ML18296A418
| ML18296A418 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/13/2018 |
| From: | NRC/NRO/DLSE/LB4 |
| To: | Southern Nuclear Operating Co |
| Hearn P/415-1189 | |
| Shared Package | |
| ML18296A412 | List: |
| References | |
| EPID L-2018-LLA-0142 | |
| Download: ML18296A418 (9) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 147 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 3.3.8-2 3.3.8-2 3.3.8-3 3.3.8-3 3.3.8-4 3.3.8-4 3.3.8-5 3.3.8-5 3.3.8-6 3.3.8-6 3.3.8-7 3.3.8-7
--- 3.3.8-8
(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. 147, 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. 147
Technical Specifications ESFAS Instrumentation 3.3.8 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.
E.2 Reduce Reactor Coolant 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> System (RCS) pressure below P-11 (Pressurizer Pressure) interlock.
AND E.3 Establish RCS boron 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> concentration greater than or equal to that necessary to meet the SDM requirements at an RCS temperature of 200°F.
F. As required by Required F.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.
F.2 Be in MODE 4 with the 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> RCS cooling provided by the Normal Residual Heat Removal System (RNS).
VEGP Units 3 and 4 3.3.8 - 2 Amendment No. 148 (Unit 3)
Amendment No. 147 (Unit 4)
Technical Specifications ESFAS Instrumentation 3.3.8 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.
G.2 Establish RCS boron 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> concentration greater than or equal to that necessary to meet the SDM requirements at an RCS temperature of 200°F.
AND G.3 Block Steamline/ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery Feedwater isolation and of RCS boron Safeguards actuations. concentration greater than or equal to that necessary to meet SDM at an RCS temperature of 200°F while in MODE 3 H. As required by Required H.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.
H.2 Be in MODE 5 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> I. As required by Required I.1 Declare affected isolation Immediately Action C.1 and valve(s) inoperable.
referenced in Table 3.3.8-1.
VEGP Units 3 and 4 3.3.8 - 3 Amendment No. 148 (Unit 3)
Amendment No. 147 (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 - 4 Amendment No. 148 (Unit 3)
Amendment No. 147 (Unit 4)
Technical Specifications ESFAS Instrumentation 3.3.8 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME N. As required by Required N.1 Suspend positive reactivity Immediately Action C.1 and additions.
referenced in Table 3.3.8-1. AND N.2 Initiate action to establish Immediately water level 23 feet above the top of the reactor vessel flange.
O. As required by Required O.1 Declare affected isolation Immediately Action C.1 and valve(s) inoperable.
referenced in Table 3.3.8-1. AND O.2 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> P. As required by Required P.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.
P.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> AND P.3 Open a containment air 44 hours1.833 days <br />0.262 weeks <br />0.0603 months <br /> flow path 6 inches in diameter.
Q. As required by Required Q.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action C.1 and referenced in AND Table 3.3.8-1.
Q.2 Be in MODE 4 with at least 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> one cold leg temperature 275°F.
VEGP Units 3 and 4 3.3.8 - 5 Amendment No. 148 (Unit 3)
Amendment No. 147 (Unit 4)
Technical Specifications ESFAS Instrumentation 3.3.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.8.2 Perform CHANNEL OPERATIONAL TEST (COT) in 92 days accordance with Setpoint Program.
SR 3.3.8.3 -----------------------------------------------------------------------
- NOTE -
This surveillance shall include verification that the time constants are adjusted to within limits.
Perform CHANNEL CALIBRATION in accordance 24 months with Setpoint Program.
SR 3.3.8.4 -----------------------------------------------------------------------
- NOTE -
Not applicable to Function 1.a.
Verify ESF RESPONSE TIME is within limit. 24 months on a STAGGERED TEST BASIS VEGP Units 3 and 4 3.3.8 - 6 Amendment No. 148 (Unit 3)
Amendment No. 147 (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)(l) 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 Q
- 11. RCS Cold Leg Temperature (Tcold) - Low 2 1,2,3(c)(l) 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.
(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.
(l) Below the P-11 (Pressurizer Pressure) interlock and RCS boron concentration is less than that necessary to meet the SDM requirements at an RCS temperature of 200°F.
VEGP Units 3 and 4 3.3.8 - 7 Amendment No. 148 (Unit 3)
Amendment No. 147 (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
- 24. Steam Line Pressure - Low 2 1,2,3(c)(l)(m) 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).
(c) Above the P-11 (Pressurizer Pressure) interlock.
(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 when Steam Line Pressure - Low 2 is blocked.
(l) Below the P-11 (Pressurizer Pressure) interlock and RCS boron concentration is less than that necessary to meet the SDM requirements at an RCS temperature of 200°F.
(m) Below the P-11 (Pressurizer Pressure) interlock when Steam Line Pressure - Low 2 is not blocked.
VEGP Units 3 and 4 3.3.8 - 8 Amendment No. 148 (Unit 3)
Amendment No. 147 (Unit 4)