RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2

Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2

ML17068A167
Person / Time
Site:	Robinson
Issue date:	03/08/2017
From:	Kapopoulos E Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/17-0019
Download: ML17068A167 (13)

Text

/_~ DUKE Ernest J. Kapopou/os, Jr.

H. B. Robinson Steam ENERGYe Electric Plant, Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 0: 843 857 1701 F: 843 8571319 Er11ie.Kapopoulos@duke-e11ergy.com 10 CFR 50.90 Serial: RNP-RA/17-0019 MAR 0 8 2017 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 SUPPLEMENTAL SUBMITTAL TO CORRECT MARKED UP TECHNICAL SPECIFICATIONS (TS) PAGES TRANSMITTED WITH APPLICATION FOR TECHNICAL SPECIFICATION TASK FORCE (TSTF)-339, RELOCATE TS PARAMETERS TO THE COLR CONSISTENT WITH WCAP-14483, REVISION 2 By letter dated April 24, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16116A033) Duke Energy Progress, Inc. (DEP) submitted a license amendment request (LAR) for H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2). The proposed amendment would adopt Technical Specifications Task Force (TSTF)-339, Revision 2, "Relocate TS Parameters to the COLR," dated May 26, 2000 (ADAMS Accession No. ML003723269), consistent with WCAP-14483, Revision 2, "Generic Methodology for Expanded Core Operating Limits Report," dated January 19, 1999 (ADAMS Accession No. ML020430092).

DEP has identified editorial and typographical errors on Technical Specifications (TS) pages 3.3-18, 3.4-1, 3.4-2, 5.0-25, "INSERT 3" and "INSERT 4" in Attachment 2 of the April 24, 2016 submittal. Attached please find replacement pages for the proposed TS changes. Additionally, the changes to the proposed TS changes impacted four revised TS pages, 3.3-18, 3.3-19, 5.0-25 and 5.0-25a, therefore these pages are also being replaced. The replacement of these pages does not affect the conclusions of either the 10 CFR 50.92 No Significant Hazards Consideration Determination or the Environmental Consideration included in Attachment 1 to the April 24, 2016 submittal letter. There are no other changes or additions to the Attachments to the April 24, 2016 letter, which presented the proposed TS page markups, the revised TS pages, and marked up TS Bases pages (for information only).

Please direct any questions regarding this matter to Mr. Tony Pila, Manager- Nuclear Regulatory Affairs at (843) 857-1409.

United States Nuclear Regulatory Commission Serial: RNP-RA/17-0019 Page 2 of 2 This document contains no new regulatory commitments.

I declare under penalty of perjury that the foregoing is true and correct. Executed on rPt fA {tk. Ff . '2017.

Sin~~

Ernest J. Kapopoulos, Jr.

Site Vice President EJK/jmw Attachment c: Region Administrator, NRC, Region II NRC Resident Inspector, HBRSEP D. Galvin, NRR

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/17-0019 8 Pages (including this page)

ATTACHMENT Replacement Pages for TS Pages 3.3-18, 3.4-1, 3.4-2, 5.0-25, "INSERT 3" and "INSERT 4" of Attachment 2 of ADAMS Accession No. ML16116A033, and Impacted Revised TS Pages 3.3-18, 3.3-19, 5.0-25 and 5.0-25a

RPS Instrumentation 3.3.1 Table 3.3.1-1 {page 6 of 7)

Reactor Protection System Instrumentation Note 1: OVertemperature AT The Overtemperature llT Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 2.96% of AT span.

fl T li8lp0int sA.To { K1 - K2 [ (1 +-r1 $)I (1 +-r 2 S) ] (T - T°) + K3(P - P)- f(lll)}

Where: AT0 is the indicated AT at RTP, °F.

s is the Laplace transform operator, sec*1.

