ML22258A066

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Core Operating Limits Report, Cycle 29, Pattern Btn, Revision 1
ML22258A066
Person / Time
Site: North Anna Dominion icon.png
Issue date: 09/13/2022
From: Standley B
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
22-282
Download: ML22258A066 (21)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 13, 2022 U.S. Nuclear Regulatory Commission Serial No.: 22-282 Attention: Document Control Desk NRNENC: RO Washington, DC 20555 Docket Nos.: 50-339 License Nos.: NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

NORTH ANNA POWER STATION UNIT 2 CORE OPERA TING LIMITS REPORT NORTH ANNA UNIT 2, CYCLE 29, PATTERN BTN, REVISION 1 The North Anna Power Station Unit 2 Core Operating Limits Report (COLR) has been revised to incorporate the FSLOCA methodology. Therefore, pursuant to Technical Specification 5.6.5.d, attached is a copy of the COLR for North Anna Unit 2, Cycle 29, Pattern BTN, Revision 1.

If you have any questions or require additional information, please contact Ms. Erica N.

Combs at (804) 273-3386.

Sincerely, B. E. Standley, Director Nuclear Regulatory Affairs Dominion Energy Services, Inc. for Virginia Electric and Power Company

Attachment:

COLR-N2C29, Revision 1, Core Operating Limits Report Commitments: None.

Serial No.: 22-282 Docket No.: 50-339 Page 2 of 2 cc: U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. G. E. Miller NRC Senior Project Manager - North Anna Power Station U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B 1-A 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector North Anna Power Station

Serial No.: 22-282 Docket No.: 50-339 ATTACHMENT COLR-N2C29, Revision 1 Core Operating Limits Report NORTH ANNA POWER STATION UNIT 2 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 1 of 18 N2C29 CORE OPERATING LIMITS REPORT INTRODUCTION The Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 29 has been prepared in accordance with North Anna Technical Specification 5.6.5. The technical specifications affected by this report are listed below:

TS 2.1.1 Reactor Core Safety Limits TS 3.1.1 Shutdown Margin (SDM)

TS 3.1.3 Moderator Temperature Coefficient (MTC)

TS 3.1.4 Rod Group Alignment Limits TS 3.1.5 Shutdown Bank Insertion Limit TS 3.1.6 Control Bank Insertion Limits TS 3.1.9 PHYSICS TESTS Exceptions - Mode 2 TS 3.2.l Heat Flux Hot Channel Factor TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN~H)

TS 3.2.3 Axial Flux Difference (AFD)

TS 3.3.1 Reactor Trip System (RTS) Instrumentation TS 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits TS 3.5.6 Boron Injection Tank (BIT)

TS 3.9.1 Boron Concentration In addition, a technical requirement (TR) in the NAPS Technical Requirements Manual (TRM) refers to the COLR:

TR 3.1.1 Boration Flow Paths - Operating The analytical methods used to determine the core operating limits are those previously approved by the NRC and discussed in the documents listed in the References Section.

Cycle-specific values are presented in bold. Text in italics is provided for information only.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 2 of 18 REFERENCES

1. VEP-FRD-42-A, Revision 2, Minor Revision 2, "Reload Nuclear Design Methodology,"

October 2017.

Methodology for:

TS 3.1.1 - Shutdown Margin TS 3 .1.3 - Moderator Temperature Coefficient TS 3.1.4 - Rod Group Alignment Limits TS 3.1.5-Shutdown Bank Insertion Limit TS 3 .1.6 - Control Bank Insertion Limits TS 3.1.9-Physics Tests Exceptions-Mode 2 TS 3.2.1 -Heat Flux Hot Channel Factor TS 3.2.2- Nuclear Enthalpy Rise Hot Channel Factor TS 3.5.6 - Boron Injection Tank (BIT) and TS 3.9.1-Boron Concentration

2. WCAP-16996-P-A, Rev. 1, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology)," November 2016.

Methodology for: TS 3.2.1 -Heat Flux Hot Channel Factor

3. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," as supplemented by ANP-3467P, Revision 0, North Anna Fuel-Vendor Independent Small Break LOCA Analysis," as approved by NRC Safety Evaluation Report dated March 19, 2021.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

4. WCAP-12610-P-A, "VANTAGE+ FUEL ASSEMBLY - REFERENCE CORE REPORT,"

April 1995.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits TS 3.2.1-Heat Flux Hot Channel Factor

5. VEP-NE-2-A, Revision 0, "Statistical DNBR Evaluation Methodology," June 1987.

Methodology for:

TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor and TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 3 of 18

6. VEP-NE-1-A, Revision 0, Minor Revision 3, "Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications," October 2017.

