220

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License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Changes
ML17054C220
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: ML17054C220 (15)
v • d • e


Text

Attachment II to ET 17-0001 Page 2 of 16 Sls 2.0 2.0 SAFETY LIMITS (Sls) 2.1 Sls

~ 1.13 for the ABB-NV DNB correlation ,

2.1.1 Reactor Core Sls and~ 1.18 for the WLOP DNB In MODES 1 and 2 the combination of THERMAL POWER, Rea tor Coolant System (RCS) hi est loop average temperature, and pressuriz r pressure shall not exceed the li its specified in the COLR; and the following S s shall not be exceeded:

2.1 .1.1 T e departure from nucleate boiling ratio (DNBR) all be maintained

~ ~ for the WRB-2 DNB correlation, and ~ 1.30 for the 1/1/ 3 DNB correlation .

2.1.1.2 The peak centerline temperature shall be maintained ~ 5080 oF, decreasing by 58 oF 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.

Wolf Creek- Unit 1 2.0-1 Amendment No. 123, 144

Attachment II to ET 17-0001 Page 3 of 16 PHYSICS TESTS Exceptions- MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1 .8 PHYSICS TESTS Exceptions- MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.3, "Moderator Temperature Coefficient (MTC)" ;

LCO 3.1.4, "Rod Group Alignment Limits" ;

LCO 3.1.5 , "Shutdown Bank Insertion Limits";

LCO 3.1.6 , "Control Bank Insertion Limits"; and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended and the number of required channels for LCO 3.3.1, "RTS Instrumentation," Functions 2, 3, 6, and 18.e, may be reduced to 3 required channels , provided :

a. RCS lowest operating loop average temperature is ~ 541 oF;
b. SDM is within the limits provided in the COLR; and
c. THERMAL POWER is~ 5% RTP .

APPLICABILITY: MODE 2 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

AND A.2 Suspend PHYSICS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TESTS exceptions.

B. THERMAL POWER not B.1 Open reactor trip Immediately within limit. breakers.

(contmued)

Wolf Creek - Unit 1 3.1-19 Amendment No.~. 151

Attachment II to ET 17-0001 Page 4 of 16 RCS Boron Limitations < 500°F IInsert New Page 3.1.9 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 kett < 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 A.1 Initiate boration to restore Immediately not within limit. RCS boron concentration to within limit.

A.2 Initiate action to place the Immediately 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 Immediately all RCS cold leg temperatures to ~ 500°F.

Wolf Creek- Unit 1 3.1-21 Amendment No.

Attachment II to ET 17-0001 Page 5 of 16 RCS Boron Limitations < 500°F 3.1 .9

!Insert New Page SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify RCS boron concentration is greater than the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ARO critical boron concentration.

Wolf Creek- Unit 1 3.1-22 Amendment No.

Attachment II to ET 17-0001 Page 6 of 16 RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T. One or more required T.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> channel(s) or train requ ired state for existing inoperable. unit conditions.

OR T.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> U. One trip mechanism U.1 Restore inoperable trip 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable for one RTB . mechanism to OPERABLE status.

OR

~. '{ '{ "{ "( "(

-~

U.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> INSERT 3 .3-9

.._>.._>... .)., ).. >..J 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)

Wolf Creek - Unit 1 3.3-9 Amendment No. 123

Attachment II to ET 17-0001 Page 7 of 16

~

CONDITION REQUIRED ACTION COMPLETION TIME V. One channel inoperable. ---------------------N0 T E-------------------

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. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR V.2.1 Be in MODE 2 with 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> kett < 1.0.

AND V.2.2 .1 Initiate action to fully insert 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> all rods.

AND V.2 .2.2 Initiate action to place the 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> Rod Control System in a condition incapable of rod withdrawal.

OR V.2.3 Initiate action to borate the 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> RCS to greater than all rods out (ARO) critical boron concentration.

Attachment II to ET 17-0001 Page 8 of 16

~y-y-j INSERT 3.3.9 (continued)

.AJ....A.A.).AJ...J...J...

CONDITION REQUIRED ACTION COMPLETION TIME

w. One channel inoperable. ---------------------N0 T E-------------------

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 X.1.1 Initiate action to fully insert Immediately associated Completion all rods.

Time of Condition W not met. AND OR X.1.2 Initiate action to place the Immediately Rod Control System in a Two or more channels condition incapable of rod inoperable. withdrawal.

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

Attachment II to ET 17-0001 Page 9 of 16 RTS Instrumentation 3.3 .1 Table 3.3.1-1 (page 1 of 6)

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

1. Manual Reactor Trip 1,2 2 B SR 3.3.1.14 NA 2 c SR 3.3.1.1 4 NA
2. Power Range Neutron Flux
a. High 1,2 4 D SR 3.3.1.1 .,; 112.3% RTP

[~

SR 3.3 .1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 4 SR 3.3 .1.1 ~ 28 . 3~~ RTP SR 3.3.1.8 SR 3.3.1.11 SR3 .3.1.1e

3. Power Range Neutron Flux Rate
a. High Positive Rate 1,2 4 E SR 3.3.1.7 <; 6.3% RTP SR 3.3.1.11 with time SR 3.3.1 .16 constant

