ML18159A442

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Attachment - Vogtle Electric Generating Plant, Unit 4 (LAR-18-004)
ML18159A442
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/12/2018
From: Manny Comar
NRC/NRO/DNRL/LB4
To: Whitley B
Southern Nuclear Operating Co
comar m/415-3863
Shared Package
ML18159A437 List:
References
EPID L-2018-LLA-0018, LAR 18-004
Download: ML18159A442 (15)
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Text

ATTACHMENT TO LICENSE AMENDMENT NO. 132 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 Nos. NPF-91 and NPF-92 REMOVE INSERT 3.3.8-4 3.3.8-4 3.3.8-6 3.3.8-6 3.3.9-5 3.3.9-5 3.3.15-2 3.3.15-2 3.4.3-1 3.4.3-1 3.4.4-1 3.4.4-1 3.4.4-2 3.4.4-2 3.4.5-1 3.4.5-1 3.4.6-1 3.4.6-1 3.4.8-1 3.4.8-1 3.4.8-2 3.4.8-2 3.4.14-1 3.4.14-1 3.4.16-1 3.4.16-1

(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 hours1 days <br />0.143 weeks <br />0.0329 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. 132, 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).

(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. 132

Technical Specifications ESFAS Instrumentation 3.3.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. As required by Required N.1 Suspend positive reactivity Immediately Action C.1 and additions.

referenced in Table 3.3.8-1. AND N.2 Initiate action to establish Immediately water level 23 feet above the top of the reactor vessel flange.

O. As required by Required O.1 Declare affected isolation Immediately Action C.1 and valve(s) inoperable.

referenced in Table 3.3.8-1. AND O.2 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> P. As required by Required P.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.

P.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> AND P.3 Open a containment air 44 hours1.833 days <br />0.262 weeks <br />0.0603 months <br /> flow path 6 inches in diameter.

Q. As required by Required Q.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.

Q.2 Be in MODE 4 with at least 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> one cold leg temperature 275°F.

VEGP Units 3 and 4 3.3.8 - 4 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

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 (b)
3. Containment Radioactivity - High 1,2,3,4 4 l
4. Containment Radioactivity - High 2 1,2,3 4 l
5. Pressurizer Pressure - Low 3 1,2,3(c) 4 E
6. Pressurizer Water Level - Low 1,2 4 D (b)
7. Pressurizer Water Level - Low 2 1,2,3,4 4 F 4(d),5(e) 4 J
8. Pressurizer Water Level - High 1,2,3 4 l (f)
9. Pressurizer Water Level - High 2 1,2,3,4 4 l (f)
10. Pressurizer Water Level - High 3 1,2,3,4 4 Q
11. RCS Cold Leg Temperature (Tcold) - Low 2 1,2,3(c) 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 4 K 6(g) 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, when the RCS boron concentration is below that necessary to meet the SDM requirements at an RCS temperature of 200°F.

(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.

VEGP Units 3 and 4 3.3.8 - 6 Amendment No. 133 (Unit 3)

Amendment No. 132 (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 Initiation (b) (d) 4 ,5 2 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 Initiation 5(d) 2 switch sets H
7. ADS Stage 4 Actuation - Manual Initiation 1,2,3,4 2 switch sets E 5 2 switch sets H 6(e) 2 switch sets I
8. Passive Containment Cooling Actuation - 1,2,3,4 2 switches E Manual Initiation (f) 5 2 switches J (f) 6 2 switches K
9. Passive Residual Heat Removal Heat 1,2,3,4 2 Switches E Exchanger Actuation - Manual Initiation 5(c) 2 switches G (h)
10. Chemical and Volume Control System Makeup 1,2,3,4 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.

VEGP Units 3 and 4 3.3.9 - 5 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications ESFAS Actuation Logic

- Operating 3.3.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.15.1 Perform ACTUATION LOGIC TEST on ESF 92 days on a Coincidence Logic. STAGGERED TEST BASIS SR 3.3.15.2 Perform ACTUATION LOGIC OUTPUT TEST on ESF 24 months Actuation.

SR 3.3.15.3 -----------------------------------------------------------------------

- NOTE -

Only required to be met when all four cold leg temperatures are > 275°F.

Verify pressurizer heater circuit breakers trip open on 24 months an actual or simulated actuation signal.

SR 3.3.15.4 Verify reactor coolant pump breakers trip open on an 24 months actual or simulated actuation signal.

SR 3.3.15.5 Verify main feedwater and startup feedwater pump 24 months breakers trip open on an actual or simulated actuation signal.

SR 3.3.15.6 -----------------------------------------------------------------------

- NOTE -

Only required to be met in MODES 1 and 2.

24 months Verify auxiliary spray and purification line isolation valves actuate to the isolation position on an actual or simulated actuation signal.

VEGP Units 3 and 4 3.3.15 - 2 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.

- NOTE -

No reactor coolant pump (RCP) shall be started with any RCS cold leg temperature 350°F unless the secondary side water temperature of each steam generator is 50°F above each of the RCS cold leg temperatures and the RCP is started at 25% of rated RCP speed.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- A.1 Restore parameters to 30 minutes

- NOTE - within limits.

