ML18100A075

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Attachment - Vogtle Electric Generating Plant Unit 3 Amendment 126 LAR-17-021
ML18100A075
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 06/07/2018
From: Peter Hearn
NRC/NRO/DNRL/LB4
To: Whitley B
Southern Nuclear Operating Co
hearn p c/415-1189
Shared Package
ML18100A069 List:
References
EPID L-2017-LLA-0131, LAR 17-021
Download: ML18100A075 (10)
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Text

ATTACHMENT TO LICENSE AMENDMENT NO. 126 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 3.3.9-5 3.3.9-5 3.3.19-3 3.3.19-3 3.6.6-1 3.6.6-1 3.7.9-1 3.7.9-1 3.7.9-2 3.7.9-2 3.7.9-3 3.7.9-3 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-237 C-237 C-238 C-238

(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. 126, 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. 126

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 > 7.0 MWt.

VEGP Units 3 and 4 3.3.9 - 5 Amendment No. 126 (Unit 3)

Amendment No. 125 (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 1,2,3,4,5,6(c) 2 switches
8. IRWST injection squib valves 1,2,3,4,5,6 2 switches
9. Containment recirculation valves 1,2,3,4,5,6 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 reactor internals in place.

VEGP Units 3 and 4 3.3.19 - 3 Amendment No. 126 (Unit 3)

Amendment No. 125 (Unit 4)

Technical Specifications PCS 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Passive Containment Cooling System (PCS)

LCO 3.6.6 The passive containment cooling system shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, MODES 5 and 6 with the reactor decay heat > 7.0 MWt.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One passive A.1 Restore flow path to 7 days containment cooling OPERABLE status.

water flow path inoperable.

B. Two passive B.1 Restore one flow path to 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> containment cooling OPERABLE status.

water flow paths inoperable.

C. One or more water C.1 Restore water storage tank 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> storage tank to OPERABLE status.

parameters not within limits.

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 in MODE 1, 2, 3, D.2 Be in MODE 5. 84 hours3.5 days <br />0.5 weeks <br />0.115 months <br /> or 4.

OR LCO not met for reasons other than Condition A, B, or C in MODE 1, 2, 3, or 4.

VEGP Units 3 and 4 3.6.6 - 1 Amendment No. 126 (Unit 3)

Amendment No. 125 (Unit 4)

Technical Specifications Spent Fuel Pool Makeup Water Sources 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Spent Fuel Pool Makeup Water Sources LCO 3.7.9 Spent fuel pool makeup water sources shall be OPERABLE.

- NOTES -

1. OPERABILITY of the cask washdown pit is required when the spent fuel pool decay heat > 4.0 MWt and 7.0 MWt.
2. OPERABILITY of the cask loading pit is required when the spent fuel pool decay heat > 5.0 MWt and 7.0 MWt.
3. OPERABILITY of the Passive Containment Cooling Water Storage Tank (PCCWST) is required as a spent fuel pool makeup water source when the spent fuel pool decay heat > 7.0 MWt. If the reactor decay heat is > 7.0 MWt, the PCCWST must be exclusively available for containment cooling in accordance with LCO 3.6.6.
4. OPERABILITY of the Fuel Transfer Canal is required.

APPLICABILITY: When irradiated fuel assemblies are stored in the spent fuel pool.

ACTIONS

- NOTE -

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Initiate action to restore the Immediately spent fuel pool makeup required makeup water water sources source(s) to OPERABLE inoperable. status.

VEGP Units 3 and 4 3.7.9 - 1 Amendment No. 126 (Unit 3)

Amendment No. 125 (Unit 4)

Technical Specifications Spent Fuel Pool Makeup Water Sources 3.7.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 -----------------------------------------------------------------------

- NOTE -

Only required to be performed when spent fuel pool decay heat is > 7.0 MWt.

Verify one passive containment cooling system, 7 days motor-operated valve in each flow path is closed and locked, sealed, or otherwise secured in position.

SR 3.7.9.2 -----------------------------------------------------------------------

- NOTE -

Only required to be performed when spent fuel pool decay heat is > 7.0 MWt.

Verify the PCCWST volume is 756,700 gallons. 7 days SR 3.7.9.3 -----------------------------------------------------------------------

- NOTE -

Only required to be performed when spent fuel pool decay heat is 7.0 MWt.

Verify the water level in the cask washdown pit is 31 days 13.75 ft.

SR 3.7.9.4 -----------------------------------------------------------------------

- NOTE -

Only required to be performed when spent fuel pool decay heat is > 5.0 MWt and 7.0 MWt.

Verify the water level in the cask loading pit is 31 days 43.9 ft. and in communication with the spent fuel pool.

SR 3.7.9.5 Verify the fuel transfer canal is in communication with 31 days the spent fuel pool.

