ML19289A489

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Core Operating Limits Report, Cycle 28 Pattern Gsw Revision 1
ML19289A489
Person / Time
Site: North Anna 
(NPF-004)
Issue date: 10/08/2019
From: Standley B
Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
19-416
Download: ML19289A489 (25)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 8, 2019 United States Nuclear Regulatory Commission Attention: Document Control Desk

19-416 NRA/DEA:

RO Docket No.:

50-338 License No.:

NPF-4 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

NORTH ANNA POWER STATION UNIT 1 CORE OPERATING LIMITS REPORT CYCLE 28 PATTERN GSW REVISION 1 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 1 Cycle 28, Pattern GSW, Revision 1, Addendum 0. The COLR was revised to incorporate shutdown data.

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-N1 C28, Revision 1, Core Operating Limits Report, North Anna Unit 1 Cycle 28, Pattern GSW 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 NRC 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 NRC Senior Resident Inspector North Anna Power Station Serial No.: 19-416 Docket No.: 50-338 COLR N1 C28 Pattern GSW, Rev. 1, Add. 0 Page 2 of 2

ATTACHMENT COLR-N1 C28, Revision 1 CORE OPERATING LIMITS REPORT North Anna Unit 1 Cycle 28 Pattern GSW North Anna Power Station Unit 1 Virginia Electric and Power Company Serial No.: 19-416 Docket No.: 50-338 Page 1 of 23

L NlC28 CORE OPERATING LIMITS REPORT INTRODUCTION Serial No.: 19-416 Docket No.: 50-338 The Core Operating Limits Report (COLR) for North Anna Unit 1 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 (FN 1rn)

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:

TR3.l.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-Nl C28, Revision 1 EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Page 2 of23

REFERENCES Serial No.: 19-416 Docket No.: 50-338

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. 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 - Heat Flux Hot Channel Factor

3. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

4. WCAP-10079-P-A, NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

5. 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. l - Heat Flux Hot Channel Factor

6. 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-N1C28, Revision 1 EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Page 3 of23

Serial No.: 19-416 Docket No.: 50-338

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

8. WCAP-8745-P-A, "Design Bases for the Thermal Overpower LiT and Thermal Overtemperature Li T 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," 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. l - Reactor Trip System Instrumentation TS 3.4. l - 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 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

11. 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-N1C28, Revision 1 EVAL-ENG-RSE-N1C28, Revision 0, Addendum A, Attachment A Page 4 of23

Serial No.: 19-416 Docket No.: 50-338 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.

2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 58°F per 10,000 MWD/MTU of burnup, for Westinghouse fuel and< 5173°F, decreasing by 65°F per 10,000 MWD/MTU ofburnup,for AREVA fuel.

COLR-NIC28, Revision I EVAL-ENG-RSE-NIC28, Revision 0, Addendum A, Attachment A Page 5 of 23

665 660 655 650 645 640

~ 635 e.......

a, 630

I

+'

111 625 a, c..

E 620

~

a, 615 b.O 111..

a, 610

<C ai 605 Ill Ill

~ 600 595 590 585 580 575 570 COLR Figure 2.1-1 NORTH ANNA REACTOR CORE SAFETY LIMITS Serial No.: 19-416 Docket No.: 50-338 T.......___ --

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0 10 20 30 40 50 60 70 80 90 100 110 120 I

Percent of RATED THERMAL POWER COLR-NIC28, Revision I EVAL-ENG-RSE-N1C28, Revision 0, Addendum A, Attachment A Page 6 of23

Serial No.: 19-416 Docket No.: 50-338 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)

LCO 3.1.3 The MTC shall.be maintained within the limits specified below. The upper limit of MTC is +0.6 x 10-4 Ak/k/°F, when< 70% RTP, and 0.0 Ak/k/°F when~ 70%

RTP.

The BOC/ARO-MTC shall be S +0.6 x 10-4 Ak/k/°F (upper limit), when< 70%

RTP, and S 0.0 Ak/k/°F when~ 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 shall be less negative than or equal to

-4.0 x 10-4 Ak/k/°F [Note 1].