• T. i.s the measured RCS average temperature, °F.----- [ 1 T 1s the reference Tavg at RTP, :S ~F. ~

[ *]

P, is the measured pressurizer pressure, psig ~

Pis the nominal RCS operating pressure, ~psig

~[*] ~ [*]

=

K, s1 .12es ~[

• 1 Kz e.e122el°F[ * ] K3 o.eeoel?psig =

't1 ~~sec -r2.S-9:&&~ [ *] / [ *] [ *]

[ * ] ----;;: =  %:4%{(qb - qJ - 47} <- [* ] wh~- qb < - ~ RTP ~

/ 0% of RTP when 1-% RTP :Sq1- qb :St2% RTP

[*] 7:4%{(q1 - Qb) - ~} when Q1 - qb >~ RTP

/ ~[*] ~[*]

[*] Where q 1 and qb are percent RTP in the upper and lower halves of the core, respectively, and q1 + qb is the total THERMAL POWER in percent RTP.

HBRSEP Unit No. 2 3.3-16 Amendment No. 231

RCS Pressure. Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM CRCS) 3.4.1 RCS Pressure, Temperature, and* Flow Departure from Nucleate Boiling CDNB) 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:

is greater than or equal to the

a. Pressurizer pressure -t:-1~ii-ft~*~: limit specified in the COLR

b. RCS average temperature ~ 579.4°F: is less than or equal to the limit specified in the COLR

c. RCS total flow rate i?: 97 .3 x 106 lbm/hr'.->_...._.,.._,._,__..-"->-.,.._,.._,.........,...,.,........,,.__,._,._,

and greater than or equal to the limit specified in the APPLICABILITY: MODE 1. COLR

-*------*-*-*-**-*--*-*---*-NOTE-**-********-***************

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5.t RTP per minute: or

b. THERMAL POWER step > 10.\' RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One*or more RCS DNB A.I Restore.RCS DNB 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> varameters not within parameter(s) to imits. within limit.

B. Required Action and B.1 Be in HOOE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

v HBRSEP Unit No. 2 3.4-1 Amendment No. 16-

RCS Pressure, Temperature, and Flow DNB Limits greater than or equal to the limit 3.4.1 specified in the COLR

~URVEILLANCE REQUIREMENTS FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is ~ 2205 psig. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.1.2 Verify RCS average temperature is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

< 579,4°F.

SR 3.4.1.3 Verify RCS total flow ra 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

~ 97.3 x 106 lbm/hr.

less than or equal SR 3.4.1.4 . * * - * * * - * * * - * * * * -* NOTE* * * - * * * * * * * * - * * * * *

• to the limit Not re ired to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> specified in the afte ~ 90t RTP.

and greater than or COLR equal to the limit specified in the Verify by precision heat balance that RCS 18 months COLR total flow rate is~ 97.3 x 106 lbm/hr.

and greater than or equal to the limit specified in the COLR HBRSEP Unit No. 2 3.4-2 Amendment No. i Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT CCOLR) (continued)

7. Axial Flux Difference (AFD) limits for Specification 3.2.3.; -aM-

8. Boron Concentration limit for Specification 3.9.11 ~

Place INSERT 4 here ,___~

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. The approved version shall be identified in the COLR. These methods are those specifically described in the following documents: *

1. Deleted

2. XN-NF-84-13(P), "Exxon Nuclear Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events." approved version as specified in the COLR.

3. XN-NF-82-21 (A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

approved version as specified in the COLR.

4. Deleted

5. XN-75-32(A), "Computational Procedure for Evaluating Rod Bow," approved version as specified in the COLR.

6. Deleted

7. Deleted

8. 'XN*NF-78-44(A), "Generic Control Rod Ejection Analysis," approved version as specified in the COLR. *

9. XN-NF-621(A), "XNB Critical Heat Flux Correlation,* approved version as* specified in the COLR.

10. Deleted

11. XN-NF-82-06(A), "Qualification of Exxon Nuclear Fuel for Extended Bumup," approved version as specified in the COLR.

12. Deleted

13. Deleted (continued)

HBRSEP Unit No. 2 5.0-25 . Amendment No.~

INSERT#3 0% of RTP when qt - qb > [ * ] RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt+ qb is the total THERMAL POWER in percent RTP.

The values denoted with [ * ] are specified in the COLR.

