ML20083B010

Proposed Tech Specs,Consisting of Change Request 172, Modifying TS Section 15.4.1, Operational Safety Review

ML20083B010
Person / Time
Site:	Point Beach
Issue date:	05/02/1995
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20083B009	List: ML20083B005 ML20083B010
References
NUDOCS 9505110233
Download: ML20083B010 (6)

Text

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TABLE 15.4.1-1 '

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS, AND TESTS OF INSTRUMENT CHANNELS -

PLANT CONDITIONS N_L CHANNEL DESCRIPTION CHECK CALIBRATE IESI WHEN REQUIRED

1. Nuclear Power Range -

R .

ALL

-Heat Balance S(1) D(1,4918)

~

ALL

-Signal to delta T; bistable - -

Q(1,2) ALL actions (rod stops, trips)

-Compare results of the incore M(4,5,2019)

~

PWR detector measurements to NIS axial flux difference

2. Nuclear Intermediate Range -

R -

ALL

-when not blocked S(1) - -

ALL

-logarithR level; bistable action - -

P ALL (rod sh,p, trips)

3. Nuclear Source Range -

R -

ALL

-when not blocked S - -

ALL

-Bistable action (alarm and - -

P ALL trips)

4. Reactor Coolant Temperature S R -

PWR, HOT S/D, COLD S/D

-0vertemperature delta T - -

Q(1,2) ALL

-0verpower delta T - -

Q(1,2) ALL

5. Reactor Coolant Flow S(1) R -

ALL

-Analog and single loop loss- - -

Q(1,2) ALL of-flow logic testing

-Logic channel testing for - -

R ALL reactor trip on loss of reactor coolant flow in both loops

6. Pressurizer Water Level S(1) R Q(1,2) ALL

7. Pressurizer Pressure S(1) R Q(1,2) ALL

8. Steam Generator Level S(l) R Q(1,4Q4) ALL Unit 1 - Amendment No. Page 1 of 6 Unit 2 - Amendment No.

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TABLE 15.4.1-1 (continued) ,

' PLANT CONDITIONS

& CHANNEL DESCRIPTION CHECK CALIBRATE IE11 WHEN REQUIRED

9. Steam. Generator Flow Mismatch S(MH) R Q(1) ALL

10. Steam Generator Pressure S(M]$) R Q(1) ALL-

11. 4KV Bus Undervoltage (A01 & A02)

-AFW pump actuation -

R M(1) ALL

-Reactor Protection actuation -

R M(1,2) ALL

12. 4KV Bus Underfrequency (A01 & A02)

-to Reactor Coolant Pump trip -

.R -

ALL

13. Safeguards Bus Voltage

-Loss of 4KV S R M(1) ALL

-Degraded 4KV S R M(1) ALL

-Loss of 480V S R M(1) ALL

14. 120 Vac Instrument Buses W(6) - -

.ALL

15. Reactor Trip Signal From Turbine

-Turbine Autostop - -

M(1) ALL

-Turbine Stop Valve - -

M(1) ALL

16. Reactor Trip Signal From SI - -

M(1) .ALL

17. Feedwater Isolation on SI

-MFP Trip on Safety Injection - -

R ALL

-MFRV Shutting on Safety Injection - -

'R ALL

18. Accumulator Level and Pressure S R -

ALL

19. Analog Rod Position S(8,MH) R M(1) .ALL

-with step counters S(Mt()~ - -

ALL

-Monitoring by On-Line Computer (48R)' - -

PWR, HOT S/D' Unit 1 - Amendment No. Page'2 of 6 Unit 2 - Amendment No.

a. _ _ _ _ . . _ . _ _ . ~ . . _ _ _ . . - - _ - . _ _ . . .. _ .. .. _ ___.____ _ _ _ _ _ . _...u_ _._. . . _ . . . _ _ _ _ _ _ _ . _ _ -

TABLE 15.4.1-1 (continued) - .,

PLANT CONDITIONS ML. CHANNEL DESCRIPTION CHECK CALIBRATE IESI WHEN REQUIRED

20. Auxiliary Feedwater Flowrate (M) R -

ALL

21. Boric Acid Control System -

R - ALL

22. Boric Acid Tank Level D R -

ALL

23. Charging Flow -

R - ALL

24. Condensate Storage Tank Level S(l) R -

ALL

25. Containment High Range Radiation S(l) R(M13) MQ(1) ALL

26. Containment Hydrogen Monitor D - -

ALL

         -Gas Calibration                        -

Q(M)}) - ALL

         -Electronic Calibration                 -

R - ALL

27. Containment Pressure S R Q(1,3,98,) ALL

28. Containment Water level M R -

ALL

29. Emergency Plan Radiation Survey Instruments Q R Q ALL

30. Environmental Monitors M - -

ALL

31. In-Core Thermocouples M R(Mf3) -

ALL

32. Overpressure Mitigating System S(Ml}) R (Mj) ALL

33. PORY Block Valve Position Indicator Q R -

ALL

34. PORV Operability -

R Q(R}0) ALL

35. PORV Position Indicator S(M[0) R R ALL l

l Unit 1 - Amendment No. Page 3 of 6 i Unit 2 - Amendment No. l

TABLE 15.4.1-1 (continued) ,

&   CHANNEL DESCRIPTION                   CHECK      CALIBRATE                    IESI         WHEN REOUIRED

36. P.:dicti:n Megtering Syst;c-M[n]}$sii 9t7t[(1J R(7}3) Mf7}QJ}} ALL LTrEIRid1Ti6on

37. RisdhfVessel Fluid Level System M R -

ALL

38. Refueling Water Storage Tank Level -

R - ALL

39. Residual Heat Removal Pump Flow -

R - ALL

40. Safety Valve Position Indicator M R -

ALL

41. Subcooling Margin Monitor M R -

ALL

42. Turbine First Stage Pressure S(1) R M(1) ALL

'43. Turbine Overspeed Trips

    -Independent Overspeed Protection System                   -

R M(1) ALL

    -0verspeed Block trip                 -

R M(1) ALL

44. Volume Control Tank Level -

R - ALL

45. Reactor Protection System and - -

M(1,4312)

