ML050680450
| ML050680450 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/07/2005 |
| From: | NRC/NRR/DLPM |
| To: | |
| Gratton C, NRR/DLPM, 415-1055 | |
| References | |
| TAC MC3328, TAC MC3329 | |
| Download: ML050680450 (5) | |
Text
TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS...........................
3.6.1-1 3.6.1 Containment...................................................
3.6.1-1 3.6.2 Containment Air Locks..................................................
3.6.2-1 3.6.3 Containment Isolation Valves.............................
3.6.3-1 3.6.4 Containment Pressure..................................................
3.6.4-1 3.6.5 Containment Air Temperature..................................................
3.6.5-1 3.6.6 Containment Spray and Cooling Systems..............................................
3.6.6-1 3.6.7 Deleted...........................;................
3.6.7-1 3.7 PLANT SYSTEMS..........................
3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs).........................
3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs).........................
3.7.2-1 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves...
3.7.3-1 3.7.4 Atmospheric Relief Valves (ARVs)..................................................
3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System.............
3.7.5-1 3.7.6 Condensate Storage Tank (CST) - (Redundant CSTs)............................
3.7.6-1 3.7.6a Condensate Storage Tank (CST) - (Non-redundant CSTs)...................
3.7.6a-1 3.7.7 Component Cooling Water (CCW) System...........................................
3.7.7-1 3.7.8 Nuclear Service Cooling Water (NSCW) System..................................
3.7.8-1 3.7.9 Ultimate Heat Sink (UHS).................
3.7.9-1 3.7.10 Control Room Emergency Filtration System (CREFS) - Both Units Operating.3.7.10-1 3.7.11 Control Room Emergency Filtration System (CREFS) - One Unit Operating.3.7.11-1 3.7.12 Control Room Emergency Filtration System (CREFS) - Both Units Shutdown.3.7.12-1 3.7.13 Piping Penetration Area Filtration and Exhaust System (PPAFES).3.7.13-1 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System.3.7.14-1 3.7.15 Fuel Storage Pool Water Level.3.7.15-1 3.7.16 Secondary Specific Activity.3.7.16-1 3.7.17 Fuel Storage Pool Boron Concentration.3.7.17-1 3.7.18 Fuel Assembly Storage in the Fuel Storage Pool.3.7.18-1 (continued)
Vogtle Units 1 and 2 iii Amendment No. 1 34 (Unit 1)
Amendment No.1 1 3 (Unit 2)
PAM Instrumentation 3.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME H.
(continued)
NOTE------------
Applicable to those functions with only one required channel per loop, SG, or steam line.
One channel inoperable and no diverse channel OPERABLE.
I-
NOTE------------
1.1 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Not applicable to Containment Radiation and RVLIS functions.
Required Action and associated Completion Time of Condition H not met.
J.
NOTE------------
J.1 Initiate action in accordance Immediately Applicable to with Specification 5.6.8.
Containment Radiation and RVLIS functions only.
Required Action and asociated Completion Time of Condition H not met.
I I
I Vogtle Units 1 and 2 3.3.3-4 Amendment No. 1 34(Unit 1)
Amendment No. 1 1 3(Unit 2)
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)
Post Accident Monitonng Instrumentation FUNCTION
- 1. Reactor Coolant System (RCS) Pressure (wide range)
- 2. RCS Th, (wide range)
- 3.
RCS Td (wide range)
- 4. Steam Generator (SG) Water Level (wide range)
- 5. SG Water Level (narrow range)
- 6. Pressurizer Level
- 7. Containment Pressure
- 8. Steam line Pressure
- 9. Refueling Water Storage Tank (RWST) Level
- 10. Containment Normal Sumps Level (narrow range)
- 11. Containment Water Level (wide range)
- 12. Condensate Storage Tank Level
- 13. Auxiliary Feedwater Flow
- 14. Containment Radiation Level (high range)
- 15. Steam line Radiation Monitor
- 16. RCS Subcooling
- 17. Neutron Flux (extended range)
- 19. Deleted
- 20. Containment Pressure (extended range)
- 21. Containment Isolation Valve Position
- 22. Core Exit Temperature - Quadrant 1
- 23. Core Exit Temperature - Quadrant 2
- 24. Core Exit Temperature - Quadrant 3
- 25. Core Exit Temperature - Quadrant 4 REQUIRED CHANNELS 2
1/loop 1/loop 11SG 2/SG 2
2 2/steamn line 2
2 2
2ttanki")
2ISG 2
1stearn line 2
2 2
2 2/penetration flow path" "c' 2(d 2(d) 2(d) 2'd' CONDITIONS BG,H,I CG,H,I D,G,H,l EG,HkI B.G,H,I BGHI B,G,H,I BGHI B.G.HI B,G,HI
- B.G,H,I B,G,H,l BAG.HI B,G.H,J FG,H,I B.GHJI BGHI B.G,HJ BG,H.I B,GH,I B,GHAI B,G,H,I B,GH.I BAGRI (a)
Only required for the OPERABLE tank.
(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.
Applicable for containment Isolation valve position Indication designated as post-accident monitoring Instrumentation (containment Isolation valves which receive containment Isolation phase A or containment ventilation Isolation signals).
(c)
Only one position Indication channel Is required for penetration flow paths with only one Installed control room Indication channel.
(d)
A channel consists of two core exit thermocouples (CETs).
Vogtle Units 1 and 2 3.3.3-6 Amendment No. 134(Unit 1)
Amendment No. 11 3(Unit 2)
Hydrogen Recombiners 3.6.7 DELETED Vogtle Units 1 and 2 3.6.7-1 Amendment 11o. 134 (Units)
Amendment No. 113 (Unit 2)
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued)
- 3.
Letter from C. I. Grimes, NRC, to R. A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing of Topical Report WCAP-14040, Revision 1, 'Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, October 16, 1995.
- 4.
Letter from C. K. McCoy, Georgia Power Company, to U.S. Nuclear Regulatory Commission, Attention: Document Control Desk, Vogtle Electric Generating Plant, Pressure and Temperature Limits Report," Enclosures 1 and 2, January 26, 1996.
- d.
The PTLR'shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
5.6.7 EDG Failure Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days.
Reports on EDG failures shall include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4, or existing Regulatory Guide 1.108 reporting requirement.
5.6.8 PAM Report When a Report is required by Condition G or J of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation,' a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
(continued)
Vogtle Units 1 and 2 5.6-5 Amendment No. 134 (Unit 1)
Amendment No. 113 (Unit 2)