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)


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 Amendment No. 132 (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 <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. 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

Technical Specifications ESFAS Instrumentation 3.3.8 VEGP Units 3 and 4 3.3.8 - 4 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N.

As required by Required Action C.1 and referenced in Table 3.3.8-1.

N.1 Suspend positive reactivity additions.

Immediately AND N.2 Initiate action to establish water level 23 feet above the top of the reactor vessel flange.

Immediately O.

As required by Required Action C.1 and referenced in Table 3.3.8-1.

O.1 Declare affected isolation valve(s) inoperable.

Immediately AND O.2 Be in MODE 3.

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

As required by Required Action C.1 and referenced in Table 3.3.8-1.

P.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND P.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> AND P.3 Open a containment air flow path 6 inches in diameter.

44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> Q.

As required by Required Action C.1 and referenced in Table 3.3.8-1.

Q.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND Q.2 Be in MODE 4 with at least one cold leg temperature 275°F.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

Technical Specifications ESFAS Instrumentation 3.3.8 VEGP Units 3 and 4 3.3.8 - 6 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Table 3.3.8-1 (page 1 of 2)

Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED 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) 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) 4 per loop E
12. Reactor Coolant Average Temperature (Tavg)

- Low 1,2 4

D

13. Reactor Coolant Average Temperature (Tavg)

- Low 2 1,2 4

D

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.

Technical Specifications ESFAS Manual Initiation 3.3.9 VEGP Units 3 and 4 3.3.9 - 5 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

Table 3.3.9-1 (page 1 of 2)

Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED 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 Initiation 1,2,3,4(a) 2 switches D

4(b), 5(d) 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 Initiation 1,2,3,4 2 switch sets E

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 -

Manual Initiation 1,2,3,4 2 switches E

5(f) 2 switches J

6(f) 2 switches K

9.

Passive Residual Heat Removal Heat Exchanger Actuation - Manual Initiation 1,2,3,4 2 Switches E

5(c) 2 switches G

10. Chemical and Volume Control System Makeup Isolation - Manual Initiation 1,2,3,4(h) 2 switches F
11. Normal Residual Heat Removal System Isolation - Manual Initiation 1,2,3 2 switch sets F

(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.

Technical Specifications ESFAS Actuation Logic

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

Amendment No. 132 (Unit 4)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.15.1 Perform ACTUATION LOGIC TEST on ESF Coincidence Logic.

92 days on a STAGGERED TEST BASIS SR 3.3.15.2 Perform ACTUATION LOGIC OUTPUT TEST on ESF Actuation.

24 months 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 an actual or simulated actuation signal.

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

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

24 months SR 3.3.15.6

- NOTE -

Only required to be met in MODES 1 and 2.

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

24 months

Technical Specifications RCS P/T Limits 3.4.3 VEGP Units 3 and 4 3.4.3 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4) 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.

- NOTE -

Required Action A.2 shall be completed whenever this Condition is entered.

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

A.1 Restore parameters to within limits.

30 minutes AND A.2 Determine RCS is acceptable for continued operation.

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

Required Action and associated Completion Time of Condition A not met.

B.1 AND B.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours

Technical Specifications RCS Loops 3.4.4 VEGP Units 3 and 4 3.4.4 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 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.

- NOTE -

Required Actions must be completed whenever Condition A is entered.

Requirements of LCO not met in MODE 1 or 2.

A.1 Suspend start of any RCP.

Immediately AND A.2 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.3 Initiate action to fully insert all rods.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.4 Place the Plant Control System in a condition incapable of rod withdrawal.

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

Technical Specifications RCS Loops 3.4.4 VEGP Units 3 and 4 3.4.4 - 2 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

- NOTE -

Required Actions must be completed whenever Condition B is entered.

Requirements of LCO not met in MODE 3, 4, or 5.

B.1 Suspend start of any RCP.

Immediately AND B.2 Initiate action to fully insert all rods.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.3 Place the Plant Control System in a condition incapable of rod withdrawal.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation with variable speed control bypassed.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

Technical Specifications Pressurizer 3.4.5 VEGP Units 3 and 4 3.4.5 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4) 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 not within limit.

A.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.2 Initiate action to fully insert all rods.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.3 Place the Plant Control System in a condition incapable of rod withdrawal.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.4 Be in MODE 4 with at least one cold leg temperature 275°F.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify pressurizer water level 92% of span.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

Technical Specifications Pressurizer Safety Valves 3.4.6 VEGP Units 3 and 4 3.4.6 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4) 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 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 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 valve inoperable.

A.1 Restore valve to OPERABLE status.

15 minutes B.

Required Action and associated Completion Time of Condition A not met.

OR Two pressurizer safety valves inoperable.

B.1 AND B.2 Be in MODE 3.

Be in MODE 4 with at least one cold leg temperature 275°F.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 24 hours

Technical Specifications Minimum RCS Flow 3.4.8 VEGP Units 3 and 4 3.4.8 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4) 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.

- NOTE -

Required Action A.2 shall be completed prior to starting any RCP whenever this Condition is entered.

No RCP in operation.

A.1 Isolate all sources of unborated water.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND 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 />

Technical Specifications Minimum RCS Flow 3.4.8 VEGP Units 3 and 4 3.4.8 - 2 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify at least one RCP is in operation with total flow through the core 3,000 gpm.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

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

Amendment No. 132 (Unit 4) 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 isolated when the accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

A.1 Isolate affected accumulator.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

Technical Specifications RVHV 3.4.16 VEGP Units 3 and 4 3.4.16 - 1 Amendment No. 133 (Unit 3)

Amendment No. 132 (Unit 4) 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 inoperable.

A.1 Restore flow path to OPERABLE status.

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

Two flow paths inoperable.

B.1 Restore at least one flow path to OPERABLE status.

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

Required Action and associated Completion Time not met.

C.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND C.2 Be in MODE 4 with at least one cold leg temperature 275°F.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify each RVHV valve strokes open.

In accordance with the Inservice Testing Program