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

-4.7 x 10-4 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 10-4 Ak/k/°F.

COLR-N1C28, Revision 1 EVAL-ENG-RSE-N1C28, Revision 0, Addendum A, Attachment A Page 7 of23

3.1.4 Rod Group Alignment Limits Required Action A. I. I 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. I. I Verify SDM to be~ 1.77 % Ak/k.

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

Serial No.: 19-416 Docket No.: 50-338 SR 3.1.5. l 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 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 100 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. l Verify SDM to be ~ 1. 77 % Ak/k.

SR3.l.6.l Verify estimated critical control bank position is within the insertion limits specified in COLR Figure 3.1-1.

SR 3.1.6.2 SR 3.1.6.3 Verify each control bank is within the inse1iion limits specified in COLR Figure 3.1-1.

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-NIC28, Revision 1 EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Page 8 of23

COLR Figure 3.1-1 North Anna 1 Cycle 28 Control Rod Bank Insertion Limits Fully w/d position = 228 steps Serial No.: 19-416 Docket No.: 50-338

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230 220 210 200 190 180 170 160

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Fraction of Rated Thermal Power COLR-N 1 C28, Revision 1 EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Page 9 of23

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

Serial No.: 19-416 Docket No.: 50-338 LCO 3.2.1 FQ(Z), as approximated by FQE(Z) and FQ \\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:

CFQ

  • K(Z)

FQ(Z) ~

p for P > 0.5 CFQ

  • K(Z)

FQ(Z) ~

0.5 for P ~ 0.5 where:

THERMAL POWER d

p

  • ~

= RATED THERMAL POWER '

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).

F5 (Z) = FQ (Z) * (1.03) * (1.05)

The expression for FQ \\Z) is:

FJ(Z) = F5(Z)

  • N(Z)

Where N(Z) is a cycle-specific non-equilibrium multiplier on F Q E(z) to account for power distribution transients during normal operation, provided in COLR Table 3.2-1.

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 F/(Z). N(Z) accounts for power distribution transients encountered during normal operation. As function N(Z) is dependent on the predicted equilibrium FQ(Z) and is sensitive to the axial power distribution, it is typically generated from the actual EOC burnup distribution that can only be obtained after the shutdown of the previous cycle.

COLR-NIC28, Revision I EVAL-ENG-RSE-NIC28, Revision 0, Addendum A, Attachment A Page 10 of23

The cycle-specific penalty factors are presented in COLR Table 3.2-2.

Serial No.: 19-416 Docket No.: 50-338 Also discussed is the application of the appropriate factor to account for potential increases in FQ(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 Q(Z)/K(Z) versus burnup. A minimum value of 2% is used should any increase in steady-state or transient measured or predicted peaking factor be determined unless frequent flux mapping is invoked (7 EFP DJ. These values are typically generated from the actual EOC burnup distribution that can only be obtained after the shutdown of the previous cycle.

The required operating space reductions are included in COLR Table 3.2-3.

Should F / (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 performed on a cycle-specific basis. These values are typically generated from the actual EOC burnup distribution that can only be obtained after the shutdown of the previous cycle.

COLR-N I C28, Revision I EVAL-ENG-RSE-N1 C28, Revision 0, Addendum A, Attachment A Page 11 of 23

COLR Table 3.2-1 N1 C28 Normal Operation N(Z)

NODE HEIGHT Oto 1000 1000 to 2000 2000 to 3000 3000 to 4000 4000 to 5000 (FEET)