                                                                                          ~

ALL Emergency Safety Feature Actuation System logic

46. Reactor Trip System Interlocks . . . . . .

    -Intermediate Range Neutron Flux, P                                                       R(4423)                       R           ALL
    -Power Range Neutron Flux, P-8        -

R(2423) R ALL

    -Power Range Neutron Flux, P-9        -

R(2423) R ALL

    -Power Range Neutron Flux, P-10       -

R(2423) R ALL

    -1st Stage Turbine Impulse Pressure   -

R(4423,) R ALL' Unit 1 - Amendment No. Page 4 of 6 Unit 2 - Amendment No.

                                                           . . ~ . -  , ..... . . . . . -    < - . - - . ....,---.-,m ,, . . . , ,. ...~     .m_   . . . _w

1. -.

NOTATION USED IN TABLE 15.4.1-1 , S- Each shift D- Daily W- W;ekly Q- Quarterly M- Monthly P- Prior to reactor criticality if not performed during the previous week. R- Each refueling interval (but not to exceed 18 months) PWR- Power and Low Power Operation, as defined in Specifications 15.1.h. and 15.1.n. HOT S/D- Hot Shutdown, as defined in Specification 15.1.g.1. COLD S/D- Cold Shutdown, as defined in Specification 15.1.g.2. REF S/D- Refueling Shutdown, as defined in Specification 15.1.g.3. ALL- All conditions of operation, as defined in Specifications 15.1.g, h and n. NOTES USED IN TABLE 15.4.1-1 (1) Not required during periods of refueling shutdown, but must be performed prior to reactor criticality if it has not been performed during the previous surveillance period. (2) Tests of the low power trip bistable setpoints which cannot be done during power operations shall be conducted prior to reactor criticality if not done in the previous surveillance interval. (3) Perform test of the isolation valve signal. (4) Perform by means of the moveable incore detector system. (5) Recalibrate if the absolute difference is 23 percent. (6) Verification of proper breaker alignment and that the 120 Vac instrument buses are energized. (7) Radic::tive Effluent Monitoring In:trun:nt: tion Surv;ill:ne: Requir:::nt: r: :p :!fied in S :ti:n 15.7.4. (8Z) Verify that the associated rod insertion limit is not being violated at least once per 4 hours whenever.the rod insertion limit alarm for a control bank is inoperable. (98) Test of Narrow Range Pressure, 3.0 psig, -3.0 psig excluded. Unit 1 - Amendment No. Page 5 of 6 Unit 2 - Amendment No.

v.s NOTES USED IN TABLE 15.4.1-1 (continued) , (Mg) When used for the Overpressure Mitigating System, each PORV shall be demonstrated operable by: . .

a. Perfomance of a channel functional test on_ the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required operable and at least once per 31' days i thereafter when the PORV is required operable.

(Hjj) Performance of a channel functional test is required, excluding valve operation. (MM)Shiftly check is required when the reactor coolant system is not open to the atmosphere and the reactor coolant system temperature is less than the minimum temperature for the in-service pressure test as specified in.TS Figure 15.3.1-1.- (M}2)An AFW flow path to each steam generator shall be demonstrated operable, following each cold shutdown of greater than 30 days, prior to entering power operation by verifying AFW flow to each steam generator.

(M)))Calibrationistobeaverificationofresponsetoasource.

(HQ) Sample gas for calibration at 2% and 6%.

l (M}})A check of one pressure channel per steam generator is required whenever the steam generator could be pressurized. (Wi() Includes test of logic for reactor trip on low-low level, automatic actuation logic for auxiliary feedwater pumps, and test of logic for feedwater isolation on high steam generator level. (481?) Rod positions must be logged at least once per hour, after a load change >10% or after >30 inches of control' rod motion-if the on-line computer is inoperable. (491))The daily heat halance is a gain adjustment performed to match Nuclear Instrumentation System indicated power level with reactor thermal output. (2019)To confirm that hot channel factor limits are being satisfied, the requirements of TS 15.3.10.B must be mat. (M20) Check required only when the overpressure mitigation system is in operation. (M21)Not required during period of cold and refueling shutdowns, but must be performed prior to reactor criticality if it

                       ~ has not been performed during the previous surveillance period.

(M)$)Each train tested at least every 62 days on a staggered basis. (Mi3) Neutron detectors excluded from calibration. Unit 1 - Amendment No. Page 6 of 6 Unit 2 - Amendment No. _ . . _ _ _ _ _ _ . _ . _ _ . _ _ _ . . . _ . _ _ _ _ . . _ _ _ . _ _ . _ . _ _ _ . _ . . . _ _ ._ _ _ .__. ._ _ _ _ . _}}