ML20129C542

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Amends 75 & 68 to Licenses DPR-42 & DPR-60,respectively, Adding Requirements to Tech Spec Sections 3.5 & 4.1 Re Automatic Actuation of Shunt Trip & Manual Reactor Trip Circuits
ML20129C542
Person / Time
Site: Prairie Island  
Issue date: 06/26/1985
From: Butcher E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20129C545 List:
References
NUDOCS 8507160237
Download: ML20129C542 (21)
v • d • e


Text

/

UNITED STATES y,

g NUCLEAR REGULATORY COMMISSION

y WASHINGTON, D. C. 20555

\\...../

NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. DPR-42 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

.The application for amendment by Northern States Power Company (thelicensee)datedApril5,1985complieswiththestandards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

00 P

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 75, are hereby in-corporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions.

3.

Thislicenseameddmentiseffectiveasofthedateofitsissuance.

~

FOR THE NUCLEAR REGULATORY COMMISSION s

Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 26, 1985

ATTACHMENT TO LICENSE AMENDMENT NO. 75 TO FACILITY OPERATING LICENSE N0. DPR-42 DOCKET NOS. 50-782 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of changes.

Remove Insert Table TS 3.5-2 Table TS 3.5-2 (page 1 of 2)

(page 1 of 2)

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

(page 2 of 2)

Table TS. 4.1-1 Table TS. 4.1-1 (5 pages)

(5 pages)

Table TS. 4.1-2A Table 4.1-2A

~. -

f\\

TABLE TS.3.5-2 (Page 1 ef 2)

UU QQ INSTRUMENT OPERATING CONDI'fIONS FOR REACTOR. (IP 57CT 1

2 3

4 mm

,S MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF QQ OPERABLE DECREE OF BYPASS CONDITIONS OF COLUMN 0 o-rbNCTIONAL UNIT CHANNELS REDUNDANCY

'^

c: c:

CONDITIONS (1) 1 OR 2 CANNOT BE MET so p5 1.

Manual 2

1 l

Notes 3, 4 l

b3 ""

2.

Nuclear Flux Power Range

  • 1 I

'8 low setting 3

2 2 of 4 power Maintain hot shutdown g' B'

.aigh setting 3

2 range channels s@

positive rate 3

2 greater than negative rate 3

2 10% F.P. (low setting only) nn 3.

Nuclear, Flux Intermediate 2

1 2 of 4 power Maintain hot shutdown 2: 2:

.O Range range channels Note 2 l

os sa greater than l

10% F.P.

4.

Nuclear Flux Source Range 2

1 1 of 2 inter-Maintain hot shutdown mediate range Note 2 channels greater than 10 10 amps 5.

Overtemperature AT 3

2 Maintain hot shutdown 6.

Overpower AT 3

2 Maintain hot shutdown 7.

Low Pressurizer Pressure 3

2 Maintain hot shutdown.

8.

Hi Pressurizer Pressure 2

1 Maintain hot shutdown-

-e 9.

Pressurizer-Hi Water Level 2

1 Maintain hot shutdown 2 $.'

m.

10.

Low Flow in one loop (>10% F.P.)

2/ loop 1/ loop Maintain hot shutdown Low Flow both loops (>10% F.P.)

2/ loop 1/ loop

"'.0!

o 11.

Turbine Trip 2

1 Maintain < 50% of

"'F (Overspeed Protection) rated power O'

12.

Lo-Lo Steam Generator 2/ loop 1/ loop Maintain hot shutdown i

Water Level

~.

~

TABLE TS 3.5-2 (Pcg2 2 cf 2) eo{h INSTRUMENT OPERATING CONDITIONS FOR REACTOR TRIP aa 0 0 1

2 3

4 gy MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF gy OPERABLE DEGREE OF BYPASS CONDITIONS OF COLUMN g, g, FUNCTIONAL UNIT CNANNELS REDUNDANCY CONDITIONS (1) 1 OR 2 CANNOT BE MET ec 1

8 8 13.

Undervoltage 4KV RCP Bus 1/ bus 1/ bus Maintain hot shutdown nn 14.

Underfrequency 4KV Bus 1/ bus 1/ bus Maintain hot shutdown gy 8 '

15.

Control Rod Misalignment Monitor gg

a. Rod position deviation 1

Log data required by a$

b. Quadrant power tilt 1

TS 3.10 1.and TS 3.10 J

n. o.

gg 16.

RCP Breakers Open 2

1 Maintain hot shutdown aa 17.

Safety Injection ff Actuation Signal 2

1 Maintain hot shutdown 18.

Lo Feedwater Flow 1/ loop 1/ loop Maintain hot shutdown my es u.

19.

