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Amend Attachment - Vogtle 3 Amend No. 190, Tech Spec Exceptions for In-Containment Refueling Water Storage Tank Operability Prior to Initial Criticality (Exigent Circumstances)
	ML23037A090
Person / Time
Site:	Vogtle
Issue date:	02/08/2023
From:	Bill Gleaves; NRC/NRR/VPOB
To:	Whitley B; Southern Nuclear Operating Co
Shared Package
ML23037A082	List: ML23037A088; ML23037A089; ML23037A090; ML23037A091;
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	Download: ML23037A090 (1)
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ATTACHMENT TO LICENSE AMENDMENT NO. 1 90

TO FACILITY COMBINED LICENSE NO. NPF-91

DOCKET NO.52-025

Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Combined License No. NPF-91

REMOVE INSERT 7 7

Appendix A to Facility Combined License No. N PF-91

REMOVE INSERT

3.3.8-7 3.3.8-7 3.3.8-8 3.3.8-8 3.3.9-5 3.3.9-5 3.3.9-6 3.3.9-6 3.3.10-5 3.3.10-5 3.3.16-1 3.3.16-1 3.3.19-3 3.3.19-3 3.3.20-3 3.3.20-3 3.5.7-1 3.5.7-1 3.5.8-1 3.5.8-1 3.5.8-2 3.5.8-2 3.5.8-3 3.5.8-3 (7) Reporting Requirements

(a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b) SNC shall report any violation of a requirement in Section 2.D.(3),

Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8) Incorporation

The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 190, a r e h e r e b y i n c o r p o r a t e d i n t o t h i s l i c e n s e.

(9) Technical Specifications

The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).

(10) Operational Program Implementation

SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:

(a) Environmental Qualification Program implemented before initial fuel load;

(b) Reactor Vessel Material Surveillance Program implemented before initial criticality;

(c) Preservice Testing Program implemented before initial fuel load;

(d) Containment Leakage Rate Testing Program implemented before initial fuel load;

(e) Fire Protection Program

1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt

7 Amendment No. 190 Technical Specifications ESFAS Instrumentation 3.3.8

Table 3.3.8-1 (page 1 of 2)

Engineered Safeguards Actuation System Instrumentation

APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS

1. Containment Pressure

a. - Low 1,2,3,4,5(a),6(a) 4 P

b. - Low 2 1,2,3,4,5(a),6(a) 4 P

2. Containment Pressure - High 2 1,2,3,4 4 H

3. Containment Radioactivity - High 1,2,3,4(b) 4 l

4. Containment Radioactivity - High 2 1,2,3 4 l

5. Pressurizer Pressure - Low 3 1,2,3(c)(l) 4 E

6. Pressurizer Water Level - Low 1,2 4 D

7. Pressurizer Water Level - Low 2 1,2,3,4(b) 4 F

4(d),5(e) 4 J

8. Pressurizer Water Level - High 1,2,3 4 l

9. Pressurizer Water Level - High 2 1,2,3,4(f) 4 l

10. Pressurizer Water Level - High 3 1,2,3,4(f) 4 Q

11. RCS Cold Leg Temperature (Tcold) - Low 2 1,2,3(c)(l) 4 per loop E

12. Reactor Coolant Average Temperature (Tavg) 1,2 4 D

- Low

13. Reactor Coolant Average Temperature (Tavg) 1,2 4 D

- Low 2

14. RCS Wide Range Pressure - Low 1,2,3,4 4 H 5(n) 4 K

6(g)(n) 4 L

(a) Without an open containment air flow path 6 inches in diameter.

(b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS).

(c) Above the P-11 (Pressurizer Pressure) interlock.

(d) With the RCS being cooled by the RNS.

(e) With RCS not VENTED and CMT actuation on Pressurizer Water Level - Low 2 not blocked.

(f) With all four cold leg temperatures > 275°F.

(g) With upper internals in place.

(l) Below the P-11 (Pressurizer Pressure) interlock and RCS boron concentration is less than that necessary to meet the SDM requirements at an RCS temperature of 200°F.

(n) For Unit 3 only, not required to be OPERABLE prior to initial criticality.