VEGP Units 3 and 4 3.7.9 - 2 Amendment No. 126 (Unit 3)

Amendment No. 125 (Unit 4)

Technical Specifications Spent Fuel Pool Makeup Water Sources 3.7.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.9.6 Verify the spent fuel pool makeup isolation valves In accordance with PCS-PL-V009, PCS-PL-V045, PCS-PL-V051, SFS- the Inservice PL-V042, SFS-PL-V045, SFS-PL-V049, SFS-PL- Testing Program V066, and SFS-PL-V068 are OPERABLE in accordance with the Inservice Testing Program.

VEGP Units 3 and 4 3.7.9 - 3 Amendment No. 126 (Unit 3)

Amendment No. 125 (Unit 4)

Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria iii) Inspection will be performed iii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built equipment including equipment including anchorage anchorage is seismically is seismically bounded by the bounded by the tested or tested or analyzed conditions. analyzed conditions.

397 2.3.07.05.ii Not used per Amendment No. 85 398 2.3.07.05.iii Not used per Amendment No. 85 399 2.3.07.06a 6.a) The Class 1E components Testing will be performed on the A simulated test signal exists identified in Table 2.3.7-1 are powered SFS by providing a simulated at the Class 1E components from their respective Class 1E division. test signal in each Class 1E identified in Table 2.3.7-1 division. when the assigned Class 1E division is provided the test signal.

400 2.3.07.06b Not used per Amendment No. 85 401 2.3.07.07a Not used per Amendment No. 85 402 2.3.07.07b.i 7.b) The SFS provides spent fuel i) Inspection will be performed i) The volume of the spent cooling for 7 days by boiling the spent to verify that the spent fuel pool fuel pool, fuel transfer canal, fuel pool water and makeup water from includes a sufficient volume of and both gate areas above the on-site storage tanks. water. fuel assemblies and below the spent fuel pool cooling suction piping is greater than or equal to 130,350 gallons.

403 2.3.07.07b.ii 7.b) The SFS provides spent fuel ii) Inspection will be performed ii) The water volume of the cooling for 7 days by boiling the spent to verify the cask washdown pit cask washdown pit from the fuel pool water and makeup water from includes sufficient volume of cask washdown pit floor to on-site storage tanks. water. 13.75 feet above the cask washdown pit floor is greater than or equal to 34,100 gallons.

404 2.3.07.07b.iii Not used per Amendment No. 85 405 2.3.07.07b.iv Not used per Amendment No. 85 C-237 Amendment No. 126

Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 406 2.3.07.07b.v Not used per Amendment No. 85 407 2.3.07.07b.vi Not used per Amendment No. 85 881 2.3.07.07b.vii 7.b) The SFS provides spent fuel vii) Inspection will be vii) The water volume of the cooling for 7 days by boiling the spent performed to verify the cask cask loading pit above the fuel pool water and makeup water from loading pit includes sufficient bottom of the gate and below on-site storage tanks. volume of water. the spent fuel pool cooling suction piping is greater than or equal to 46,050 gallons.

408 2.3.07.07c 7c) The SFS provides check valves in Exercise testing of the check Each check valve changes the drain line from the refueling cavity valves with active safety- position as indicated on to prevent flooding of the refueling functions identified in Table Table 2.3.7-1.

cavity during containment flooding. 2.3.7-1 will be performed under pre-operational test pressure, temperature and flow conditions.

8. The SFS provides the nonsafety- ii) Testing will be performed to ii) Each SFS pump produces related function of removing spent fuel confirm that each SFS pump at least 900 gpm through its decay heat using pumped flow through provides flow through its heat heat exchanger.

a heat exchanger. exchanger when taking suction from the SFP and returning flow to the SFP.

9. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.3.7-1 can be retrieved in the retrievability of the safety- identified in Table 2.3.7-1 can MCR. related displays in the MCR. be retrieved in the MCR.
10. Controls exist in the MCR to cause Testing will be performed to Controls in the MCR cause the pumps identified in Table 2.3.7-3 to actuate the pumps identified in pumps identified in Table perform their listed functions. Table 2.3.7-3 using controls in 2.3.7-3 to perform the listed the MCR. functions.
11. Displays of the SFS parameters Inspection will be performed for Displays of the SFS identified in Table 2.3.7-3 can be retrievability in the MCR of the parameters identified in Table retrieved in the MCR. displays identified in Table 2.3.7-3 are retrieved in the 2.3.7-3. MCR.

409 2.3.07.08.i 8. The SFS provides the nonsafety- i) Inspection will be performed i) A report exists and related function of removing spent fuel for the existence of a report that concludes that the heat decay heat using pumped flow through determines the heat removal transfer characteristic, UA, of a heat exchanger. capability of the SFS heat each SFS heat exchanger is exchangers. greater than or equal to 2.2 million Btu/hr-°F.

410 2.3.07.08.ii Not used per Amendment No. 113 411 2.3.07.09 Not used per Amendment No. 113 412 2.3.07.10 Not used per Amendment No. 113 413 2.3.07.11 Not used per Amendment No. 113 C-238 Amendment No. 126

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