ML18075A101

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Attachment - VEGP U3 Amendment 118(LAR-17-027)
ML18075A101
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/29/2018
From: Chandu Patel
NRC/NRO/DNRL/LB4
To: Whitley B
Southern Nuclear Operating Co
patel c/415-3025
Shared Package
ML18075A094 List:
References
EPID L-2017-LLA-0098, LAR-17-027
Download: ML18075A101 (26)
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Text

ATTACHMENT TO LICENSE AMENDMENT NO. 118 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 Nos. NPF-91 and NPF-92 REMOVE INSERT 1.1-6 1.1-6 3.3.8-3 3.3.8-3 3.3.8-6 3.3.8-6 3.3.8-7 3.3.8-7 3.3.9-2 3.3.9-2 3.3.9-3 3.3.9-3 3.3.9-5 3.3.9-5 3.3.10-2 3.3.10-2 3.3.10-3 3.3.10-3 3.3.10-5 3.3.10-5 3.3.15-2 3.3.15-2 3.3.16-4 3.3.16-4 3.4.11-1 3.4.11-1 3.4.11-2 3.4.11-2

--- 3.4.11-3 3.4.12-1 3.4.12-1 3.4.12-2 3.4.12-2 3.4.13-1 3.4.13-1 3.4.13-2 3.4.13-2

--- 3.4.13-3 3.5.3-1 3.5.3-1 3.5.3-2 3.5.3-2 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-409 C-409 C-426 C-426

(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR 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. 118, 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. 118

Technical Specifications Definitions 1.1 1.1 Definitions TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip actuating device OPERATIONAL TEST and verifying the OPERABILITY of all devices in the channel (TADOT) required for trip actuating device OPERABILITY. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy. The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps.

VENTED VENTED shall be the condition when all required flow paths in ADS stage 1, 2, and 3, or alternative flow path with equivalent area, required by LCO 3.4.13, "Automatic Depressurization System (ADS) - Shutdown, RCS Open," are open.

VEGP Units 3 and 4 1.1 - 6 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS Instrumentation 3.3.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required J.1 Be in MODE 5. 37 hours1.542 days <br />0.22 weeks <br />0.0507 months <br /> with three or Action C.1 and more inoperable referenced in channels Table 3.3.8-1.

AND 180 hours7.5 days <br />1.071 weeks <br />0.247 months <br /> AND J.2 Initiate action to establish 180 hours7.5 days <br />1.071 weeks <br />0.247 months <br /> RCS VENTED.

K. As required by Required K.1 Suspend positive reactivity Immediately Action C.1 and additions.

referenced in AND Table 3.3.8-1.

K.2 Initiate action to open RCS Immediately pressure boundary and establish 20%

pressurizer level.

L. As required by Required L.1 Suspend positive reactivity Immediately Action C.1 and additions.

referenced in Table 3.3.8-1. AND L.2 Initiate action to remove Immediately the upper internals.

M. As required by Required M.1 Suspend positive reactivity Immediately Action C.1 and additions.

referenced in Table 3.3.8-1. AND M.2 Be in MODE 5. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> AND M.3 Initiate action to establish a 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> pressurizer level 20%

with the RCS pressure boundary intact.

VEGP Units 3 and 4 3.3.8 - 3 Amendment No. 118 (Unit 3)

Amendment No. 117 (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 F
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) Above the P-19 (RCS Pressure) interlock with the RCS not being cooled by RNS.

(g) With upper internals in place.

VEGP Units 3 and 4 3.3.8 - 6 Amendment No. 118 (Unit 3)

Amendment No. 117 (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 (d) (h) 4 ,5 4 per OPERABLE J tank
16. CMT Level - Low 6 1,2,3,4(b) 4 per tank F (d) (h) 4 ,5 4 per OPERABLE J tank
17. Source Range Neutron Flux Doubling 2(i),3(i),4(j) 4 I (j) 5 4 I (b)
18. IRWST Level - Low 3 1,2,3,4 4 F 4(d),5 4 M 6(g) 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 1,2,3,4(b) 4 per SG F (b)
21. SG Wide Range Water Level - Low 1,2,3,4 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 1,2,3,4(b) 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).

(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 except during intentional approach to criticality.