VEGP Units 3 and 4 3.3.8 - 7 Amendment No. 190 (Unit 3)

Amendment No. 147 (Unit 4)

Technical Specifications ESFAS Instrumentation 3.3.8

Table 3.3.8-1 (page 2 of 2)

Engineered Safeguards Actuation System Instrumentation

APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS

15. Core Makeup Tank (CMT) Level - Low 3 1,2,3,4(b) 4 per tank F 4(d),5(h) 4 per OPERABLE J tank

16. CMT Level - Low 6 1,2,3,4(b) 4 per tank F 4(d),5(h)(n) 4 per OPERABLE J tank

17. Source Range Neutron Flux Doubling 2(i),3(i),4(j) 4 I 5(j) 4 I

18. IRWST Lower Narrow Range Level - Low 3 1,2,3,4(b) 4 F 4(d),5(n) 4 M

6(g)(n) 4 N

19. Reactor Coolant Pump Bearing Water 1,2,3,4 4 per RCP O Temperature - High 2

20. SG Narrow Range Water Level - Low 2 1,2,3,4(b) 4 per SG F

21. SG Wide Range Water Level - Low 2 1,2,3,4(b) 4 per SG F

22. SG Narrow Range Water Level High 1,2,3,4 4 per SG I

23. SG Narrow Range Water Level - High 3 1,2 4 per SG D

3,4 4 per SG I

24. Steam Line Pressure - Low 2 1,2,3(c)(l)(m) 4 per steam line G

25. Steam Line Pressure - Negative Rate - High 3(k) 4 per steam line I

(b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS).

(c) Above the P-11 (Pressurizer Pressure) interlock.

(d) With the RCS being cooled by the RNS.

(g) With upper internals in place.

(h) With RCS not VENTED.

(i) With unborated water source flow paths not isolated except when critical or exc ept during intentional approach to criticality.

(j) With unborated water source flow paths not isolated.

(k) Below the P-11 (Pressurizer Pressure) interlock when Steam Line Pressure - Low 2 is blocked.

(l) Below the P-11 (Pressurizer Pressure) interlock and RCS boron concentration is less than that necessary to meet the SDM requirements at an RCS temperature of 200°F.

(m) Below the P-11 (Pressurizer Pressure) interlock when Steam Line Pressure - Low 2 is not blocked.

(n) For Unit 3 only, not required to be OPERABLE prior to initial criticality.

VEGP Units 3 and 4 3.3.8 - 8 Amendment No. 190 (Unit 3)

Amendment No. 147 (Unit 4)

Technical Specifications ESFAS Manual Initiation 3.3.9

Table 3.3.9-1 (page 1 of 2)

Engineered Safeguards Actuation System Instrumentation

APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS

1. Safeguards Actuation - Manual Initiation 1,2,3,4 2 switches E

5 2 switches J

2. Core Makeup Tank (CMT) Actuation - Manual 1,2,3,4(a) 2 switches D 4(b), 5(d) 2 Initiation switches G

3. Containment Isolation - Manual Initiation 1,2,3,4 2 switches E

4. Steam Line Isolation - Manual Initiation 1,2,3,4 2 switches F

5. Feedwater Isolation - Manual Initiation 1,2,3,4 2 switches F

6. ADS Stages 1, 2 & 3 Actuation - Manual 1,2,3,4 2 switch sets E 5(d) 2 switch sets H Initiation

7. ADS Stage 4 Actuation - Manual Initiation 1,2,3,4 2 switch sets E

5(i) 2 switch sets H

6(e)(i) 2 switch sets I

8. Passive Containment Cooling Actuation - 1,2,3,4 2 switches E 5(f) 2 Manual Initiation switches J

6(f) 2 switches K

9. Passive Residual Heat Removal Heat 1,2,3,4 2 Switches E 5(c) 2 Exchanger Actuation - Manual Initiation switches G

10. Chemical and Volume Control System Makeup 1,2,3,4(h) 2 switches F Isolation - Manual Initiation

11. Normal Residual Heat Removal System 1,2,3 2 switch sets F Isolation - Manual Initiation

(a) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS).

(b) With the RCS being cooled by the RNS.

(c) With the RCS pressure boundary intact.

(d) With RCS not VENTED.

(e) With upper internals in place.

(f) With decay heat > 7.0 MWt.

(h) With all four cold leg temperatures > 275°F.

(i) For Unit 3 only, not required to be OPERABLE prior to initial criticality.

VEGP Units 3 and 4 3.3.9 - 5 Amendment No. 190 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications ESFAS Manual Initiation 3.3.9

Table 3.3.9-1 (page 2 of 2)

Engineered Safeguards Actuation System Instrumentation

APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS

12. In-Containment Refueling Water Storage Tank 1,2,3,4(a) 2 switch sets D 4(b),5(i) 2 switch sets J (IRWST) Injection Line Valve Actuation -

Manual Initiation 6(i) 2 switch sets K

13. IRWST Containment Recirculation Valve 1,2,3,4(a) 2 switch sets D 4(b),5(i) 2 switch sets J Actuation - Manual Initiation

6(i) 2 switch sets K

14. SG Power Operated Relief Valve and Block 1,2,3,4(a) 2 switches D Valve Isolation - Manual Initiation

15. Containment Vacuum Relief Valve Actuation - 1,2,3,4,5(g),6(g) 2 switches L Manual Initiation

(a) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS).

(b) With the RCS being cooled by the RNS.