Reactor Core Safety Limits Figure for Specification 2.1.1; Overtemperature LH and Overpower LH setpoint parameter values for Specification 3.3.1; and Reactor Coolant System pressure, temperature and flow Departure from Nucleate Boiling (DNB} limits for Specification 3.4.1.

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7)

Reactor Protection System Instrumentation Note 1: Overtemperature /1 T The Overtemperature /1 T Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 2.96% of /1 T span .

11Tsetpoint S/1To { K1 - K2 [ (1 +-t1 S) I (1 +i: 2 S) ] (T - T) + K3(P - P) - f(/11)}

Where: /1T 0 is the indicated b.T at RTP, °F.

1 s is the Laplace transform operator, sec-

• Tis the measured RCS average temperature, °F.

0 T is the reference T avg at RTP, s [ * ]°F.

P is the measured pressurizer pressure, psig p' is the nominal RCS operating pressure, ~ [ * ] psig K1 s [ *] K2 = [ * ]/°F K3 = [ * ]/psig i:1 ~ [*]sec i:2 s [*]sec f(/11) = [ *] {(qb - q,) - [ *]} when q, - qb < - [ * ] RTP 0% of RTP when - [ * ] RTP s q1- qb s [ * ] RTP

[ * ] {(q, - qb) - [ *]} when q, - qb > [ * ] RTP Where q1and qb are percent RTP in the upper and lower halves of the core, respectively, and q1+ qb is the total THERMAL POWER in percent RTP.

The values denoted with [ * ] are specified in the COLR.

HBRSEP Unit No. 2 3.3-18 Amendment No.

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)

Reactor Protection System Instrumentation Note 2: Overpower b..T The Overpower b..T Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 3.17% of b..T span.

b.. Tsetpoint Sb.. To { K4 - Ks [-r3 SI (1 +-r 3 SJ] T - K6(T - T) - f(b..I)}

Where: b..T0 is the indicated b..T at RTP, °F.

s is the Laplace transform operator, sec- 1

• Tis the measured RCS average temperature, °F.

T' is the reference T avg at RTP s [

• l °F.

I

~ s [* l K 5 ~ [ * ]/°F for increasing T avg Ks~ [ * ]/°F when T > T'

[ * ]/°F for decreasing Tavg [ * ]/°F when T s T'

't3 ~ [*]sec f(b..I) = [

• l {(qb - qt) - [ * ]} when qt - qb < - [ * ] RTP 0% of RTP when - [ * ] RTP s qt - qb s [ * ] RTP

[

• l {(qt - qb) - [ *]} when qt - qb > [ * ] RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt+ qb is the total THERMAL POWER in percent RTP.

The values denoted with [ * ] are specified in the COLR.

HBRSEP Unit No. 2 3.3-19 Amendment No.

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

7. Axial Flux Difference (AFD) limits for Specification 3.2.3;

8. Boron Concentration limit for Specification 3.9.1;

9. Reactor Core Safety Limits Figure for Specification 2.1.1;

10. Overtemperature LiT and Overpower LiT setpoint parameter values for Specification 3.3.1; and

11. Reactor Coolant System pressure, temperature and flow Departure from Nucleate Boiling (DNB) limits for Specification 3.4.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRG. The approved version shall be identified in the COLR. These methods are those specifically described in the following documents:

1. Deleted

2. XN-NF-84-73(P), "Exxon Nuclear Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," approved version as specified in the COLR.

3. XN-NF-82-21 (A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

approved version as specified in the COLR.

4. Deleted

5. XN-75-32(A), "Computational Procedure for Evaluating Rod Bow,"

approved version as specified in the COLR.

6. Deleted

7. Deleted

8. XN-NF-78-44(A), "Generic Control Rod Ejection Analysis," approved version as specified in the COLR.

9. XN-NF-621 (A), "XNB Critical Heat Flux Correlation," approved version as specified in the COLR.

10. Deleted (continued)

HBRSEP Unit No. 2 5.0-25 Amendment No.

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements (continued)

11. XN-NF-82-0S(A), "Qualification of Exxon Nuclear Fuel for Extended Burnup," approved version as specified in the COLR.

12. Deleted

13. Deleted (continued)

HBRSEP Unit No. 2 5.0-25a Amendment No.