MWD/MTU MWO/MTU MWDIMTU MWD/MTU MWD/MTU 5

11.2 1.126 1.127 1.134 1.142 1.151 6

11.0 1.125 1.130 1.137 1.141 1.150 7

10.8 1.124 1.132 1.140 1.140 1.148 8

10.6 1.122 1.132 1.140 1.139 1.146 9

10A 1.120 1.130 1.137 1.136 1.144 10 10.2 1.119 1.126 1.133 1.134 1.142 11 10.0 1.118 1.121 1.128 1.133 1.141 12 9.8 1.117 1.118 1.125 1.133 1.141 13 9.6 1.118 1.118 1.125 1.133 1.142 14 9.4 1.121 1.121 1.127 1.13,5 1.144 15 9.2 1.124 1.124 1.131 1.139 1.147 16 9.0 1.128 1.128 1.136 1.144 1.152 17 8.8 1.131 1.130 1.140 1.1413 1.156 1B 8.6 1.131 1.131 1.140 1.149 1.156 19 8.4 1.128 1.130 1.137 1.146 1.153 20 8.2 1.126 1.128 1.134 1.142 1.149 21 8.0 1.125 1.125 1.131 1.139 1.147 22 7.8 1.122 1.120 1.126 1.134 1.142 23 7.6 1.114 1.112 1.117 1.124 1.132 24 7.4 1.104 1.102 1.107 1.114 1.121 25 7.2 1.098 1.096 1.101 1.107 1.115 26 7.0 1.096 1.095 1.099 1.106 1,114 27 6.8 1.092 1.091 1.096 1.103 1.111 28 6.6 1.082 1.081 1.084 1.090 1.097 29 6.4 1.066 1.064 1.067 1.071 1.076 30 6.2 1.050 1.049 1.050 1.053 1.057 31 6.0 1.040 1.039 1.040 1.043 1.047 32 5.8 1.037 1.037 1.038 1.041 1.044 33 5.6 1.044 1,045 1.045 1.047 1.048 34 5.4 1.058 1.058 1.059 1.058 1.057 35 5.2 1.073 1.073 1.073 1.071 1.069 36 5.0 1.085 1.085 1.084 1.062 1.080 37 4.8 1.094 1.094 1.093 1.091 1.089 38 4.6 1.099 1.099 1.097 1.096 1.095 39 4.4 1.105 1.105 1.102 1.101 1.100 40 4.2 1.116 1.116 1.114 1.112 1.109 41 4.0 1,134 1.134 1.133 1.129 1.124 42 3.8 1.150 1.150 1.150 1.145 1.139 43 3.6 1.158 1.158 1.158 1.152 1.145 44 3.4 1.161 1.161 1.159 1.153 1.147 45 3.2 1.165 1.165 1.162 1.156 1.150 46 3.0 1.174 1.174 1.173 1.166 1.159 47 2.8 1.187 1.187 1.186 1.179 1.170 48 2.6 1.199 1.199 1.199 1.191 1.181 49 2.4 1.210 1.210 1.209 1.201 1.191 50 2.2 1.220 1.220 1.219 1.2.11 1.200 51 2.0 1.229 1.229 1.229 1.220 1.209 52 1.8 1,239 1.239 1.239 1.230 1.218 53 1.6 1.247 1.247 1.247 1.238 1.225 54 1A 1.255 1.255 1.255 1.245 1.232 COLR-NlC28, Revision 1 EVAL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Serial No.: 19-416 Docket No.: 50-338 5000 to 7000 7000 to 9000 MVt/DlMTU MWDfMTU 1.161 1.161 1.160 1.160 1.158 1.158 1.156 1.156 1.154 1.154 1.152 1.153 1.151 1.153 1.151 1.153 1.151 1.154 1.153 1.155 1.157 1.160 1.163 1.167 1.168 1.174 1.168 1.177 1.166 1.176 1.163 1.175 1.162 1.174 1.158 1.171 1.150 1.163 1.139 1.154 1.132 1.147 1.130 1.143 1.125 1.136 1.109 1.118 1.086 1.094 1.066 1.074 1.054 1.063 1.051 1.058 1.052 1.056 1.057 1.057 1.065 1.062 1.077 1.072 1.087 1.082 1.094 1.089 1.099 1.094 1.107 1.101 1.120 1.111 1.132 1.122 1.140 1.132 1.144 1.140 1.148 1.149 1.154 1.157 1.162 1.163 1.171 1.166 1.180 1.168 1.189 1.172 1.197 1.180 1.206 1.189 1.213 1.196 1.219 1.201 Page 12 of23

