ML050970155

Tech Spec Pages for Amendments 209, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process

ML050970155
Person / Time
Site:	Mcguire, McGuire
Issue date:	04/04/2005
From:	NRC/NRR/DLPM
To:
SHea J, 415-1388, NRR/DLPM
Shared Package
ML050970013	List: ML050960007 ML050970142 ML050970155
References
TAC MC4445, TAC MC4446
Download: ML050970155 (5)

Text

TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) (continued) 3.4.6 RCS Loops-MODE 4 .................................................... 3.4.6-1 3.4.7 RCS Loops-MODE 5, Loops Filled ............................................... 3.4.7-1 3.4.8 RCS Loops-MODE 5, Loops Not Filled ......................................... 3.4.8-1 3.4.9 Pressurizer .................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves ..................................................... 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ...................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ........... 3.4.12-1 3.4.13 RCS Operational LEAKAGE ............................................ ........ 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ................................. 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ........................................ 3.4.15-1 3.4.16 RCS Specific Activity .................................................... 3.4.16-1 3.4.17 RCS Loop-Test Exceptions .................................................... 3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ............................. 3.5.1-1 3.5.1 Accumulators .................................................... 3.5.1-1 3.5.2 ECCS-Operating .................................................... 3.5.2-1 3.5.3 ECCS-Shutdown .................................................... 3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST) .......................................... 3.5.4-1 3.5.5 Seal Injection Flow .................................................... 3.5.5-1 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 System .................................................... 3.6.6-1 3.6.7 Not Used.

3.6.8 Hydrogen Skimmer System (HSS) .................................................. 3.6.8-1 3.6.9 Hydrogen Mitigation System (HMS) ................................................ 3.6.9-1 3.6.10 Annulus Ventilation System (AVS) .................................................. 3.6.10-1 3.6.11 Air Return System (ARS) .................................................... 3.6.11-1 3.6.12 Ice Bed .................................................... 3.6.12-1 3.6.13 Ice Condenser Doors .................................................... 3.6.13-1 3.6.14 Divider Barrier Integrity ..................................................... 3.6.14-1 3.6.15 Containment Recirculation Drains ................................................... 3.6.15-1 3.6.16 Reactor Building .................................................... 3.6.16-1 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),

Main Feedwater Control Valves (MFCVs), MFCV's Bypass Valves and Main Feedwater (MFW) to Auxiliary Feedwater (AFW) Nozzle Bypass Valves (MFW/AFW NBVs) ... 3.7.3-1 3.7.4 Steam Generator Power Operated Relief Valves (SG PORVs) ....... 3.7.4-1 McGuire Unit.2 ii Amendment No. 209

I PAM Instrumentation 3.3.3 ACTIONS (continued)

- CONDITICN REQUIRED ACTION COMPLETION TIME E. One or more Functions E.1 Restore one channel to 7 days with two required OPERABLE status.

channels inoperable.

F. Not Used F.1 Not Used Not Used G. Required Action and G.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 /> associated Completion Time of Condition D or E AND not met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> H. Required Action and H.1 Initiate action in Immediately associated Completion accordance with of Condition D not met. Specification 5.6.7.

HicGuire Unit 2 3.3.3-2 Amendment No. 209

- B -I PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

-' L IATySI - - - - - - - - - - - - - - -

- -- - ---a- -- - - - --- - mtj PAM i------_

I3 _______

SR 3.3.3.1 and SR 3.3.3.3 apply to each PAM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2 Not Used Not Used I SR 3.3.3.3 ----------- ------- NOTE--

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months McGuire Unit 2 3.3.3-3 Amendment No. 209

r PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)

Post Accident Monitoring Instrumentation OR.

FUNCTION REQUIRED CHANNELS CONDITIONS

1. Neutron Flux (Wide Range) 2 B,C.E,G

2. Reactor Coolant System (RCS) Hot Leg Temperature 2 B.C.E,G

3. RCS Cold Leg Temperature 2 B,C.E.G

4. RCS Pressure (Wide Range) 2 B,C,E,G

5. Reactor Vessel Water Level (Dynamic Head Range) 2 BC,E.G

6. Reactor Vessel Water Level (Lower Range) 2 B,C.E.G

7. Containment Sump Water Level (Wide Range) 2 BCE.G

8. Containment Pressure (Wide Range) 2 B,C.EG

9. Containment Atmosphere Radiation (High Range) I D,H

10. Not Used Not Used Not Used I

11. Pressurizer Level 2 B,C,EG

12. Steam Generator Water Level (Narrow Range) 2 per steam generator BC,E.G

13. Core Exit Temperature - Quadrant 1 B,C,EG 2 (a)

14. Core Exit Temperature - Quadrant 2 2(a) BCEG

15. Core Exit Temperature - Quadrant 3 B,C,E,G 2(a)

16. Core Exit Temperature - Quadrant 4 2(a) B.CE.G

17. Auxiliary Feedwater Flow 2 per steam generator B,C,EG

18. RCS Subcooling Margin Monitor 2 BCE.G

19. Steam Une Pressure 2 per steam generator 8,C,E.G

20. Refueling Water Storage Tank Level 2 8,C,EG

21. DG Heat Exchanger NSWS Flow(b) 1 per DG DG

22. Containment Spray Heat Exchanger NSWS Flow(b) 1 per train D,G (a) A channel consists of two core exit thermocouples (CETs).

(b) Not applicable If the associated outlet valve Is set to Its flow balance position with power removed or If the associated outlet valve's flow balance position Isfully open.

McGuire Unit 2 3.3.3-4 Amendment No. 209

3.6 CONTAINMENT SYSTEMS 3.6.7 Not Used IlcGuire Unit- 2 3.6.7-1 Amendment No. 209