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{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 109 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 3.6.8-1 3.6.8-1 (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, for Changes and SNC shall report the change to the Director of NRO, or the 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 hours. 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. 109, 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. 109}}
{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 109 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 3.6.8-1                             3.6.8-1
 
(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 hours. 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. 109, 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. 109
 
Technical Specifications                      pH Adjustment 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 pH Adjustment LCO 3.6.8            The pH adjustment baskets shall contain  25,920 lbs of trisodium phosphate (TSP).
APPLICABILITY:        MODES 1, 2, 3, and 4.
ACTIONS CONDITION                      REQUIRED ACTION                COMPLETION TIME A. The weight of TSP in      A.1      Restore weight of TSP in    72 hours the pH adjustment                  the pH adjustment baskets baskets not within limit.          to within limit.
B. Required Action            B.1      Be in MODE 3.                6 hours and associated Completion Time not        AND met.
B.2      Be in MODE 5.                84 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE                                  FREQUENCY SR 3.6.8.1        Verify the pH adjustment baskets contain  25,920 lbs  24 months of TSP.
SR 3.6.8.2        Verify a sample from the pH adjustment baskets        24 months provides adequate pH adjustment of the post-accident water.
VEGP Units 3 and 4                          3.6.8 - 1            Amendment No. 110 (Unit 3)
Amendment No. 109 (Unit 4)}}

Revision as of 00:29, 22 October 2019

Attachment - Vogtle Electric Generating Plant Unit 4 Amendment 109 (LAR-17-032)
ML18036A454
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 02/27/2018
From:
NRC/NRO/DNRL
To:
References
EPID L-2017-LLA-0100, LAR 17-032
Download: ML18036A454 (3)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 109 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 3.6.8-1 3.6.8-1

(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 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. 109, 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. 109

Technical Specifications pH Adjustment 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 pH Adjustment LCO 3.6.8 The pH adjustment baskets shall contain 25,920 lbs of trisodium phosphate (TSP).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The weight of TSP in A.1 Restore weight of TSP in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> the pH adjustment the pH adjustment baskets baskets not within limit. to within limit.

B. Required Action B.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 associated Completion Time not AND met.

B.2 Be in MODE 5. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify the pH adjustment baskets contain 25,920 lbs 24 months of TSP.

SR 3.6.8.2 Verify a sample from the pH adjustment baskets 24 months provides adequate pH adjustment of the post-accident water.

VEGP Units 3 and 4 3.6.8 - 1 Amendment No. 110 (Unit 3)

Amendment No. 109 (Unit 4)