ML042310523

Technical Specifications, Relocation of Requirements for Hydrogen Monitors

ML042310523
Person / Time
Site:	Point Beach
Issue date:	08/13/2004
From:	Chernoff H NRC/NRR/DLPM/LPD3
To:	Koehl D Nuclear Management Co
Chernoff, H, NRR/DLPM, 301-415-4018
Shared Package
ML042300461	List: ML042310523
References
TAC MC1904, TAC MC1905
Download: ML042310523 (5)

Text

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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NOTES----------------------

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETIONTIvE A. One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel inoperable. status.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.

met.

C. One or more Functions C.1 Restore one channel 7 days with two required to OPERABLE status.

channels inoperable.

(continued)

Point Beach 3.3.3-1 Unit 1 - Amendment No. 214 Unit 2 - Amendment No. 219

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETIONTIM\E D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3-1 for the not met. channel.

E. As required by E.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 /> I Required Action D.1 and referenced in AND Table 3.3.3-1.

E.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 /> F. As required by Required F.1 Initiate action in Immediately I Action D.1 and accordance with referenced in Specification 5.6.6.

Table 3.3.3-1.

Point Beach 3.3.3-2 Unit 1 - Amendment No. 214 Unit 2 - Amendment No. 219

PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

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NOTE-------------------------------------------------

SR 3.3.3.1 applies to each PAM instrumentation Function in Table 3.3.3-1. SR 3.3.3.2 applies to each PAM instrumentation Function in Table 3.3.3-1, except Function 12.

SR 3.3.3.3 applies to Function 12 only.

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 ------------------------ NOTE---------------------------

CHANNEL CALIBRATION of Containment Area Radiation (High Range) detectors shall consist of verification of a response to a source.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.3.3 Perform TADOT. 18 months I Point Beach 3.3.3-3 Unit 1 - Amendment No. 214 Unit 2 - Amendment No. 219

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

Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION D.1

1. Reactor Coolant System (RCS) Subcooling Monitor 2

2. RCS Hot Leg Temperature (Wide Range) 2 per loop

3. RCS Cold Leg Temperature (Wide Range) 2 per loop

4. RCS Pressure (Wide Range) 2

5. RCS Pressure (Narrow Range) 2

6. Reactor Vessel Water Level (Wide Range) 2

7. Reactor Vessel Water Level (Narrow Range) 2

8. Containment Sump B Water Level 2

9. Containment Pressure (Wide Range) 2

10. Containment Pressure (Intermediate Range) 2

11. Containment Pressure (Low Range) 2

12. Containment Isolation Valve Position 2 per penetration flow path (a)(b)

13. Containment Area Radiation (High Range) 2

14. Pressurizer Level 2

15. Steam Generator Water Level (Wide Range) 2 per steam generator

16. Steam Generator Water Level (Narrow Range) 2 per steam generator

17. Steam Generator Pressure 2 per steam generator

18. Condensate Storage Tank Level 2 per tank

19. Core Exit Temperature - Quadrant 1 2

20. Core Exit Temperature - Quadrant 2 2 E

21. Core Exit Temperature -Quadrant 3 2 E

22. Core Exit Temperature - Quadrant 4 2 E

23. Auxiliary Feedwater Flow 2 E

24. Refueling Water Storage Tank Level 2 E (a) 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.

(b) Only one position Indication channel Is required for penetration flow paths with only one Installed control room Indication channel.

I Point Beach 3.3.3-4 Unit 1 - Amendment No. 214 Unit 2 - Amendment No. 219

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(1) LCO 3.4.3, -RCS Pressure and Temperature (P/T) Limits" (2) LCO 3.4.6, -RCS Loops-MODE 4" (3) LCO 3.4.7, URCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.10, "Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)"

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000 and July 23, 2001.

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

5.6.6 PAM Report When a report is required by Condition B or F 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.

5.6.7 Tendon Surveillance Report Abnormal conditions observed during testing will be evaluated to determine the effect of such conditions on containment structural integrity. This evaluation should be completed within 30 days of the identification of the condition. Any condition which is determined in this evaluation to have a significant adverse effect on containment structural integrity will be considered an abnormal degradation of the containment structure.

Any abnormal degradation of the containment structure identified during the engineering evaluation of abnormal conditions shall be reported to the Point Beach 5.6-5 Unit 1 - Amendment No. 214 Unit 2 - Amendment No. 219