ML23138A125

Attachment to LAR 208 to Facility Combined License No. NPF-92 Docket No.52-026

ML23138A125
Person / Time
Site:	Vogtle
Issue date:	10/23/2023
From:	NRC/NRR/VPOB
To:	Southern Nuclear Operating Co
Shared Package
ML23138A085	List: ML23138A100 ML23138A105 ML23138A116 ML23138A117 ML23138A119 ML23138A125
References
EPID L-2022-LLA-0149
Download: ML23138A125 (1)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 190 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 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-92 REMOVE INSERT 7

7 Appendix A to Facility Combined License No. NPF-92 REMOVE INSERT 3.2.1-1 3.2.1-1 3.2.1-2 3.2.1-2 3.2.1-3 3.2.1-3 3.2.1-4 3.2.1-4 3.2.1-5 3.2.1-5 3.2.1-6 5.6-4 5.6-4 5.6-5 5.6-5 5.6-6

7 Amendment No. 190 (7)

Reportin R g equirements (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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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, are hereby incorporated into this license.

(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) with the following exceptions:

(a)

Prior to initial criticality of the reactor core while operating in plant operational Mode 5 (Cold Shutdown) or Mode 6 (Refueling) the following TS are temporarily excluded from becoming effective:

TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation, Table 3.3.8-1 o

Function 14, RCS Wide Range Pressure - Low o

Function 15, Core Makeup Tank (CMT) Level - Low 3 o

Function 16, CMT Level - Low 6 o

Function 18, IRWST Lower Narrow Range Level - Low 3 TS 3.3.9, Engineered Safety Feature Actuation System (ESFAS)

Manual Initiation, Table 3.3.9-1 o

Function 1, Safeguards Actuation - Manual Initiation o

Function 6, ADS Stages 1, 2 & 3 Actuation - Manual Initiation o

Function 7, ADS Stage 4 Actuation - Manual Initiation o

Function 8, Passive Containment Cooling Actuation - Manual Initiation o

Function 9, Passive Residual Heat Removal Heat Exchanger Actuation - Manual Initiation

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 VEGP Units 3 and 4 3.2.1 - 1 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4) 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) (Constant Axial Offset Control (CAOC) W(Z)

Methodology)

LCO 3.2.1 FQ(Z), as approximated by

)

Z

(

FC Q

and

)

Z

(

FW Q

, shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 1 with THERMAL POWER 25% RTP and with On-Line Power Distribution Monitoring System (OPDMS) not monitoring parameters.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

- NOTES -

1. Required Action A.3 shall be completed whenever this Condition is entered prior to increasing THERMAL POWER above the limit of Required Action A.1.

2. SR 3.2.1.2 is not required to be performed if this Condition is entered prior to THERMAL POWER exceeding 75% RTP after refueling.

)

Z

(

FC Q

not within limit.

A.1 Reduce THERMAL POWER 1% RTP for each 1%

)

Z

(

FC Q

exceeds limit.

15 minutes after each

)

Z

(

FC Q

determination AND A.2 AND A.3 Reduce Overpower T trip setpoints 1% for each 1% that THERMAL POWER is limited below RTP by Required Action A.1.

Perform SR 3.2.1.1 and SR 3.2.1.2.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each

)

Z

(

FC Q

determination Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 VEGP Units 3 and 4 3.2.1 - 2 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

)

Z

(

FW Q

not within limits.

B.1.1

- NOTE -

Required Action B.1.2 shall be completed if control rod motion is required to comply with the new operating space implemented by Required Action B.1.1.

Restore

)

Z

(

FW Q

to within limits specified in the COLR.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> AND B.1.2 Perform SR 3.2.1.1 and SR 3.2.1.2.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR (continued)

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 VEGP Units 3 and 4 3.2.1 - 3 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2.1

- NOTE -

Required Action B.2.3 shall be completed whenever Required Action B.2.1 is performed prior to increasing THERMAL POWER above the limit of Required Action B.2.1.

Limit THERMAL POWER to less than RTP by amount specified in the COLR.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after each

)

Z

(

FW Q

determination AND B.2.2 Reduce Overpower T trip setpoints 1% for each 1% that THERMAL POWER is limited below RTP by Required Action B.2.1.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each

)

Z

(

FW Q

determination AND B.2.3 Perform SR 3.2.1.1 and SR 3.2.1.2.

