ML20317A081

From kanterella
Jump to navigation Jump to search
Core Operating Limits Report Cycle 28 Pattern Owt Revision 2
ML20317A081
Person / Time
Site: North Anna 
Issue date: 11/09/2020
From: Standley B
Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
20-388
Download: ML20317A081 (21)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 9, 2020 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.:

NRA/DEA:

Docket No.:

License No.:

20-388 R1 50-339 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

NORTH ANNA POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT CYCLE 28 PATTERN OWT REVISION 2 Pursuant to North Anna Technical Specification 5.6.5.d, attached is a copy of the Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 28, Pattern OWT, Revision 2, Addendum 0. The COLR was revised to reflect the new core loading pattern.

If you have any questions or require additional information, please contact Ms. Diane Aitken at (804) 273-2694.

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

Attachment:

COLR-N2C28, Revision 2, Core Operating Limits Report, North Anna Unit 2 Cycle 28, Pattern OWT Commitment Summary: There are no new commitments contained in this letter.

cc:

U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. G. Edward Miller NRG Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B 1-A 11555 Rockville Pike Rockville, Maryland 20852-2738 NRG Senior Resident Inspector North Anna Power Station Serial No.: 20-388 Docket No.: 50-339 COLR N2C28 Pattern OWT, Rev. 2, Add. 0 Page 2 of 2

ATTACHMENT COLR-N2C28, Revision 2 CORE OPERATING LIMITS REPORT North Anna Unit 2 Cycle 28 Pattern OWT North Anna Power Station Unit 2 Virginia Electric and Power Company Serial No.: 20-388 Docket No.: 50-339 Page 1 of 19

N2C28 CORE OPERA TING LIMITS REPORT INTRODUCTION Serial No.: 20-388 Docket No.: 50-339 Attachment The Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 28 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 TS 3.1.1 TS 3.1.3 TS 3.1.4 TS 3.1.5 TS 3.1.6 TS 3.1.9 TS 3.2.1 TS 3.2.2 TS 3.2.3 TS 3.3.1 TS 3.4.1 TS 3.5.6 TS 3.9.1 Reactor Core Safety Limits Shutdown Margin (SDM)

Moderator Temperature Coefficient (MTC)

Rod Group Alignment Limits Shutdown Bank Insertion Limit Control Bank Insertion Limits PHYSICS TESTS Exceptions - Mode 2 Heat Flux Hot Channel Factor Nuclear Enthalpy Rise Hot Channel Factor (FNm)

Axial Flux Difference (AFD)

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

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 Ualics is provided for information only.

COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 2 of 19

REFERENCES Serial No.: 20-388 Docket No.: 50-339 Attachment

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-ShutdownBanklnsertionLimit 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-NuclearEnthalpy Rise Hot Channel Factor TS 3.5.6 - Boron Injection Tank (BIT) and TS 3.9.1 -Boron Concentration

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

as approved by NRC Safety Evaluation Report dated February 29, 2012.

Methodology for: TS 3.2.1-HeatFluxHot Channel Factor

3. WCAP-10054-P-A, "WestinghouseSmallBreakECCSEvaluationModel Usingthe NOTRUMP Code," August 1985.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

4. WCAP-10079-P-A, "NOTRUMP,ANodal Transient Small Break and GeneralNetwo1kCode,"

August 1985.

Methodology for: TS 3.2.1-Heat Flux Hot Channel Factor

5. WCAP-12610-P-A, "VANTAGE+FUELASSEMBLY-REFERENCECOREREPORT,"

April 1995.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits TS 3.2.1-HeatFluxHotChannelFactor

, 6. VEP-NE-2-A, Revision 0, "Statistical DNBREvaluation Methodology," June 1987.

Methodology for:

TS 3.2.2-NuclearEnthalpy Rise Hot Channel Factor and TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 3 of 19

Serial No.: 20-388 Docket No.: 50-339 Attachment

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

Methodology for:

TS 3.2.1-HeatFluxHot Channel Factor and TS 3.2.3-AxialFluxDifference

8. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower LlT and Thermal Overtemperature LlT Trip Functions," September 1986.

Methodology for:

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

9. WCAP-14483-A, "Generic Methodology for Expanded Core Operating Limits Report," Janumy 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

10. DOM-NAF-2-P-A, Revision 0, Minor Revision 3, "Reactor Core The1mal-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 C01Telations in the Dominion VIPRE-D Computer Code," September 2014.

Methodology for:

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

11. WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, "OptimizedZIRLO'," July 2006.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits and TS 3.2.1-HeatFluxHot Channel Factor COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 4 of 19

Serial No.: 20-388 Docket No.: 50-339 Attachment 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 1he 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-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 5 of 19

COLRFigure2.1-1 Serial No.: 20-388 Docket No.: 50-339 Attachment NORTH ANNA REACTOR CORE SAFETY LIMITS 665 660 655 650 645 640

'ii:' 635 I?.....

~ 630

I ro 625 QJ a.

E 620

~

QJ 615 ti.I) ro...

