ML20100K186

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Proposed Tech Specs Incorporating Operability & Testing Requirements Associated W/Shunt Trip Attachment Mod Required by Generic Ltr 83-28
ML20100K186
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 04/05/1985
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20100K135 List:
References
GL-83-28, NUDOCS 8504120302
Download: ML20100K186 (10)
v • d • e


Text

7 Exhibit B Prairie Island Nuclear Generating Plant License Amendment Reauest Dated April 5.1985 Proposed Changes to the Techn'. cal Specifications Appendix A of Operating Licenses DPR-42 and 60 Exhibit B consists of revised pages of Appendix A Technical Specifications as listed below:

Page Table TS.3.5-2 (page 1 of 2)

Table TS.3.5-2 (page 2 of 2)

Table TS.4.1-1 (page 1 of 6)

Table TS.4.1-1 (page 2 of 6)

Table TS.4.1-1 (page 3 of 6)

Table TS.4.1-1 (page 4 of 6)

Table TS.4.1-1 (page 5 of 6)

Table TS.4.1-1 (page 6 of 6)

Table TS.4.1-2A 8504120302 850405 PDR ADOCK 05000282 P PDR

TABLE TS.3.5-2 ,

INSTRUMENT OPERATING CONDITIONS FOR REACTOR TRIP (Page 1 of 2) 1 2 3 4 MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF OPERABLE DEGREE OF BYPASS CONDITIONS OF COLUMN FUNCTIONAL UNIT CHANNELS REDUNDANCY CONDITIONS ( ) 1 OR 2 CANNOT BE MET

1. Manual 2 1 Notes 3, 4 l
2. Nuclear Flux Power Range
  • low setting 3 2 2 of 4 power Maintain hot shutdown high setting 3 2 range channels positive rate '

3 2 greater than negative rate 3 2 10% F.P. (Iow setting only)

3. Nuclear Flux Intermediate 2 1 2 of 4 power Maintain hot shutdown Range range channels Note 2 greater than 10% F.P.
4. Nuclear Flux Source Range 2 1 1 of 2 inter- Maintain hot shutdown mediate range Note 2 channelsg greater than 10 amps
5. Maintain hot a,hutdown Overtemperature AT 3 2 Ng
  • r M
6. Overpower AT 3 2 Maintain hot shutdown
7. Low Pressurizer Pressure 3 2 Maintain hot shatdown i
8. Hi Pressurizer Pressure 2 1 Maintain hot shutdown h
9. Pressurizer-Hi Water Level 2 1 Maintain hot shutdown f
10. Low Flow in one loop 2/ loop 1/ loop Maintain hot shutdown-( >10% F.P.) o Low Flow both loops 2/ loop 1/ loop

(>10% F.P.) O

w-1 -- - - e.- - - u,o , a e .wia. u:

TABLE TS.3.5-2 INSTRUMENT OPERATING CONDITIONS FOR REACTOR TRIP ',-

l (Page 2 of 2) 1 2 3 4 MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION-IF OPERABLE DEGREE OF BYPASS CONDITIONS OF COLUMN FUNCTIONAL UNIT CHANNELS REDUNDANCY CONDITIONS ( l OR 2 CANNOT BE MET

11. Turbine Trip 2 1 Maintain <50% of (Overspeed Protection) rated power
12. Lo-Lo Steam Generator 2/ loop 1/ loop Maintain hot shutdown Water Level
13. Undervoltage 4KV RCP Bus 1/ bus 1/ bus Maintain hot shutdown

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14. Underfrequency 4KV Bus 1/ bus 1/ bus Maintain hot shutdown
15. Control Rod Misalignment Monitor
a. Rod position deviation 1 - Log data required by
b. Quadrant power tilt 1 -

TS.3.10 I and TS. 3.10 J

16. RCP Breakers Open 2 1 Maintain hot shutdown
17. Safety Injection 2 1 Maintain hot shutdown Actuation Signal
18. Lo Feedwater Flow 1/ loop 1/ loop Maintain hot shutdown
19. Automatic Trip Logic including 2 1 Notes 3, 4 Reactor Trip Breakers ** @{

Note 1: Automatic permissives not listed r*

M Note 2: When bypass condition exists, maintain normal operation g Note 3: With the number of operable channels one less than the minimum operable channels requirement. w be in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to I, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.1, provided the other channel is operable. h Note 4: Whea in the hot shutdown condition with the number of operable channels one less than the minimum (E operable chann21s requirement, restore the inoperable channel to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> $*

or open the reactor trip breakere within the next hour.