COLR Table 3.2-1 (continued}

N1C28 Normal Operation N(Z)

NODE HEIGHT 0 to 1000 1000to2000 2000 to 3000 3000to4000 4000 to 5000 (FEET)

MWD/MTU MWDJMTU MWDl1MTU M1/I/D/MTU MWD/MTU 55 1.2 1.262 1.262 1.261 1.251 1.238 56 1.0 1.268 1.268 1.267 1.258 1.244 57 0.8 1.275 1.275 1.273 1.263 1.250 Serial No.: 19-416 Docket No.: 50-338 5000 to 7000 7000to9000 MWDIMTU MWD/MTU 1.225 1.206 1.231 1.211 1.236 1.216 These decks are generated for normal operation flux maps that are typically taken at full power ARO. Additional N(Z) decks may be generated, if necessary, consistent with the methodology described in the RPDC topical (Reference 7). EOR is defined as Hot Full Power End of Reactivity.

COLR-N1C28, Revision 1 EVAL-ENG-RSE-N1C28, Revision 0, Addendum A, Attachment A Page 13 of 23

COLR Table 3.2-1 (continued}

N1C28 Normal Operation N(Z)

NODE HEIGHT 9000 to 11000 11000 to 13000 13000 to 15000 15000 to 17000 17000 to 19000 (FEET)

MVIIDrMTU MWOlMTU MWDIMTU MWDlMTU MWDllITTU 5

11.2 1.161 1.156 1.150 1.145 1.141 6

11.0 1.160 1.155 1.149 1.144 1.141 7

10.B 1.158 1.154 1.148 1.143 1.140 8

10.6 1.157 1.152 1.146 1.141 1.138 9

10A 1.154 1.151 1.144 1.140 1.137 10 10.2 1.153 1.150 1.145 1.141 1.139 11 10.0 1,153 1.149 1.147 1.145 1.144 12 9.8 1.153 1.150 1.150 1.150 1.149 13 9.6 1.154 1.151 1.151 1.152 1.150 14 9A 1.155 1.153 1.153 1.153 1.151 15 9.2 1.160 1.158 1.158 1.158 1,156 16 9.0 1.167 1.167 1.167 1.167 1.167 17 8.8 1.174 1.174 1.176 1.177 1.178 18 8.6 1.177 1.177 1.180 1.181 1.183 19 BA 1.177 1.177 1.180 1.181 1.183 20 8.2 1.176 1.177 1.180 1.181 1.183 2.1 8.0 1.176 1.178 1.181 1.182 1.165 n

7.8 1.175 1.178 1.180 1.182 1.185 23 7.6 1.169 1.173 1.175 1.177 1.180 24 7A 1.161 1.165 1.168 1.170 1.172 25 7.2 1.155 1.159 1.162 1.164 1.167 26 7.0 1.150 1.. 155 1.158 1.161 1.164 27 6.8 1.141 1.147 1.150 1.154 1.158 28 6.6 1.123 1.129 1.132 1.136 1.140 29 6A 1.100 1.105 1.109 1.113 1.116 30 6.2 1.081 1.086 1.090 1.094 1.098 31 6.0 1.070 1.076 1.081.