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

(k) Below the P-11 (Pressurizer Pressure) interlock.

VEGP Units 3 and 4 3.3.8 - 7 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS Manual Initiation 3.3.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Requried Action and C.1 Enter the Condition Immediately associated Completion referenced in Table 3.3.9-1 Time of Condition A or for the channel(s).

B not met.

OR One or more Functions with two channels inoperable.

D. As required by D.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Required Action C.1 and referenced in AND Table 3.3.9-1.

D.2 Be in MODE 4 with the 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> Reactor Coolant System (RCS) cooling provided by the Normal Residual Heat Removal System (RNS).

E. As required by E.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Required Action C.1 and referenced in AND Table 3.3.9-1.

E.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> F. As required by F.1 Declare affected isolation Immediately Required Action C.1 valve(s) inoperable.

and referenced in Table 3.3.9-1.

G. As required by G.1 Be in MODE 5. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Required Action C.1 and referenced in AND Table 3.3.9-1.

G.2 Initiate action to establish 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> RCS VENTED.

VEGP Units 3 and 4 3.3.9 - 2 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS Manual Initiation 3.3.9 ACTIONS (continued)

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

and referenced in Table 3.3.9-1. AND H.2 Initiate action to establish Immediately RCS VENTED and establish 20%

pressurizer level.

I. As required by I.1 Suspend positive reactivity Immediately Required Action C.1 additions.

and referenced in Table 3.3.9-1. AND I.2 Initiate action to remove Immediately the upper internals.

J. As required by J.1 Suspend positive reactivity Immediately Required Action C.1 additions.

and referenced in Table 3.3.9-1. AND J.2 Be in MODE 5. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> AND J.3 Initiate action to establish a 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> pressurizer level 20%

with the RCS pressure boundary intact.

K. As required by K.1 Suspend positive reactivity Immediately Required Action C.1 additions.

and referenced in Table 3.3.9-1. AND K.2 Initiate action to establish Immediately water level 23 feet above the top of the reactor vessel flange.

VEGP Units 3 and 4 3.3.9 - 3 Amendment No. 118 (Unit 3)

Amendment No. 117 (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 (a)
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 > 6.0 MWt.

VEGP Units 3 and 4 3.3.9 - 5 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS RCS Hot Leg Level Instrumentation 3.3.10 ACTIONS (continued)

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

referenced in Table 3.3.10-1. AND C.2 Initiate action to establish a Immediately pressurizer level above the P-12 (Pressurizer Level) interlock.

D. As required by Required -------------------------------------------------

Action B.1 and - NOTE -

referenced in Flow path(s) may be unisolated Table 3.3.10-1. intermittently under administrative controls.

D.1.1 Isolate the affected flow 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> path(s).

AND D.1.2.1 Isolate the affected flow 7 days path(s) by use of at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

OR D.1.2.2 Verify the affected flow Once per 7 days path is isolated OR D.2 Initiate action to establish a 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> pressurizer level above the P-12 (Pressurizer Level) interlock.

VEGP Units 3 and 4 3.3.10 - 2 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS RCS Hot Leg Level Instrumentation 3.3.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Initiate action to establish Immediately Action B.1 and water level 23 feet above referenced in the top of the reactor Table 3.3.10-1. vessel flange.

VEGP Units 3 and 4 3.3.10 - 3 Amendment No. 118 (Unit 3)

Amendment No. 117 (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),6(b) 1 per loop C
2. Hot Leg Level - Low 2 5(c) 1 per loop D 6(d) 1 per loop E (a) With CMT actuation on Pressurizer Water Level - Low 2 blocked.

(b) With upper internals in place and with CMT actuation 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.

VEGP Units 3 and 4 3.3.10 - 5 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS Actuation Logic

- Operating 3.3.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.15.1 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.15.2 -----------------------------------------------------------------------

- NOTE -

Only required to be met in MODE 4 above the P-19 (RCS Pressure) interlock with the RCS not being cooled by RNS.

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

SR 3.3.15.3 Verify reactor coolant pump breakers trip open on an 24 months actual or simulated actuation signal.

SR 3.3.15.4 Verify main feedwater and startup feedwater pump 24 months breakers trip open on an actual or simulated actuation signal.