F.P. = Full Power o

  • = One additional channel may be taken out of service for low power physics testing g3
    • = Includes both undervoltage and shunt trip circuits and if either circuit becomes inoperable the respective channel shall be considered inoperable.

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TABLE TS.4.1-1 (Page 1 of 6) l MINIMUM FREQUENCIES FOR Ln.tCKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Functional Response Description Check Calibrate Test Test Remarks 1

1. Nuclear Power S(l) D(2) M(3) R 1) Once/shif t when in service Range M(4) Q(4) M(5) 2) Heat balance

, M(6) 3) Signal to AT: bistable action P(7) (permissive, rod stop, trips),

j with the exception of the j items covered in Remark #7.

4

4) Upper and lower chambers for axial off-set using in-core 4 detectors i 5) Simulated signal for testing j positive and negative rate bistable action

. 6) Quadrant Power Tilt Monitor

7) P8 and P10 permissives and J

the 25% High Flux Low Setpoint Trip.

2. Nuclear Inter- *S(l) NA T(2) R 1) Once/ shift when in service

! mediate Range 2) Log Level; bistable action i

(permissive, rod stop, trips) i 3. Nuclear Source *S(l) NA T(2) R 1) Once/shif t when in service Eg Range 2) Bistable action (alarm, trips) 4 c.

ps

4. Reactor Coolant S(1,2) R(1,2,3) M(1) R(1) 1) Overtemperature AT Temperature M(2) R(2) 2) Overpower AT d T(3) 3) Control Rod Bank Insertion ,

Limit Monitor ~

< 5. Reactor Coolant S R M NA d.

Flow ,s

6. Pressurizer S R H NA ]

Water Level  %

7. Pressurizer S R M NA -

Pressure o m

2 cs

%s a ,

TABLE TS.4.1-1 (Page 2 of 6) l MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Functional Response Description Check Calibrate Test Test Remarks

8. 4KV Voltage & NA R H NA Reactor protection circuits only Frequency 8a. RCP Breakers NA R T NA
9. Analog Rod S(l) R T(2) NA 1) With step counters Position M(2)

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2) Rod Position Daviation Monitor Tested by updating computer bank count and comparing with analog rod position test signal
10. Rod Position S(1,2) NA T(3) NA 1) With analog rod position Bank Counters M(3) 2) Following rod motion in excess of six inches when the computer is out of service
1) Control rod banks insertion limit monitor and control rod position deviation monitcrs
11. Steam Generator S R M NA Level gj H

<:Mh i 12. Steam Generator S R M NA i

Flow Mismatch

13. Charging Flow S R NA NA ,

1 l 14. Residual Heat S(l) R NA NA 1) When in operation ,s Removal Pump Flow i 5

15. Boric Acid Tank D R(1) M(1) NA 1) Transfer logic to Refueling Water g Level Storage Tank o m

b

TABLE TS.4.1-1

! (Page 3 of 6) l MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND i TEST OF INSTRUMENT CHANNELS i .

! Channel Functional Response i Description Check Calibrate Test Test Remarks

16. Refueling Water W R M(1) NA 1) Functional test can be performed Storage Tank Level by bleeding transmitter
17. Volume Control Tank S R NA NA

. 18a. Containment Pressure S R M(1) NA Wide Range Containment Pressure ,

i SI Signal 1) Isolation Valve Signal 18b. Containment Pressure S R M NA Narrow Range Containment Pressure Steam Line Isolation 18c. Containment Pressure S R H NA

! Containment Spray I

18d. Annulus Pressure NA R R NA

! (Vacuum Breaker) j 19. Auto Load Sequencers NA NA M NA l

! 20. Boric Acid Make-up Flow NA R NA NA Channel

) 21. Containment Sump Level NA R R NA Includes Sumps A, B, and C "8 I d

22. Accumulator Level S R R NA
  • i and Pressure ~

1 l 23. Steam Generator Pressure S R M NA ,s e

j 24. Turbine First Stage Pressure S R H NA h I

w

25. Emergency Plan Radiation *M R H NA Includes those named in the emergency o Instruments procedure (referenced in Spec. 6.5 A.6.) "'
4D

! 26a. Protection Systems NA NA M NA Includes reactor trip logic for both the l Logic Channel Testing undervoltage and shunt trips l

TABLE TS.4.1-1 (Page 4 of 6)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Functional Response Description Check Calibrate Test Test Remarks 26b. Reactor Trip Breakers NA NA M(1) R(2) (1) Includes independent testing of both undervoltage and shunt trip attach-ment of the reactor trip breakers.