QJ 610

<C a:; 605

~ 600 595 590 585 580

~~

i,,,..,,.,_ -~---

~

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

psia

~

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

~"

~

~

\\

~

2000 psia

\\. \\

~

~

\\'

I"'-,,....

i\\.

\\ \\

1860 osia

-~...

-.............. I"--,..__

\\'

-I'-\\ \\

~

\\

\\.

............. \\

\\ '\\

\\

575 570 0

10 20 30 40 50 60 70 80 90 100 110 120 Percent of RATED THERMAL POWER COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 6 of 19

3.1 REACTIVITY 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)

Serial No.: 20-388 Docket No.: 50-339 Attachment LCO 3.1.3 The MTC shall be maintained within the limits specified below. The upper limit ofMTC is+0.6 x 104 Ak/k/°F, when< 70%RTP, and 0.0 Ak/k/°Fwhen 270%

RTP.

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

RTP, and~ 0.0 Ak/k/°F when z 70% RTP.

The EOC/ARO/RTP-MTC shall be less negative than-5.0 x 10-4 Ak/k/°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 Ak/k/°F [Note 1].

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

-4.7 x 104 Ak/k/°F [Note 2].

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

Note 1: If the MTC is more negative than -4.0 x 10-4 Ak/k/°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 104 Ak/k/°F.

COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 7 of 19

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 228 steps.

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

Required Action B.l Verify SDMto be~ 1.77 % Ak/k.

Serial No.: 20-388 Docket No.: 50-339 Attachment SR 3.1.5.1 Verify each shutdown bank is withdrawn to at least 228 steps.

3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be limited in physical insertion as shown in COLR Figure3.1-

1. Sequence of withdrawal shall be A, B, C and D, in that order; and the overlap limit during withdrawal shall be 100 steps.

RequiredActionA.1.1 Verify SDMto be~ 1.77 % Ak/k.

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

Required Action C. l 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 Ve1;ify each control bank not fully withdrawn from the core 1s 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-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 8 of 19

230 220 210 200 190 180 170 160

~ 150

i:

5} 140

~

=ll:~130 C:

0

~ 120 0

~ 110 0 l5 100 "C

0 90 ci::

80 70 60 50 40 30 20 10 0

/

/

COLRFigure3.1-1 North Anna 2 Cycle 28 Control Rod Bank Insertion Limits Fully w/d position= 228 steps I/ o.s39, 228

/

/

/

/

/

C-BANK

/

/

Av

.. (i18

/

Av

/

Vo-BArK

/

V

/

V

/

V

/

/

/o.048,o 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 Fraction of Rated Thermal Power COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A V

,J

/

0.8 Serial No.: 20-388 Docket No.: 50-339 Attachment 1.0, 194

/

/

/v

/

0.9 1

Page 9 of 19

3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

Serial No.: 20-388 Docket No.: 50-339 Attachment LCO 3.2.1 FQ(Z), as approximated by FQE(Z) and FQ T(Z), shall be within the limits specified below.

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

CFQ

  • K(Z) p for P > 0.5 CFQ
  • K(Z)

FQ(Z) ::::;

0.5 for P :s; 0.5 where:

THERMAL POWER d

P= RATED THERMAL POWER; an 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. 0 5 for measurement unce1tainty to obtain FQE(Z).

The expression for FQT(Z) is:

where:

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

FJ'(Z) = Fcf (Z)

  • N(Z)

N(Z) = FQ(Z),MaximumConditionl FQ(Z),EquilibriumConditionl 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 flux map using analyticallyderivedFQ(Z) values (scaled by relative power), consistent with the methodology described in VEP-NE-1. N(Z) accounts for power distribution transients encountered during nomial operation.

COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 10 of 19

The cycle-specific penalty factors are presented in COlR Table 3.2-1.

Serial No.: 20-388 Docket No.: 50-339 Attachment Also discussed is the application of the appropriate factor to accountfor potential increases in F Q(Z) between surveillances. This factor is determined on a cycle specific basis and is dependent on the predicted increases in steady-state and transient FQ(Z)/K(Z) versus burnup. A minimum value of2% isusedshouldanyincrease in steady-state or transientmeasuredorpredictedpeaking factor be determined unless.frequent.flux mapping is invoked (7 EFPD).

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

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

COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 11 of 19

COLR Table 3.2-1 N2C28 Penalty Factors for Flux Map Analysis Burnup Penalty (MWD/MTU)

Factor%

0-499 2.0 500-999 4.5 1000-1999 4.5 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

Serial No.: 20-388 Docket No.: 50-339 Attachment

1. Penalty Factors are not reqidredfor in Wal power ascension flux maps.
2. All fitll power maps shall apply a Penalty Factor unless frequent flux mapping is invoked

(~ 7 EFPD).