1.085 1.090 32 5.8 1.065 1.071 1.076 1.080 1.084 33 5.6 1.061 1.065 1.069 1.072 1.075 34 5A 1.059 1.061 1.062 1.063 1.064 35 5.2 1.062 1.061 1.061 1.061 1.061 36 5.0 1.070 1.069 1.069 1.068 1.068 37 4.8 1.080 1.079 1.080 1.079 1.079 38 4.6 1.087 1.087 1.088 1.066 1.088 39 4A 1.093 1.093 1.093 1.093 1.093 40 4.2 1.099 1.099 1.100 1.100 1.100 41 4.0 1.106 1.108 1.109 1.109 1.109 42 3.8 1.118 1.118 1.119 1.'119 1.119 43 3.6 1.128 1.127 1.128 1.128 1.128 44 3A 1,137 1.137 1.138 1.138 1.138 45 3.2 1:146 1.146 1.147 1.147 1.147 46 3.0 1.156 1.155 1.156 1.157 1.157 47 2.8 1.163 1.164 1.165 1.167 1.167 48 2.6 1.166 1.171 1.175 1.176 1.176 49 2.4 1.166 1.176 1.183 1.184 1.185 50 2.2 1.169 1.181 1.1a9 1:192 1.194 51 2.0 1.176 1.185 1.192 1.196 1.203 52 1.8 1.184 1.189 1.194 1.202 1.209 53 1.6 1.191 1.193 1.197 1.205 1.213 54 1.4 1.195 1.198 1.202 1.206 1.213 COLR-Nl C28, Revision 1 EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Serial No.: 19-416 Docket No.: 50-338 19000 to EOR MWDllITTU 1.140 1.140 1.139 1.138 1.136 1.138 1.143 1.147 1.148 1,149 1.155 1.167 1.179 1.185 1.184 1.184 1.186 1.186 1.181 1.173 1.168 1.166 1.160 1.142 1.118 1.099 1.092 1.086 1.076 1.064 1.060 1.067 1.078 1.087 1.093 1.099 1.108 1.118 1.128 1.137 1,147 1.157 1.167 1.176 1.185 1.194 1.203 1.210 1.214 1.215 Page 14 of 23

COLR Table 3.2-1 (continued)

N1C28 Normal Operation N(Z)

Serial No.: 19-416 Docket No.: 50-338 HODE HEIGHT 9000 to 11000 11000 to 13000 13-000 to 15000 15000 to 17000 17000 to 19000 19000 to EOR (FEET)

MWD/MTU MWD/MTU MWD,1MTU MWDIMTU MWD/MTU 55 1.2 1.200 1.203 1.207 1.212 1.215 56 1.0 1.205 1.209 1.213 1.217 1.220 57 0.8 1.210 1.214 1.218 1.222 1.226 MWD/MTU 1.217 1.221 1.226 These decks are generated for normal operation flux maps that are typically taken at full power ARO. Additional N(Z) decks may be generated, if necessary, consistent with the methodology described in the RPDC topical (Reference 7). EOR is defined as Hot Full Power End of Reactivity.

COLR-NlC28, Revision 1 EV AL-ENG-RSE-N 1 C28, Revision 0, Addendum A, Attachment A Page 15 of23

COLR Table 3.2-2 N1C28 Penalty Factors for Flux Map Analysis Burnup Penalty (MWD/MTU)

Factor 0/o 0-999 2.0 1000-1999 4.0 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.: 19-416 Docket No.: 50-338 I. 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 3.2-3 N1C28 Required Operating Space Reductions for FQr(Z) Exceeding its Limits Required F0T(Z)

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

Limits* (% AFD)

Limits* (% AFD)

s 1%
S 98.0%
0.5%
1.0%

> 1% and :S 2%

S 96.0%
1.0%
2.0%

> 2% and :S 3%

S 95.0%
1.5%
4.0%

>3%

S50%

NIA NIA

  • Axial Flux Difference Limits are provided in COLR Figure 3.2-2 COLR-Nl C28, Revision 1 EVAL-ENG-RSE-N1C28, Revision 0, Addendum A, Attachment A Page 16 of23

1.2 1.1 1.0 0.9 0.8 N

0

u. 0.7 C

w N

'.j < 0.6 2

0::

0 z

~ 0.5

~

0.4 0.3 0.2 0.1 0.0 COLR Figure 3.2-1 K(Z) - Normalized FQ as a Function of Core Height 6, 1.0 Serial No.: 19-416 Docket No.: 50-338

--~.

(12,.925) 0 1

2 3

4 5

6 7

8 CORE HEIGHT (FT) 9 10 11 12 13 COLR-NIC28, Revision I EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Page 17 of 23

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN,18)

LCO 3.2.2 FN iiH shall be within the limits specified below.

