ML042780345
| ML042780345 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/28/2004 |
| From: | NRC/NRR/DLPM/LPD3 |
| To: | |
| Shared Package | |
| ML042780426 | List: |
| References | |
| TAC MB7794 | |
| Download: ML042780345 (5) | |
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TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.7.1 Control Room Emergency Filtration (CREF)
System Instrumentation 3.3.8.1 Loss of Power (LOP) Instrl-uii'uttit6...........
3.3-671 3.3.8.2 Reactor Protection System (RPS) Electric er......
Monitoring...........
3.3-74 3.4 REACTOR COOLANT SYSTEM (RCS).
3.4-1 3.4.1 Recirculation Loops OperAtig.
3.4-1 3.4.2 Jet PuTmps,...
3.-45 3.4.3 Safety Re......
Valvs 3.4-7 3.4.4 RCS Operational LEAKAGE 349 3.4.5 RCS Pressure Isolation
.......... 3.4-11 3.4.6 RCS Leakage Detection Instrumentation
........... 3.4-13 3.4.7 RCS Specific Activity 3.4-16 3.4.8.
) Shuta6do C661ing 4-1 System-Hot Shutdown 3.4-18 3.4.9 Residual Heat Removal (RR.)3Sf41t86AnC661i.
System-Cold Shutdown 3.4-21 3.4.10 RCS Pressure and TemperatuWre (tYLim its............. 3.4-23 3.4.11 Reactor Steam Dome Pressure 3.4-29 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5-1 3.5.1 ECCS-Operating.3.5-1 3.5.2 ECCS-S utdown..............
3 3.5.3 RCIC System...............
............. 3.5-12
.3.6 CONTAINMENT SYSTEMS 3.6-1 3.6.1.1 Primary Containmenit.3.6-1 3.6.1.2 Primary Containment'Air 6.k.3.6-3 3.6.1.3 Primary Containment Isolatioh-VW6s IVW.:........ 3.6-7 3.6.1.4 Primary Containment Pressure
- .*.*-3.6-18 3.6.1.5 Drywell Air Temperature 3.6-19 3.6.1.6 Low-Low Set (LLS) Valves---...........................3.6-20 3.6.1.7 Reactor Building-to-Suppressii6hCfihabe'r-taum----....
Breakers 3.6-22 3.6.1.8 Suppression:Chamb&ert6oiS'y11w Vacum k
rs 3.6-25 3.6.1.9 Deleted.....362 3.6.2.1 Suppression.P6l.Average temperature.3.6-29 3.6.2.2 Suppression Pool Water Level 3.6-32 3.6.2.3 Residual Heat Removal (RHR) S....sion.o
.3.6.-32 Cooling 3.6-33 3.6.2.4 Residual 3.6.
Spray..
3.6-35 (continued)
FERMI - UNIT 2 ii Amendment No. X,(. 160
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.11 Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the paths that are not provided with a seal Primary system is
- 0.05 L. when pressurized to Containment 2 56.5 psig.
Leakage Rate Testing Program and Inservice Testing Program SR 3.6.1.3.12 Verify combined MSIV leakage rate for In accordance all four main steam lines is S 150 scfh with the and 5 100 scfh for any one steam line Primary when tested at 2 25 psig.
Containment Leakage Rate Testing Program SR 3.6.1.3.13
NOTE.--------.-------
Only required to be met in MODES 1, 2, and 3.
Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrate the primary containment is Primary within limits.
Containment Leakage Rate Testing Program FERMI - UNIT 2 3.6 17 Amendment No. Age, 160
MSIV LCS 3.6.1.9 3.6 CONTAINMENT SYSTEMS THIS PAGE INTENTIONALLY LEFT BLANK FERMI -UNIT 2 3.6-27 Amendment No. Ac.
160
MSIV LCS 3.6.1.9 THIS PAGE INTENTIONALLY LEFT BLANK FERMI - UNIT 2 3.6-28 Amendment No. XU'K 160
Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.4.1.2 NOTEE---..................
Not required to be met for one railroad
.bay access door until:
- a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after opening for entry.
exit, or testing; and
- b. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after opening for new fuel receipt activities provided the other door remains OPERABLE and closed.
Verify all secondary containment equipment hatches, pressure relief doors and railroad bay access doors are closed and sealed.
31 days SR 3.6.4.1.3 Verify one secondary containment access 31 days door in each access opening is closed.
SR 3.6.4.1.4 Verify steam tunnel blowout panels are Prior to closed.
entering MODE 2 or 3 from MODE 4 if not performed in the previous 31 days SR 3.6.4.1.5 Verify each standby gas treatment (SGT) 18 months on a subsystem will draw down the secondary STAGGERED TEST containment to 2 0.25 inch of vacuum BASIS water gauge in S 12 minutes.
SR 3.6.4.1.6 Verify each SGT subsystem can maintain 18 months on a 2 0.25 inch of vacuum water gauge in the STAGGERED TEST secondary containment for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at a BASIS flow rate S 3000 cfm.
I FERMI - UNIT 2 3.6-42 Amendment No. A4W, 160