COLR Table 3.2-2 N2C28 Required Operating Space Reductions for FQT(Z) Exceeding its Limits Required FQT(Z)

Required Negative AFD Band Margin THERMAL POWER Reduction fromAFD Improvement Limit (% RTP)

Limits* (% AFD)

>0% and:::; 1%

98.0%

2':0.5%

> 1% and:S2%

96.0%

2': 1.0%

>2% and::::;3%

95.0%

2': 1.5%

>3%

S50%

NIA

  • Axial Flux Difference Limits are provided in COLR Figure 3.2-2 COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Positive AFD Band Reduction from AFD Limits* (% AFD) 2': 1. 5%

2': 2.0%

2': 3.5%

NIA Page 12 of 19

1.2 1.1 1.0 0.9 0.8 N a u.. 0. 7 C

w N

J !

0 z 0.6 0.4 0.3 0.2 0.1 0.0 COLRFigure 3.2-1 K(Z) - Normalized FQ as a Function of Core Height

{6, 1.0) -------

Serial No.: 20-388 Docket No.: 50-339 Attachment

--~.

(12,.925) 0 2

3 4

5 6

7 8

CORE HEIGHT (FT) 9 10 11 12 13 COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 13 of 19

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNm)

LCO 3.2.2 FN~H shall be within the limits specified below.

THERMAL POWER where:

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

3.2.3 AXIAL FLUX DIFFERENCE (AFD)

Serial No.: 20-388 Docket No.: 50-339 Attachment LCO 3.2.3 The AFD in% flux difference units shall be maintained within the limits specified in COLR Figure 3.2-2.

COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 14 of 19

120 110 COLR Figure 3.2-2 North Anna 2 Cycle 28 Axial Flux Difference Limits Serial No.: 20-388 Docket No.: 50-339 Attachment 100 90 r2* 10v

\\6, 100)

Q) 3:

0 a.

iii E Q)

..c I-

'O Q) -

/}_....

0 -

C:

Q)

~

Q)

a.

80 70 60 50 40 30 20 10 0

-30 Unacceptable /

Operation I

I I I/ I

(-2 7, 50)

-20 COLR-N2C28, Revision 2

\\

Unacceptable

[\\

Operation

\\

Acceptable Operation

' \\ \\

(+20, 50)

-10 0

10 20 30 Percent Flux Difference (Delta-I)

EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 15 of 19

3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation TS Table 3.3.1-1 Note 1: Overtemperature L\\T Serial No.: 20-388 Docket No.: 50-339 Attachment The Overtemperature L\\ T Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of L\\T span, with the numerical values of the parameters as specified below.

where: L\\T L\\To s

T T'

p P'

is measured RCS L\\T, °F is the indicated L\\TatRTP, °F is the Laplace transform operator, sec-1 is the measured RCS average temperature, °F is the nominal Tavg at RTP, s 586.8 °F is the measured pressurizer pressure, psig is the nominal RCS operating pressure, ~ 2235 psig K1 s 1.2715 K3 ~ 0.001145 /psig

-r1, -r2 = time constants utilized in the lead-lag controller for Tavg

-r1 ~ 23.75 sec

-r2 s 4.4 sec (1 +-r1s)/(l +-r2s) = function generated by the lead-lag controller for Tavgdynamic compensation f1(.6.l) 2: 0.0291 {-13.0- (qt-qb)}

0 0.0251 {(qt-qb)-7.0}

when (qt-qb) <-13.0% RTP when-13.0% RTP ~ (qt-qb) s +7.0% RTP 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-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 16 of 19

TS Table 3.3.1-1 Note 2: Overpower Lff Serial No.: 20-388 Docket No.: 50-339 Attachment The Overpower L\\T Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of L\\ Tspan, with the numerical values of the parameters as specified below.

where: L\\T L\\To s

T T'

is measured RCS L\\T, °F.

is the indicated L\\TatRTP, °F.

is the Laplace transform operator, sec-1.

is the measured RCS average temperature, °F.

is the nominal Tavg at RTP, ~ 586.8 °F.

K4 ~ 1.0865 Ks :2:: 0.0198 /°F for increasing Tavg K6 :2:: 0.00162 /°F when T> T' 0 /°F for decreasing Tavg O /°F when T::::; T' T3 = time constant utilized in the rate lag controller for Tavg T3 :2:: 9.5 sec T3s I (1 + r3s) = function generated by the rate lag controller for Tavg dynamic compensation f 2(Af) = O, for all ill.

COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 17 of 19

3.4 REACTOR COOLANT SYSTEM (RCS)

Serial No.: 20-388 Docket No.: 50-339 Attachment 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--------------------------------------------

Notrequired 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-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 18 of 19

NAPS TECHNICAL REQUIREMENTS MANUAL TRM 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.1 Boration Flow Paths - Operating Serial No.: 20-388 Docket No.: 50-339 Attachment Required Action D.2 Borate to a SHUTDOWN MARGIN ~ 1. 77 % Lil{!k at200 °F, after xenon decay.

COLR-N2C28, Revision 2 EVAL-ENG-RSE-N2C28, Revision 2, Attachment A Page 19 of 19

Retrieved from "https://kanterella.com/w/index.php?title=ML20317A081&oldid=3829875"