ML18191B094

Attachment - Vogtle Electric Generating Plant Unit 3 Amendment 137 (LAR-18-012)

ML18191B094
Person / Time
Site:	Vogtle
Issue date:	08/07/2018
From:	NRC/NRO/DLSE/LB4
To:	Southern Nuclear Operating Co
Kallan P/415-2809
Shared Package
ML18191B091	List: ML18191B092 ML18191B093 ML18191B094 ML18191B095 ML18191B096 ML18191B097
References
EPID L-2018-LLA-0102, LAR-18-012
Download: ML18191B094 (3)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 137 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 3.3.17-3 3.3.17-3

(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. 137, 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. 137

Technical Specifications PAM Instrumentation 3.3.17 VEGP Units 3 and 4 3.3.17 - 3 Amendment No. 137 (Unit 3)

Amendment No. 136 (Unit 4)

Table 3.3.17-1 (page 1 of 1)

Post-Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1.

Neutron Flux (Intermediate Range) 2 E

2.

Reactor Coolant System (RCS) Hot Leg Temperature (Wide Range) 2 E

3.

RCS Cold Leg Temperature (Wide Range) 2 E

4.

RCS Pressure (Wide Range) 2 E

5.

RCS Subcooling Monitor 2

E

6.

Containment Water Level 2

E

7.

Containment Pressure 2

E

8.

Containment Pressure (Extended Range) 2 E

9.

Containment Area Radiation (High Range) 2 E

10.

Pressurizer Level and Associated Reference Leg Temperature 2

E

11.

In-Containment Refueling Water Storage Tank (IRWST)

Wide Range Water Level 2

E

12.

Passive Residual Heat Removal (PRHR) Heat Removal 2

E

13.

Core Exit Temperature -- Quadrant 1 2(a)

E

14.

Core Exit Temperature -- Quadrant 2 2(a)

E

15.

Core Exit Temperature -- Quadrant 3 2(a)

E

16.

Core Exit Temperature -- Quadrant 4 2(a)

E

17.

Passive Containment Cooling System (PCS) Heat Removal 2

E

18.

Penetration Flow Path Remotely Operated Containment Isolation Valve Position 2 per penetration flow path(b)(c)(d)

E

19.

IRWST to Normal Residual Heat Removal System (RNS) Suction Valve Status 2

E (a) A channel consists of two thermocouples within a single division. Each quadrant contains two divisions. The minimum requirement is two OPERABLE thermocouples in each of the two divisions.

(b) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(c) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(d) Penetration Flow Path Remotely Operated Containment Isolation Valve Position applies to components that receive the ESF containment isolation signal (T signal).