(g) Without an open containment air flow path 6 inches in diameter.

(i) For Unit 3 only, not required to be OPERABLE prior to initial criticality.

VEGP Units 3 and 4 3.3.9 - 6 Amendment No. 190 (Unit 3)

Amendment No. 13 (Unit 4)

Technical Specifications ESFAS RCS Hot Leg Level Instrumentation 3.3.10

Table 3.3.10-1 (page 1 of 1)

Engineered Safeguards Actuation System Instrumentation

APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS

1. Hot Leg Level - Low 4 5(a)(e),6(b)(e) 1 per loop C

2. Hot Leg Level - Low 2 5(c)(e) 1 per loop D

6(d)(e) 1 per loop E

(a) With CMT actuation on Pressurizer Water Level - Low 2 blocked.

(b) With upper internals in place and with CMT act uation on Pressurizer Water Level - Low 2 blocked.

(c) Below the P-12 (Pressurizer Level) interlock.

(d) With the water level < 23 feet above the top of the reactor vessel flange.

(e) For Unit 3 only, not required to be OPERABLE prior to initial criticality.

VEGP Units 3 and 4 3.3.10 - 5 Amendment No. 190 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS Actuation Logic

- Shutdown 3.3.16

3.3 INSTRUMENTATION

3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic -

Shutdown

LCO 3.3.16 Four divisions with one subsystem for each of the following Functions shall be OPERABLE:

a. ESF Coincidence Logic; and

b. ESF Actuation.

- NOTES -

1. Only the divisions necessary to support Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization are required to be OPERABLE during movement of irradiated fuel assemblies when not in MODE 1, 2, 3, 4, 5, or 6.

2. For Unit 3 only, ESF actuation Function for ADS stage 4 flow paths, In-Containment Refueling Water Storage Tank injection and recirculation flow paths, and CVS letdown isolation valves, not required to be OPERABLE prior to initial criticality.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

- NOTE -

Separate condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions A.1 Restore required division 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months within one required to OPERABLE status.

division inoperable.

VEGP Units 3 and 4 3.3.16 - 1 Amendment No. 190 (Unit 3)

Amendment No. 107 (Unit 4)

Technical Specifications DAS Manual Controls 3.3.19

Table 3.3.19-1 (page 1 of 1)

DAS Manual Controls

APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CONTROLS

1. Reactor trip manual controls 1,2 2 switches

2. Passive Residual Heat Removal Heat 1,2,3,4,5(a) 2 switches Exchanger (PRHR HX) control and In-Containment Refueling Water Storage Tank (IRWST) gutter control valves

3. Core Makeup Tank (CMT) isolation valves 1,2,3,4,5 (a) 2 switches

4. Automatic Depressurization System (ADS) 1,2,3,4,5(a) 2 switches stage 1 valves

5. ADS stage 2 valves 1,2,3,4,5(a) 2 switches

6. ADS stage 3 valves 1,2,3,4,5(a) 2 switches

7. ADS stage 4 valves 1,2,3,4,5(d),6(c)(d) 2 switches

8. IRWST injection squib valves 1,2,3,4,5(d),6(d) 2 switches

9. Containment recirculation valves 1,2,3,4,5(d),6(d) 2 switches

10. Passive containment cooling drain valves 1,2,3,4,5 (b),6(b) 2 switches

11. Selected containment isolation valves 1,2,3,4,5,6 2 switches

(a) With Reactor Coolant System (RCS) pressure boundary intact.

(b) With the reactor decay heat > 7.0 MWt.

(c) With upper internals in place.

(d) For Unit 3 only, not required to be OPERABLE prior to initial criticality.

VEGP Units 3 and 4 3.3.19 - 3 Amendment No. 190 (Unit 3)

Amendment No. 137 (Unit 4)

Technical Specifications ADS and IRWST Injection Blocking Device 3.3.20

Table 3.3.20-1 (page 1 of 1)

ADS and IRWST Injection Blocking Device

APPLICABLE MODES REQUIRED OR OTHER SPECIFIED CHANNELS PER SURVEILLANCE FUNCTION CONDITIONS DIVISION REQUIREMENTS

1. Core Makeup Tank Level for 1,2,3,4(b) 2 SR 3.3.20.2 Automatic Unblocking(a) SR 3.3.20.3 SR 3.3.20.5

2. ADS and IRWST Injection 1,2,3,4(b) 1 SR 3.3.20.3 Block Switches for Manual SR 3.3.20.4 Unblocking

4(c),5(d),6(d) 1 SR 3.3.20.1 SR 3.3.20.3 SR 3.3.20.4

(a) Not required to be OPERABLE with associated divisional ADS and IRWST Injection Bl ock switch in the unblock position.

(b) With the Reactor Coolant System (RCS) not being cooled by the Normal Residual Heat Removal System (RNS).