Methodology for:

TS 3.2.1 - Heat Flux Hot Channel Factor and TS 3.2.3 -Axial Flux Difference

7. WCAP-8745-P-A, "Design Bases for the Thermal Overpower ~T and Thermal Overtemperature

~T Trip Functions," September 1986.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits and TS 3.3.1 - Reactor Trip System Instrumentation

8. WCAP-14483-A, "Generic Methodology for Expanded Core Operating Limits Report," January 1999.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits TS 3.1.1-Shutdown Margin TS 3.1.4 - Rod Group Alignment Limits TS 3.1.9 - Physics Tests Exceptions - Mode 2 TS 3 .3 .1 - Reactor Trip System Instrumentation TS 3 .4.1 - RCS Pressure, Temperature, and Flow DNB Limits TS 3.5.6 - Boron Injection Tank (BIT) and TS 3.9 .1 - Boron Concentration

9. DOM-NAF-2-P-A, Revision 0, Minor Revision 3, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code," including Appendix C, "Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code," August 2010 and Appendix D, "Qualification of the ABB-NV and WLOP CHF Correlations in the Dominion VIPRE-D Computer Code," September 2014.

Methodology for:

TS 3.2.2- Nuclear Enthalpy Rise Hot Channel Factor and TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits

10. WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO'," July 2006.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits and TS 3.2.1 - Heat Flux Hot Channel Factor COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 4 of 18 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 COLR Figure 2.1-1; and the following SLs shall not be exceeded.

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained greater than or equal to the 95/95 DNBR criterion for the DNB correlations and methodologies specified in the References Section.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 5 of 18 COLR Figure 2.1-1 NORTH ANNA REACTOR CORE SAFETY LIMITS 665 660

~-..............

655 650

.....__ -- ~- .......... psia

~ ....... ~

645 640 635 ....

-.."" -.......... ~ o psia

~~

~

u::' ............ r-,....__ -............. ......

I!! 630

....I'll

...cu 625 ,...........

T......__,__ '--

~

i\

CL ~ ~ 2000 psia \\

~

E 620 ......

~ --......... ....... \,

cu 615 tl0

............ r--,......_ --....

\ 'I\ '

<(

I'll cu

> 610

~~

1860 psia "-- -.............

ai ""'--

605 ......

Ill Ill

'\

~ 600 ...............

'"" \

595 590 585

~ ......

580 i\

575 570 0 10 20 30 40 so 60 70 80 90 100 110 120 Percent of RATED THERMAL POWER COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 6 of 18 3.1 REACTMTY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be~ 1.77 % Ak/k.

3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3 .1.3 The MTC shall be maintained within the limits specified below. The upper limit ofMTC is +0.6 x 10-4 ~°F, when< 70% RTP, and 0.0 ~°F when~ 70%

RTP.

The BOC/ARO-MTC shall be :S: +0.6 x 104 ~°F (upper limit), when< 70%

RTP, and :S: 0.0 ~°F when~ 70% RTP.

The EOC/ARO/RTP-MTC shall be less negative than-5.0 x 10 4 ~ ° F (lower limit).

The MTC surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-4.0 x 10 4 ~°F [Note 1].

The 60 ppm/ARO/RTP-MTC should be less negative than or equal to

-4.7 x 10 4 ~°F [Note 2].

SR 3.1.3.2 Verify MTC is within-5.0 x 10-4 ~°F (lower limit).

Note 1: If the MTC is more negative than -4.0 x 10-4 ~°F, SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

Note 2: SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of :S: 60 ppm is less negative than-4.7 x 10 4 Ak/k/°F.

COLR-N2C29, Revision I EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 7 of 18 3.1.4 Rod Group Alignment Limits Required Action A.1.1 Verify SDM to be ~ 1. 77 % Ak/k.

Required Action B.1.1 Verify SDM to be ~ 1. 77 % Ak/k.

Required Action D.1.1 Verify SDM to be~ 1.77 % Ak/k.

3 .1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be withdrawn to at least 230 steps.

Required Action A.1.1 Verify SDM to be ~ 1. 77 % Ak/k.

Required Action B.1 Verify SDM to be ~ 1.77 % Ak/k.

SR 3.1.5.l Verify each shutdown bank is withdrawn to at least 230 steps.

3.1.6 Control Bank Insertion Limits LCO 3 .1.6 Control banks shall be limited in physical insertion as sho\.vn in COLR Figure 3.1-

1. Sequence of withdrawal shall be A, B, C and D, in that order; and the overlap limit during withdrawal shall be 102 steps.

Required Action A.1.1 Verify SDM to be ~ 1. 77 % Ak/k.

Required Action B.1.1 Verify SDM to be~ 1.77 % Ak/k.