Required Action A.2 shall be completed AND whenever this Condition is entered. A.2 Determine RCS is 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />

acceptable for continued operation.

Requirements of LCO not met in MODE 1, 2, 3, or 4.

B. Required Action B.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and associated Completion Time of AND Condition A not met.

B.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> VEGP Units 3 and 4 3.4.3 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications RCS Loops 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops LCO 3.4.4 Two RCS loops shall be OPERABLE with four Reactor Coolant Pumps (RCPs) in operation with variable speed control bypassed.

- NOTE -

All RCPs may be removed from operation in MODE 3, 4, or 5 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and
b. Core outlet temperature is maintained at least 10°F below saturation temperature.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 with Plant Control System capable of rod withdrawal or one or more rods not fully inserted.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- A.1 Suspend start of any RCP. Immediately

- NOTE -

Required Actions must AND be completed whenever Condition A is entered. A.2 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> AND Requirements of LCO not met in MODE 1 or 2. A.3 Initiate action to fully insert 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> all rods.

AND A.4 Place the Plant Control 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> System in a condition incapable of rod withdrawal.

VEGP Units 3 and 4 3.4.4 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications RCS Loops 3.4.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. -------------------------------- B.1 Suspend start of any RCP. Immediately

- NOTE -

Required Actions must AND be completed whenever Condition B is entered. B.2 Initiate action to fully insert 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

all rods.

Requirements of LCO AND not met in MODE 3, 4, or 5. B.3 Place the Plant Control 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> System in a condition incapable of rod withdrawal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation with variable 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> speed control bypassed.

VEGP Units 3 and 4 3.4.4 - 2 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications Pressurizer 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 Pressurizer LCO 3.4.5 The pressurizer water level shall be 92% of span.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all four cold leg temperatures > 275°F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level A.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> not within limit.

AND A.2 Initiate action to fully insert 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> all rods.

AND A.3 Place the Plant Control 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> System in a condition incapable of rod withdrawal.

AND A.4 Be in MODE 4 with at least 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> one cold leg temperature 275°F.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify pressurizer water level 92% of span. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> VEGP Units 3 and 4 3.4.5 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications Pressurizer Safety Valves 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 Pressurizer Safety Valves LCO 3.4.6 Two pressurizer safety valves shall be OPERABLE with lift settings 2460 psig and 2510 psig.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all four cold leg temperatures > 275°F.

- NOTE -

The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. One pressurizer safety valve at a time may be inoperable for hot lift setting adjustment.

This exception is allowed for 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> following entry into MODE 3, provided a preliminary cold setting was made prior to heatup.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action B.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and associated Completion Time of AND Condition A not met.

B.2 Be in MODE 4 with at least 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> OR one cold leg temperature 275°F.

Two pressurizer safety valves inoperable.

VEGP Units 3 and 4 3.4.6 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications Minimum RCS Flow 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Minimum RCS Flow LCO 3.4.8 At least one Reactor Coolant Pump (RCP) shall be in operation with a total flow through the core of 3,000 gpm.

- NOTE -

a. All RCPs may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period for the purpose of testing; or
b. With no RCPs in operation, an unborated water source through the chemical mixing tank may be unisolated under administrative controls for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for the purpose of chemical addition to the pressurizer; provided:
i. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and ii. Core outlet temperature is maintained at least 10°F below saturation temperature.

APPLICABILITY: MODES 3, 4, and 5 with unborated water sources not isolated from the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- A.1 Isolate all sources of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

- NOTE - unborated water.

Required Action A.2 shall be completed prior AND to starting any RCP whenever this Condition A.2 Perform SR 3.1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is entered.

No RCP in operation.

VEGP Units 3 and 4 3.4.8 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications Minimum RCS Flow 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify at least one RCP is in operation with total flow 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> through the core 3,000 gpm.

VEGP Units 3 and 4 3.4.8 - 2 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications LTOP 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 Low Temperature Overpressure Protection (LTOP)

LCO 3.4.14 At least one of the following overpressure protection methods shall be OPERABLE, with the accumulators isolated:

a. Two Normal Residual Heat Removal System (RNS) suction relief valves and Chemical and Volume Control System (CVS) makeup line containment isolation valve, CVS-PL-V091, closed; or
b. The RCS depressurized and an RCS vent of 4.15 square inches.

- NOTE -

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

APPLICABILITY: MODE 4 when any cold leg temperature is 275°F, MODE 5, MODE 6 when the reactor vessel head is on.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. An accumulator not A.1 Isolate affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolated when the accumulator.

accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

VEGP Units 3 and 4 3.4.14 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Technical Specifications RVHV 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 Reactor Vessel Head Vent (RVHV)

LCO 3.4.16 The Reactor Vessel Head Vent shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all four cold leg temperatures > 275°F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One flow path A.1 Restore flow path to 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> inoperable. OPERABLE status.

B. Two flow paths B.1 Restore at least one flow 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> inoperable. path to OPERABLE status.

C. Required Action C.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and associated Completion Time not AND met.

C.2 Be in MODE 4 with at least 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> one cold leg temperature 275°F.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify each RVHV valve strokes open. In accordance with the Inservice Testing Program VEGP Units 3 and 4 3.4.16 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

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