SR 3.3.15.5 -----------------------------------------------------------------------

- 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. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ESFAS Actuation Logic

- Shutdown 3.3.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.16.3 -----------------------------------------------------------------------

- NOTES -

1. Not required to be met in MODE 5 above the P-12 (Pressurizer Level) interlock.
2. Not required to be met in MODE 6 with water level > 23 feet above the top of the reactor vessel flange.

Verify CVS letdown isolation valves actuate to the 24 months isolation position on an actual or simulated actuation signal.

SR 3.3.16.4 ----------------------------------------------------------------------

- NOTE -

Only required to be met in MODE 6.

Verify Spent Fuel Pool Cooling System containment 24 months isolation valves actuate to the isolation position on an actual or simulated actuation signal.

VEGP Units 3 and 4 3.3.16 - 4 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Operating 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Automatic Depressurization System (ADS) - Operating LCO 3.4.11 Ten ADS flow paths shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One flow path in ADS A.1 Restore flow path to 7 days stage 1, 2, or 3 OPERABLE status.

inoperable.

B. One flow path in ADS B.1 Restore flow path to 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> stage 4 inoperable. OPERABLE status.

C. One flow path in ADS C.1 Restore one flow path to 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> stage 1 inoperable and OPERABLE status.

one flow path in ADS stage 2 or 3 inoperable.

OR Two flow paths in ADS stage 1 inoperable.

VEGP Units 3 and 4 3.4.11 - 1 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Operating 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action D.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, B, or C not met. D.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> OR Condition A and Condition B entered concurrently.

OR Three or more flow paths in ADS stage 1, 2, and 3 inoperable.

OR LCO not met for reasons other than Condition A, B, or C.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Verify the motor operated valve in series with each 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> 4th stage ADS valve is open.

SR 3.4.11.2 Verify each stage 1, 2, and 3 ADS valve strokes open. In accordance with the Inservice Testing Program SR 3.4.11.3 Verify each stage 4 ADS valve is OPERABLE in In accordance with accordance with the Inservice Testing Program. the Inservice Testing Program VEGP Units 3 and 4 3.4.11 - 2 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Operating 3.4.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.11.4 Verify each stage 1, 2, and 3 ADS valve actuates to 24 months the open position on an actual or simulated actuation signal.

SR 3.4.11.5 -----------------------------------------------------------------------

- NOTE -

Squib actuation may be excluded.

Verify continuity of the circuit from the Protection 24 months Logic Cabinets to each stage 4 ADS valve.

VEGP Units 3 and 4 3.4.11 - 3 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Shutdown, RCS Intact 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Automatic Depressurization System (ADS) - Shutdown, RCS Intact LCO 3.4.12 A. With reactor subcritical for < 28 hrs:

1. Five flow paths in ADS stage 1, 2, and 3 shall be OPERABLE; and
2. Four flow paths in ADS stage 4 shall be OPERABLE B. With reactor subcritical for 28 hrs:
1. Three flow paths in ADS stage 1, 2, and 3, with a minimum of two flow paths in ADS stage 2 or 3, shall be OPERABLE; and
2. Three flow paths in ADS stage 4 shall be OPERABLE APPLICABILITY: MODE 5 with RCS pressure boundary intact and pressurizer level 20%.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required flow path A.1 Restore required flow path 7 days in ADS stage 1, 2, or 3 to OPERABLE status.

inoperable.

B. One required flow path B.1 Restore required flow path 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> in ADS stage 4 to OPERABLE status.

inoperable.

C. One required flow path C.1 Restore one required flow 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> in ADS stage 1 path to OPERABLE status.

inoperable and one required flow path in ADS stage 2 or 3 inoperable.

OR Two required flow paths in ADS stage 1 inoperable.

VEGP Units 3 and 4 3.4.12 - 1 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Shutdown, RCS Intact 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action D.1 Initiate action to open the Immediately and associated RCS pressure boundary.

Completion Time of Condition A, B, or C not met.

OR Condition A and Condition B entered concurrently.

OR Three or more flow paths in ADS stage 1, 2, and 3 inoperable.