~ 2 sec

b. High Negative 1,2 4 E SR 3.3.1.7 '>6.3% RTP with Rate SR 3.3.1.11 time constant SR 3.3.1 .16 ~ 2 sec
4. Intermediate Range 2 F,G SR 3.3.1 .1 '> 35.3% RTP Neutron Flux SR 3. 3.1 .8 SR 3.3.1.11
5. Source Range Neutron 2 I,J SR 3.3.1.1 <; 1.6 E5 cps Flux SR 3.3.1.8 SR 3.3 .1.11 2 J,K SR 3.3 .1.1 .,; 1.6 E5 cps SR 3.3 .1.7 SR 3.3.1.11 (continued)

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

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

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

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

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

Wolf Creek- Unit 1 3.3-15 AmendmentNo.123 , 131 , 132, 165

Attachment II to ET 17-0001 Page 10 of 16 APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a)

b. Low 1 (c),2 (t) 4 v SR 3.3.1 .1 s 28.3% RTP SR 3.3.1 .8 SR 3.3.1 .11 SR 3.3.1 .16 4 W, X SR 3.3.1 .1 s 28.3% RTP SR 3.3.1 .8 SR 3.3.1.11 SR 3.3.1.16 (f) With Keff;:: 1.0.

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

Attachment II to ET 17-0001 Page 11 of 16 RTS Instrumentation 3.3.1 Table 3.3.1 -1 (page 2 of 6)

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

6. Overtemperature LI.T 1,2 4 E SR 3.3.1.1 Refer to Note 1 SR 3.3.1.3 (Page 3.3-19)

SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

7. Overpower L\.T 1,2 4 E SR 3.3.1.1 Refer to SR 3.3.1.7 Note 2 SR 3.3.1.10 (Page SR 3.3.1 .16 3.3-20)
8. Pressurizer Pressure
a. Low 1(g) 4 M SR 3.3.1.1 ~ 1930 psig SR 3.3.1.7 SR 3.3.1 .10 SR 3.3.1.16
b. High 1,2 4 E SR3.3 .1.1 ~ 2395 psig SR 3.3 .1.7 SR 3.3.1.10 SR 3.3.1. 16
9. Pressurizer Water 1(g) 3 M SR 3.3 .1.1 ~ 93 .9% of Level- High SR 3.3.1.7 instrument span SR 3.3.1.10
10. Reactor Coolant Flow - 1(g) 3 per loop M SR 3.3.1.1 Low SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 11 . Not Used .
12. Undervoltage 1(g) 2/bus M SR 3.3.1.9 ~ 10355 Vac RCPs SR 3.3.1.10 SR 3.3.1.16 (continued)

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

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

~  % ef aesiJA flew QQ,a24 !j~IR Wolf Creek- Unit 1 3.3-16 Amendment No. 123, 140

Attachment II to ET 17-0001 Page 12 of 16 RCS Pressure, Temperature and Flow DNB Limits 3.4.1 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 ~ 37 .1 x 104 gpm and greater than or equal to the limit specified in the COLR. \

APPLICABILITY: MODE 1.

~

N0 T E-------------------------------------------------

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-------------- A.1 Restore RCS DNB 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Not applicable to RCS total parameter(s) to within flow rate. limit.

One or more RCS DNB parameters not within limits.

(continued)

Wolf Creek- Unit 1 3.4-1 Amendment No. 123, 144

Attachment II to ET 17-0001 Page 13 of 16 RCS Pressure, Temperature and Flow DNB Limits 3.4 .1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.1.2 Verify RCS average temperature is less than or equal 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to the limit specified in the COLR. ,...,....,...,.V'V'.,.......,

~361,200 -~

SR 3.4.1.3 Verify RCS total flow rate is ~ 37 .1 t 1Q4 gpm and greater than or equal to the limit specified in the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> COLR.

SR 3.4.1.4 ----------------------------N0 T E------------------------------------

Not required to be performed until 7 days after

~ 95 %,_...RJ"

.rV'p_

..-v-..-v-""

f361 ,200 * ~-----------------------------------------------

Verify by p~~ision heat balance that RCS total flow 18 months rate is~ 37 .1 x 1Q4 gpm and greater than or equal to the limit specified in the COLR.

Wolf Creek- Unit 1 3.4-4 Amendment No. 123, 144

Attachment II to ET 17-0001 Page 14 of 16 MSSVs 3.7 .1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs PER MAXIMUM ALLOWABLE POWER STEAM GENERATOR (% RTP) 4 3

2 Wolf Creek- Unit 1 3.7-3 Amendment No. ~

Attachment II to ET 17-0001 Page 15 of 16 Reporting Requirements 5.6 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, F0 (Z),
6. Specification 3.2.2 : Nuclear Enthalpy Rise Hot Channel Factor (F~H) ,
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, T and Overpower t,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:

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

(continued)

Wolf Creek- Unit 1 5.0-25 Amendment No. 123, 142, 144 , 158, 159, 164 , 179

Attachment II to ET 17-0001 Page 16 of 16 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 ATING LIMITS REPORT

~'""V""VV""V"V~+.e.,.

WCAP-10216-P-A, "Relaxation of Constant Axial Offset Control-Fa Surveillance Technical Specification."

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

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

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

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

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

~ 4-h WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report."

~~ WCAP-87 45-P-A, "Design Bases for the Thermal Power AT and Thermal Overtemperature AT 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)

Wolf Creek - Unit 1 5.0-26 Amendment No. 123, 142, 144, 158, 164 , 179, 209, 213

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