(2) Automatically trip the undervoltage 4

trip attachment.

I 26c. Manual Reactor Trip NA NA R NA Includes independent " testing of both

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undervoltage and shunt trip circuits.

l The test shall also verify the operability l of the bypass breaker.

4 26d. Reactor Trip Bypass Breaker NA NA M(1) R(2) (1) Manually trip the undervoltage trip attachment remotely (ie from the I

protection system racks).

(2) Automatically trip the undervoltage trip attachment i

27. Turbine Overspeed NA R H NA

{ Protection Trip Channel llH

<= D

28. Deleted

] 29. Deleted d l 30. Deleted ,

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4 ~

31. Seismic Monitors R R NA NA ,L

{

l m

32. Coolant Flow - RTD S R H NA ]

Bypass Flowmeter  %

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33. CRDM Cooling Shroud S NA R NA FSAR page 3.2-56 i

! 34. Reactor Gap Exhaust S NA R NA $

Air Temperature

TABLE TS.4.1-1 (Page 5 of 6)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Functional Response Description Check Calibrate Test Test Remarks 35a. Post-Accident Monitoring M R NA NA Includes all those in Table Instruments TS.3.15-1 (except for contain-ment hydrogen monitors which are separately specified in this table)

b. Post-Accider.c Monitoring D R H NA Includes all those in Table Radiatica Instruments ,

TS.3.15-2

36. Steam Exclusion W Y M NA See FSAR Appendix I Section Actuation System I.14.6
37. Overpressure Mitigation NA R R NA Instrus.ent Channels for PORV System Control Including Overpressure Mitigation System 4
38. Degraded Voltage NA R M NA 4KV Safeguard Busses
39. Loss of Voltage NA R H NA 4KV Safeguard Busses i 40. Auxiliary Feedwater NA R R NA < g Pump Suction Pressure M
41. Auxiliary Feedwater NA R d

j R HA ,

a Pump Discharge Pressure -

f 42. NaOH Caustic Stand Pipe W R H NA Level 'g 43.

5 Control Room Ventilation S Y M(1) NA ,

System Chlorine Monitors o

m

TABLE TS.4.1-1 (Page 6 of 6)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Functional Response Description Check Calibrate Test Test Remarks

44. Hydrogen Monitors S Q(2) M NA
45. Containment Temperature M R NA NA Monitors E!"

E d

S - Shift Y - Yearly

  • D - Daily R - Each refueling shutdown
  • W - Weekly NA - Not applicable J.

M -

Monthly * - See Specification 4.1.D , ,,

Q - Quarterly jl P - Prior to each startup if not done previous week g T - Prior to each startup following shutdown in excess ,,

of 2 days if not done in the previous 30 days o (1) Verification of the chlorine monitor control logic only. (D (2) Test will be conducted per manufacturer's recommendations.

TABLE TS.4.1-2A REV i MINIMUM FREQUENCIES FOR EQUf> MENT TESTS

. FSAR Section Test Frequency Reference

1. Control Rod Assemblies Rod drop times All rods curing each 7 of full length refueling shutdown rods or following each removal of the reac-tor vessel head; affected rods follow-ing maintenance on or 4 modification to the control rod drive system which could affect performance of those specific rods
2. Contro,1 Rod Assemblies Partial move- Every 2 weeks 7 ment of all rods
3. Pressurizer Safety Set point Per ASME Code,Section XI -

Valves Inservice Testing Program

4. Main Steam Safety Set point Per ASME Code,Section XI -

Valves Inservice Testing Program

5. Reactor Cavity Water level Prior to moving fuel -

assemblies or control rods and at least once every day while the cavity is flooded.

6. Pressurizer PORV Functional Quarterly -

Block Valves

7. Pressurizer PORV's Functional Every 18 months -
8. Deleted ,
9. Primary System Leakage Evaluate Daily 4
10. Deleted
11. Turbine stop valves, Functional Monthly ( } 10 governor valves, and intercept valves. (Part of turbine overspeed protection.)
12. Deleted (1) This test may be waived for end of cycle operations when boron concentrations are less than 150 ppm provided more than 60 days do not elapse following the last test.

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