OR LCO not met for reasons other than Condition A, B, or C.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 For flow paths required to be OPERABLE, the SRs of In accordance with LCO 3.4.11, Automatic Depressurization System applicable SRs (ADS) - Operating are applicable.

VEGP Units 3 and 4 3.4.12 - 2 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Shutdown, RCS Open 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Open LCO 3.4.13 A. With reactor subcritical for < 28 hrs:

1. Five flow paths in ADS stage 1, 2, and 3 shall be open; and
2. Four flow paths in ADS stage 4 shall be OPERABLE.

B. With reactor subcritical for 28 hrs:

1. Three flow paths in ADS stage 1, 2, and 3, with a minimum of two flow paths in ADS stage 2 or 3, shall be open; and
2. Three flow paths in ADS stage 4 shall be OPERABLE.

- NOTE -

In MODE 5, required flow paths in ADS stage 1, 2, and 3 may be closed provided they meet OPERABILITY requirements of LCO 3.4.12, ADS -

Shutdown, RCS Intact, for the following:

a. To facilitate RCS vacuum fill operations until a pressurizer level of 20% is established; or
b. To facilitate LCO compliance during transitions between LCO 3.4.12 and LCO 3.4.13.

APPLICABILITY: MODE 5 with pressurizer level < 20%,

MODE 5 with RCS pressure boundary open, MODE 6 with upper internals in place.

VEGP Units 3 and 4 3.4.13 - 1 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Shutdown, RCS Open 3.4.13 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required flow path A.1 Restore required flow path 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> in ADS stage 1, 2, and in ADS stage 1, 2, and 3 to 3 not open. open status.

OR A.2 Open alternative flow 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> path(s) with an equivalent area.

B. One required flow path B.1 Restore required flow path 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> in ADS stage 4 in ADS stage 4 to inoperable. OPERABLE status.

OR B.2 Open an alternative flow 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> path with an equivalent area.

C. Required Action C.1 Initiate action to fill the Immediately and associated RCS to establish 20%

Completion Time of pressurizer level.

Condition A or B not met in MODE 5. AND OR C.2 Suspend positive reactivity Immediately additions.

Condition A and Condition B entered AND concurrently in MODE 5. C.3 Initiate action to establish Immediately RCS VENTED condition.

OR LCO not met for reasons other than Condition A or B in MODE 5.

VEGP Units 3 and 4 3.4.13 - 2 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications ADS - Shutdown, RCS Open 3.4.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action D.1 Initiate action to remove Immediately and associated the upper internals.

Completion Time of Condition A or B not met AND in MODE 6.

D.2 Suspend positive reactivity Immediately OR additions.

Condition A and Condition B entered concurrently in MODE 6.

OR LCO not met for reasons other than Condition A or B in MODE 6.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 Verify each required ADS stage 1, 2, and 3 valve is in 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> the open position.

SR 3.4.13.2 For each required flow path in ADS stage 4, the In accordance with following SRs are applicable: applicable SRs SR 3.4.11.1 SR 3.4.11.3 SR 3.4.11.5 VEGP Units 3 and 4 3.4.13 - 3 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications CMTs - Shutdown, RCS Intact 3.5.3 3.5 PASSIVE CORE COOLING SYSTEM (PXS) 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, Reactor Coolant System (RCS) Intact LCO 3.5.3 One CMT shall be OPERABLE.

APPLICABILITY: MODE 4 with the RCS cooling provided by the Normal Residual Heat Removal System (RNS).

MODE 5 with the RCS not VENTED.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required CMT A.1 Restore required isolation 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> inoperable due to one valve to OPERABLE outlet isolation valve status.

inoperable.

B. Required CMT B.1 Restore water temperature 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> inoperable due to water and boron concentration to temperature or boron within limits.

concentration not within limits.

C. Required CMT inlet line C.1 Restore CMT inlet line 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> noncondensible gas noncondensible gas volume not within limit volume to within limit.

in MODE 4.

OR C.2 Be in MODE 5. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> D. Required CMT D.1 Restore required CMT to 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> inoperable for reasons OPERABLE status.

other than Condition A, B, or C.

E. Required Action E.1 Initiate action to be in Immediately and associated MODE 5 with RCS Completion Time of VENTED.

Condition A, B, or D not met.