FN,\\H ~ 1.587 {l + 0.3(1 - P)}

THERMAL POWER where:

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

3.2.3 AXIAL FLUX DIFFERENCE (AFD)

Serial No.: 19-416

. Docket No.: 50-338 LCO 3.2.3 The AFD in% flux difference units shall be maintained within the limits specified in COLR Figure 3.2-2.

COLR-NIC28, Revision I EVAL-ENG-RSE-NlC28, Revision 0, Addendum A, Attachment A Page 18 of23

120 110 COLR Figure 3.2-2 North Anna 1 Cycle 28 Axial Flux Difference Limits Serial No.: 19-416 Docket No.: 50-338 100 90

,-12. 10v

\\6, 100)

Q) 3::

0 a.

iii E

Q)

.c:

I-

"C Q)

+"'

Ill 0::....

0

+"'

C:

Q)

~

Q) a.

80 70 60 50 40 30 20 10 0

-30 Unacceptable /

Operation I

)

I I *;

(-27, 50)

-20 COLR-NIC28, Revision 1 Unacceptable

\\

Operation

\\

Acceptable Operation

' \\ \\

(+20, 50)

-10 0

10 20 Percent Flux Difference (Delta-I)

EV AL-ENG-RSE-N 1 C28, Revision 0, Addendum A, Attachment A 30 Page 19 of23

3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation TS Table 3.3.1-1 Note 1: Overtemperature.1 T Serial No.: 19-416 Docket No.: 50-338 The Overtemperature.1T Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of.1T span, with the numerical values of the parameters as specified below.

where:.1T

.1To s

T T'

p P'

is measured RCS L'.1 T, °F is the indicated L1T at RTP, °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 K2 ~ 0.02174 /°F K3 ~ 0.001145 /psig 1' 1, 1'2 = time constants utilized in the lead-lag controller for Tavg 1'1 ~ 23.75 sec 1'2 S 4.4 sec (1 +1'1S)/(l +1'2S) = function generated by the lead-lag controller for Tavg dynamic compensation f1 (L1I) 2: 0.0291 {-13.0 - ( qt - qb)}

0 0.0251{(qi-qb)-7.0}

when ( qi - qb) < -13.0% R TP when-13.0% RTP ~ (qt-qb) ~ +7.0% RTP when (qi-qb) > +7.0% RTP Where qt 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.

COLR-N1C28, Revision 1 EV AL-ENG-RSE-N 1 C28, Revision 0, Addendum A, Attachment A Page 20 of23

TS Table 3.3.1-1 Note 2: Overpower ~T Serial No.: 19-416 Docket No.: 50-338 The Overpower ~T Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of ~T span, with the numerical values of the parameters as specified below.

where: ~T

~To s

T T'

is measured RCS ~T, °F.

is the indicated ~Tat RTP, °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.

K,i S 1.0865 Ks ~ 0.0198 /°F for increasing Tavg K6 ~ 0.00162 /°F when T > T' O /°F for decreasing Tavg O !°F when T ~ T'

!'3 = time constant utilized in the rate lag controller for Tavg T3 ~ 9.5 sec I'3s I(]+ I'3s) = function generated by the rate lag controller for Tavg dynamic compensation f2(~I) = 0, for all Af.

COLR-NIC28, Revision I EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Page 21 of23

Serial No.: 19-416 Docket No.: 50-338 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 SR 3.4.1.2 SR 3.4.1.3 SR 3.4.1.4 Verify pressurizer pressure is greater than or equal to 2205 psig.

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

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

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 SOM~ 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-N1C28, Revision 1 EVAL-ENG-RSE-N1C28, Revision 0, Addendum A, Attachment A Page 22 of23

NAPS TECHNICAL REQUIREMENTS MANUAL TRM 3.1 TR 3.1.1 REACTIVITY CONTROL SYSTEMS Boration Flow Paths - Operating Serial No.: 19-416 Docket No.: 50-338 Required Action D.2 Borate to a SHUTDOWN MARGIN~ 1.77 % Ak/k at 200 °F, after xenon decay.

COLR-N1C28, Revision I EV AL-ENG-RSE-Nl C28, Revision 0, Addendum A, Attachment A Page 23 of 23

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