Required Action C.1 Verify SDM to be~ 1.77 % Ak/k.

SR 3.1.6.1 Verify estimated critical control bank position is within the insertion limits specified in COLR Figure 3.1-1.

SR 3.1.6.2 Verify each control bank is within the insertion limits specified in COLR Figure 3.1-1.

SR 3.1.6.3 Verify each control bank not fully withdrawn from the core is within the sequence and overlap limits specified in LCO 3.1.6 above.

3.1.9 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.9.b SDM is~ 1.77 % Ak/k.

SR 3.1.9.4 Verify SDM to be~ 1.77 % Ak/k.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 8 of 18 COLR Figure 3.1-1 North Anna 2 Cycle 29 Control Rod Bank Insertion Limits Fully w/d position = 230 steps 230 V o.549,230 220 210 /

200 I/

1.0, 194 190 / ~

180 I/ /

/ C-BANK

~

V 170 160 I/ /

-c 150 / .,-V 3 / /

3" 140 t;

~130 / ,v C

0 / /

~ 120 I; 0, 118 0

';, 110

,v

I 0

\!i 100 /

-c Vo-BAI K 0 90 a:

80 /

70

/

60 /

so V 40 /

30 /

20 /

10 /

/o.048,o 0

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Fraction of Rated Thermal Power COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 9 of 18 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCO 3.2.1 FQ(Z), as approximated by FQE(Z) and FQT(Z), shall be within the limits specified below.

CFQ=2.32 The Heat Flux Hot Channel Factor, FQ(Z), shall be limited by the following relationships:

for P > 0.5 for P :S; 0.5 THERMAL POWER where: nd P= RATED THERMAL POWER; a K(Z) is provided in COLR Figure 3.2-1 FQE(Z) is an excellent approximation for FQ(Z) when the reactor is at the steady-state power.

FQ(Z) from the incore flux map results is increased by 1.03 for fuel manufacturing tolerances and 1.05 for measurement uncertainty to obtain FQE(Z).

F3 (Z) = FQ (Z) * (1.03) * (1.05)

The expression for FQT(Z) is:

FJ(Z) = F3(Z)

  • N(Z) where:

NZ = FQ(Z),MaximumConditionl

( ) FQ(Z),Equilibrium Condition I The discussion in the Bases Section B 3.2.1 for this LCO requires the application of a cycle dependent non-equilibrium multiplier, N(Z), to the steady state FQE(Z). N(Z) values are calculated for each fhcc map using analytically derived F Q(Z) values (scaled by relative power), consistent with the methodology described in VEP-NE-1. N(Z) accounts for power distribution transients encountered during normal operation.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 10 of 18 The cycle-specific penalty factors are presented in COLR Table 3.2-1.

Also discussed is the application of the appropriate factor to account for potential increases in Fg(Z) between surveillances. This factor is determined on a cycle specific basis and is dependent on the predicted increases in steady-state and transient F g(Z)/K(Z) versus burnup. A minimum value o/2% is used should any increase in steady-state or transient measured or predictedpeaking factor be determined unless fi*equent flux mapping is invoked (7 EFPD).

The required operating space reductions are included in COLR Table 3.2-2.

Should FgT(Z) exceed its limits the normal operating space should be reduced to gain peaking factor margins. The determination and verification of the margin improvements along with the corresponding required reductions in the Thermal Power Limit and AFD Bands are pe1formed on a cycle-specific basis.

COLR-N2C29, Revision 1 EV AL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 11 of 18 COLR Table 3.2-1 N2C29 Penalty Factors for Flux Map Analysis Burnup Penalty (MWD/MTU) Factor%

0-499 2.0 500-999 4.0 1000-1999 2.5 2000-2999 2.0 3000-3999 2.0 4000-4999 2.0 5000-6999 2.0 7000-8999 2.0 9000-10999 2.0 11000-12999 2.0 13000 - 14999 2.0 15000-16999 2.0 17000 -18999 2.0 19000-EOC 2.0 Notes:

1. Penalty Factors are not required for initial power ascension flux maps.
2. All full power maps shall apply a Penalty Factor unless frequent flux mapping is invoked

(~7 EFPD).

COLR Table 3.2-2 N2C29 Required Operating Space Reductions for Far(Z) Exceeding its Limits Required FQT(Z) Required Negative AFD Band Positive AFD Band Margin THERMAL POWER Reduction from AFD Reduction from AFD Improvement Limit (% RTP) Limits* (% AFD) Limits* (% AFD)

>03/4andS 1% S98.0% ~ 0.5% ~ 1.0%

> 1% andS2% S97.0% ~ 1.5% ~2.5%

>2%andS3% S95.0% ~ 1.5% ~3.0%

>3% S50% NIA NIA

  • Axial Flux Difference Limits are provided in COLR Figure 3.2-2 COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 12 of 18 COLR Figure 3.2-1 K(Z) - Normalized FQ as a Function of Core Height 1.2 1.1 6, 1.0 1.0

-- i----

~

0.9 (12 .925) 0.8 g

fl 0.7 C

w t=:.11

...I

< 0.6

~

0 z

~ 0.5 0.4 0.3 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 13 CORE HEIGHT (FT)

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 13 of 18 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN6H)

LCO 3 .2.2 FN6H shall be within the limits specified below.