VEGP Units 3 and 4 3.5.3 - 1 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

Technical Specifications CMTs - Shutdown, RCS Intact 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 For the CMT required to be OPERABLE, the following In accordance with SRs are applicable: applicable SRs SR 3.5.2.1 SR 3.5.2.2 SR 3.5.2.3 SR 3.5.2.5 SR 3.5.2.6 SR 3.5.2.7 SR 3.5.2.8 SR 3.5.3.2 -----------------------------------------------------------------------

- NOTE -

Only required to be met in MODE 4 with RCS cooling provided by the Normal Residual Heat Removal System (RNS).

For the CMT required to be OPERABLE, the following In accordance with SR is applicable: applicable SR SR 3.5.2.4 VEGP Units 3 and 4 3.5.3 - 2 Amendment No. 118 (Unit 3)

Amendment No. 117 (Unit 4)

1. The physical arrangement of the nuclear island structures, the annex building, and the turbine building is as described in the Design Description of this Section 3.3, and as shown on Figures 3.3-1 through 3.3-14. The physical arrangement of the radwaste building and the diesel generator building is as described in the Design Description of this Section 3.3.
2. a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads, as specified in the Design Description, without loss of structural integrity and the safety-related functions. The design bases loads are those loads associated with:
  • Normal plant operation (including dead loads, live loads, lateral earth pressure loads, and equipment loads, including hydrodynamic loads, temperature and equipment vibration);
  • Internal events (including flood, pipe rupture, equipment failure, and equipment failure generated missiles).

b) Site grade level is located relative to floor elevation 100-0 per Table 3.3-5. Floor elevation 100-0 is defined as the elevation of the floor at design plant grade.

c) The containment and its penetrations are designed and constructed to ASME Code Section III, Class MC.(1) d) The containment and its penetrations retain their pressure boundary integrity associated with the design pressure.

e) The containment and its penetrations maintain the containment leakage rate less than the maximum allowable leakage rate associated with the peak containment pressure for the design basis accident.

f) The key dimensions of the nuclear island structures are as defined on Table 3.3-5.

g) The containment vessel greater than 7 feet above the operating deck provides a heat transfer surface. A free volume exists inside the containment shell above the operating deck.

h) The containment free volume below elevation 107.68 provides containment floodup during a postulated loss-of-coolant accident.

3. Walls and floors of the nuclear island structures as defined on Table 3.3-1, except for designed openings and penetrations, provide shielding during normal operations.
4. a) Walls and floors of the annex building as defined on Table 3.3-1, except for designed openings and penetrations, provide shielding during normal operations.

b) The walls on the outside of the waste accumulation room in the radwaste building provide shielding from accumulated waste.

1. Containment isolation devices are addressed in subsection 2.2.1, Containment System.

C-409 Amendment No. 118

Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 772 3.3.00.02d Not used per Amendment No. 85 773 3.3.00.02e Not used per Amendment No. 85 774 3.3.00.02f 2.f) The key dimensions of nuclear An inspection will be performed A report exists and concludes island structures are defined on of the as-built configuration of that the key dimensions of the Table 3.3-5. the nuclear island structures. as-built nuclear island structures are consistent with the dimensions defined on Table 3.3-5.

775 3.3.00.02g 2.g) The containment vessel greater The maximum containment The containment vessel than 7 feet above the operating deck vessel inside height from the maximum inside height from provides a heat transfer surface. A free operating deck is measured and the operating deck is 146'-7" volume exists inside the containment the inner radius below the spring (with tolerance of +12", -6"),

shell above the operating deck. line is measured at two and the inside diameter is orthogonal radial directions at 130 feet nominal (with one elevation. tolerance of +12", -6").

776 3.3.00.02h 2.h) The free volume in the An inspection will be performed A report exists and concludes containment allows for floodup to of the as-built containment that the floodup volume of support long-term core cooling for structures and equipment. The this portion of the containment postulated loss-of-coolant accidents. portions of the containment is less than 71,960 ft3 to an included in this inspection are elevation of 107.68'.

the volumes that flood with a loss-of-coolant accident in passive core cooling system valve/equipment room B (11207). The in-containment refueling water storage tank volume is excluded from this inspection.

C-426 Amendment No. 118

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