(c) With the RCS being cooled by the RNS.

(d) For Unit 3 only, not required to be OPERABLE prior to initial criticality.

VEGP Units 3 and 4 3.3.20 - 3 Amendment No. 190 (Unit 3)

Amendment No. 166 (Unit 4)

Technical Specifications IRWST - Shutdown, MODE 5 3.5.7

3.5 PASSIVE CORE COOLING SYSTEM (PXS)

3.5.7 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, MODE 5

LCO 3.5.7 The IRWST, with one injection flow path and one containment recirculation flow path, shall be OPERABLE.

- NOTE -

For Unit 3 only, not required to be OPERABLE prior to initial criticality.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. Required motor A.1 Open required motor 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months operated containment operated containment recirculation isolation recirculation isolation valve not fully open. valve.

B. Required IRWST B.1 Restore noncondensible 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months injection flow path with gas volume in squib valve noncondensible gas outlet line pipe stub to volume in one squib within limit.

valve outlet line pipe stub not within limit.

C. Required IRWST C.1 Restore noncondensible 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months injection flow path with gas volume in one squib noncondensible gas valve outlet line pipe stub volume in both squib to within limit.

valve outlet line pipe stubs not within limit.

VEGP Units 3 and 4 3.5.7 - 1 Amendment No. 190 (Unit 3)

Amendment No. 13 (Unit 4)

Technical Specifications IRWST - Shutdown, MODE 6 3.5.8

3.5 PASSIVE CORE COOLING SYSTEM (PXS)

3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, MODE 6

LCO 3.5.8 The IRWST, with one injection flow path and one containment recirculation flow path, shall be OPERABLE.

- NOTE -

For Unit 3 only, not required to be OPERABLE prior to initial criticality.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. Required motor A.1 Open required motor 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months operated containment operated containment recirculation isolation recirculation isolation valve not fully open. valve.

B. Required IRWST B.1 Restore noncondensible 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months injection flow path with gas volume in squib valve noncondensible gas outlet line pipe stub to volume in one squib within limit.

valve outlet line pipe stub not within limit.

C. Required IRWST C.1 Restore noncondensible 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months injection flow path with gas volume in one squib noncondensible gas valve outlet line pipe stub volume in both squib to within limit.

valve outlet line pipe stubs not within limit.

VEGP Units 3 and 4 3.5.8 - 1 Amendment No. 190 (Unit 3)

Amendment No. 80 (Unit 4)

Technical Specifications IRWST - Shutdown, MODE 6 3.5.8

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

D. IRWST and refueling D.1 Restore IRWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months cavity boron concentra-OPERABLE status.

tion not within limits.

OR

IRWST and refueling cavity borated water temperature not within limits.

OR

IRWST and refueling cavity borated water volume < 73,100 cu. ft and 70,907 cu. ft.

E. Required motor E.1 Restore required motor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months operated IRWST operated IRWST isolation isolation valve not fully valve to fully open open. condition with power removed.

OR

Power is not removed from required motor operated IRWST isolation valve.

F. Required Action and F.1 Initiate action to establish Immediately associated Completion water level 23 feet above Time of Condition A, B, the top of the reactor C, D, or E not met. vessel flange.

OR AND

LCO not met for F.2 Suspend positive reactivity Immediately reasons other than additions.

Condition A, B, C, D, or E.

VEGP Units 3 and 4 3.5.8 - 2 Amendment No. 190 (Unit 3)

Amendment No. 80 (Unit 4)

Technical Specifications IRWST - Shutdown, MODE 6 3.5.8

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

SR 3.5.8.1 Verify the IRWST and refueling cavity water 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature is < 120°F.

SR 3.5.8.2 Verify the IRWST and refueling cavity water total 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months borated water volume is 73,100 cu. ft.

SR 3.5.8.3 -----------------------------------------------------------------------

- NOTES -

1. Penetration flow path(s) may be unisolated intermittently under administrative controls.

2. Only required to be met with refueling cavity and

spent fuel pool volumes not in communication.

Verify Spent Fuel Pool Cooling System containment 31 days isolation valves are closed.

SR 3.5.8.4 Verify the IRWST and refueling cavity boron 31 days concentration is 2600 ppm and 2900 ppm.

AND

Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of 15,000 gal

SR 3.5.8.5 For the IRWST and flow paths required to be In accordance with OPERABLE, the following SRs are applicable: applicable SRs

SR 3.5.6.3 SR 3.5.6.6 SR 3.5.6.8 SR 3.5.6.10 SR 3.5.6.5 SR 3.5.6.7 SR 3.5.6.9 SR 3.5.6.11

VEGP Units 3 and 4 3.5.8 - 3 Amendment No. 190 (Unit 3)

Amendment No. 149 (Unit 4)

ML23037A090

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