FNMI ::;; 1.587 {l + 0.3(1 - P)}

THERMAL POWER where:

p= RATED THERMAL POWER SR 3.2.2.1 Verify FN6H is within limits specified above.

3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in% flux difference units shall be maintained within the limits specified in COLR Figure 3.2-2.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 14 of 18 COLR Figure 3.2-2 North Anna 2 Cycle 29 Axial Flux Difference Limits 120 110 100 r2* 10; \6, 100) 90 80 Unacceptable /

Operation '\ Unacceptable Operation Cl) 3: I I \

0 70 Acceptable Operation ll..

ns E 60 I/

I \

\

Cl)

.c

-Cl) ns 50 I (+20, 50)

(-27, 50)

....0::::0 C

Cl)

(J Cl) 40 ll.. 30 20 10 0

-30 -20 -10 0 10 20 30 Percent Flux Difference (Delta-I)

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 15 of 18 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation TS Table 3.3.1-1 Note 1: Overtemperature AT The Overtemperature AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.

where: AT is measured RCS AT, °F ATo is the indicated AT at RTP, °F s is the Laplace transform operator, sec- 1 T is the measured RCS average temperature, °F T' is the nominal T avg at R TP, ::S: 586.8 °F p is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, ~ 2235 psig K1 ~ 1.2715 K3 ~ 0.001145 /psig

'C1, 'C2 = time constants utilized in the lead-lag controller for Tavg

't1 ~ 23.75 sec 't2 ::S: 4.4 sec (1 +'C1S)/(l +'C2S) = fimction generated by the lead-lag controller for Tavg dynamic compensation fi(Af) ~ 0.0291 {-13.0- (qt- qb)} when (qt-qb) <-13.0% RTP 0 when-13.0% RTP ~ (qt-qb) ~ +7.0% RTP 0.0251{(qt-qb)-7.0} when (qt - qb) > +7.0% 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.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 16 of 18 TS Table 3.3.1-1 Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.

where: AT is measured RCS AT, °F.

ATo is the indicated AT at R TP, °F.

s is the Laplace transform operator, sec- 1.

T is the measured RCS average temperature, °F.

T' is the nominal T avg at R TP, ~ 586.8 °F.

K.i ~ 1.0865 Ks ~ 0.0198 /°F for increasing Tavg K6 ~ 0.00162 /°F when T > T' 0 /°F for decreasing T avg 0 /°F when T ~ T' t'3 = time constant utilized in the rate lag controller for Tavg t'3 ~ 9.5 sec ns I (1 + t'3s) = function generated by the rate lag controller for T avg dynamic compensation fa(Af) = 0, for all AL COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 17 of 18 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 2205 psig;
b. RCS average temperature is less than or equal to 591 °F; and
c. RCS total flow rate is greater than or equal to 295,000 gpm.

SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to 2205 psig.

SR 3.4.1.2 Verify RCS average temperature is less than or equal to 591 °F.

SR 3.4.1.3 Verify RCS total flow rate is greater than or equal to 295,000 gpm.

SR 3.4.1.4 ------------------------------NOTE--------------------------------------------

Not required to be performed until 30 days after~ 90% RTP.

Verify by precision heat balance that RCS total flow rate is ~ 295,000 gpm.

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 Boron Injection Tank (BIT)

Required Action B.2 Borate to a SDM ~ 1.77 % Ak/k at 200 °F.

3.9 REFUELING OPERATIONS 3.9 .1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System (RCS), the refueling canal, and the refueling cavity shall be maintained~ 2600 ppm.

SR 3.9.1.1 Verify boron concentration is within the limit specified above.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

Serial No.: 22-282 Docket No.: 50-339 Attachment 1 Page 18 of 18 NAPS TECHNICAL REQUIREMENTS MANUAL TRM 3.1 REACTIVITY CONTROL SYSTEMS TR 3. I. I Boration Flow Paths Operating Required Action D.2 Borate to a SHUTDOWN MARGIN~ 1.77 % Ak/k at 200 °F, after xenon decay.

COLR-N2C29, Revision 1 EVAL-ENG-RSE-N2C29, Revision 0, Addendum A, Attachment A

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