Prior to increasing THERMAL POWER above the limit of Required Action B.2.1 C.

Required Action and associated Completion Time not met.

C.1 Reduce THERMAL POWER < 25% RTP.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 VEGP Units 3 and 4 3.2.1 - 4 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1

- NOTE -

Not required to be performed if OPDMS was monitoring parameters upon exceeding 75% RTP.

Verify

)

Z

(

FC Q

within limit.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP SR 3.2.1.2

- NOTE -

Not required to be performed if OPDMS was monitoring parameters upon exceeding 75% RTP.

Verify

)

Z

(

FW Q

within limits.

Once after each refueling within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions after THERMAL POWER exceeds 75% RTP

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 VEGP Units 3 and 4 3.2.1 - 5 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4)

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.3

- NOTE -

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after OPDMS not monitoring parameters.

Verify

)

Z

(

FC Q

within limit.

Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which

)

Z

(

FC Q

was last verified AND 31 effective full power days (EFPD) thereafter

Technical Specifications FQ(Z) (CAOC W(Z) Methodology) 3.2.1 VEGP Units 3 and 4 3.2.1 - 6 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4)

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.4

- NOTE -

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after OPDMS not monitoring parameters.

Verify

)

Z

(

FW Q

within limits.

Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilib-rium conditions after exceeding, by 10% RTP, the THERMAL POWER at which

)

Z

(

FW Q

was last verified AND 31 EFPD thereafter

Technical Specifications Reporting Requirements 5.6 VEGP Units 3 and 4 5.6 - 4 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4) 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued) 6.

APP-GW-GLR-137, Revision 1, Bases of Digital Overpower and Overtemperature Delta-T (OPT/OTT) Reactor Trips, Westinghouse Electric Company LLC.

(Methodology for Specification 2.1.1 - Reactor Core Safety Limits.)

7a. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004 (Westinghouse Proprietary) and WCAP-16045-NP-A, (Non-Proprietary).

(Methodology for Specification 3.1.3 - Moderator Temperature Coefficient (MTC).)

7b. WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007 (Westinghouse Proprietary) and WCAP-16045-NP-A, Addendum 1-A, (Non-Proprietary).

(Methodology for Specification 3.1.3 - Moderator Temperature Coefficient (MTC).)

7c. WCAP-13749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, March 1997 (Westinghouse Proprietary).

(Methodology for Specification 3.1.3 - Moderator Temperature Coefficient (MTC).)

8.

WCAP-17667-P-A, Revision 1, "Improved RAOC and CAOC FQ Surveillance Technical Specifications," February 2019 (Westinghouse Proprietary).

(Methodology for Specifications 3.1.6 - Control Bank Insertion Limits, 3.2.1 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for FQ Methodology), and 3.2.3 - AXIAL FLUX DIFFERENCE.)

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Passive Core Cooling Systems limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

Technical Specifications Reporting Requirements 5.6 VEGP Units 3 and 4 5.6 - 5 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4) 5.6 Reporting Requirements 5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

3.4.3, RCS Pressure and Temperature (P/T) Limits; and 3.4.14, Low Temperature Overpressure Protection (LTOP).

b.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

WCAP-14040-A, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves.

(Limits for LCO 3.4.3 and LCO 3.4.14).

c.

The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for any revision or supplement thereto.

5.6.5 Post Accident Monitoring Report When a report is required by Condition B of LCO 3.3.17, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Technical Specifications Reporting Requirements 5.6 VEGP Units 3 and 4 5.6 - 6 Amendment No. 193 (Unit 3)

Amendment No. 190 (Unit 4) 5.6 Reporting Requirements 5.6.6 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.4, "Steam Generator (SG) Program." The report shall include:

a.

The scope of inspections performed on each SG,

b.

Active degradation mechanisms found,

c.

Nondestructive examination techniques utilized for each degradation mechanism,

d.

Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e.

Number of tubes plugged during the inspection outage for each active degradation mechanism,

f.

Total number and percentage of tubes plugged to date,

g.

The results of condition monitoring, including the results of tube pulls and in-situ testing, and

h.

The effective plugging percentage for all plugging in each SG.