Automatic Trip Logic including Reactor Trip Breakers **

2 1

Notes 3, 4 Note 1: Automatic permissives not listed Note 2: When bypass condition exists, maintain normal operation Note 3: With the number of operable channels one less than the minimum operable channels requirement, 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 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.

Note 4: When in the hot shutdown condition with the number of operable channels one less than the minimum operable channels 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 gg trip _ breakers within the next hour.

g$

F.P. = Full I'ower "d

= One additional channel may be taken out of service for low power physics testing o-

= Includes both undervoltage and shunt trip circuits and if either circuit becomes inoperable the respective wh channel shall be consider-d inoperable.

N

mm 3g TABLE TS.4.1-1 (Page 1 of 5) l

$p MINIMUM FREQUENCIES FOR CHECKS. CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS sm

'd E 99 Channel Functional Response Description Check Calibrate Test Test Remarks EE 1.

Nuclear Power S(l)

D(2)

M(3)

RI

1) Once/ shift when in service ww Range M(4)

Q(4)

M(5)

2) Heat balance M(6)
3) Signal to AT; bistable action g

P(7)

(permissive, rod stop, trips), with e.g the exception of the items covered EE in Remark #7.

4) Upper and lower chambers for axial 55 off-set using in-core detectors m z
5) Simulated signal for testing posi-

.P tive and negative rate bistable t= =

action

6) Quadrant Power Tilt Monitor
  • w
7) P8 and P10 permissives and the 25%

High Flux Low Setpoint Trip.

[E 2.

Nuclear Inter-

  • S(l)

NA T(2)

R

1) Once/ shift when in service y

mediate Range

2) Log Level; bistable action (permis-ow' sive, rod stop, trips) 3.

Nuclear Source

  • S (l)

NA T(2)

R

1) Once/ shift when in service
2) Bistable aEtion (alarm, trips)

Range i

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 T(3)
3) Control Rod Bank Insertion Limit Monitor mg mm 5.

Reactor Coolant Flow S

R.

M NA g$

mm 6.

Pressurizer Water Level

_S R'

M NA gg 7.

Pressurizer Pressure S

R M

NA 0(

8.

4KV Voltage & Frequency NA R

M NA Reactor protection circuits only 3y 8a. RCP Breakers NA

'~R T

NA e

/

yy TABLE TS.4.1-1 (Pcre 2 of 5)

~ l OE E" E MINIMUM FREQUENCIES FOR CHECKS. CALIBRATIONS AND n

TEST OF INSTRUMENT CHANNELS CC Ry Channel Functional-Response

$, g Description Check Calibrate Test Test Remarks cc I

E3 9.

Analog Rod Position S(l)

R T(2)

NA

  • 4,
1) With step counters M(2)
2) Rod Position Deviation Monitor "e

Tested by updating computer bank 8

i count and comparing with analog g$g rod position test signal

$ g 10.

j Rod Position Bank S(1,2)

NA T(3)

NA

1) With analog rod position "g

Counters M(3)

2) Following rod motion in excess of six inches when the computer is Eg out of service
3) Control rod banks insertion limit

'Dg monitor and control rod position j**

w.

deviation monitors

  • " 11.

Steam Generator Level S

R M

NA

$ M 12.

Steam Generator Flow S

R M

NA Mismatch i

13.

Charging Flow S

R NA NA 14.

Residual Heat Removal S(l)

~R NA NA

1) When in operation Pump Flow 15.

Boric Acid Tank Level D

R(1)

M(1)

NA

1) Transfer logic to Refueling Water Storage Tank 16.

Refueling Water Storage W

R M(1)

NA

1) Functional test can be performed Tank Level mg by bleeding transmitter 7 $.

17.

Volume Control Tank S

R NA NA i oc s t **

i ws 18a. Containment Pressure S

R M(1)

NA Wide Range Containment Pressure

oP SI Signal
1) Isolation Valve Signal 18b. Containment Pressure S

R M

NA Nar ow Range Containment Pressure Steam Line Isolation

Q'y8 TABLE TS.4.1-1 (Page 3 of 5)

Kk QQ MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND D0 TEST OF INSTRUMENT CHANNE_LS UU iR Channel Functional Response E, E, Description Check Calibrate Test Test Remarks c: c l

EE 18c. Containment Pressure S

R M

NA I

Containment Spray nw r

18d. Annulus Pressure (Vacuum Breaker)

NA R

R NA a@

19.

Auto Load Sequencers NA NA M

NA l

n. a.

v i

55 20.

Boric Acid Make-up Flow NA R

NA NA 5E Channel f f 21.

Containment Sump Level NA R

R NA Includes Sumps A, B, and C 22.

Accumulator Level and S

R R

NA 3

g.

Pressure

]_ " _ ' "

23.

Steam Generator Pressure S

R M

NA 24.

Turbine First Stage S

R M

NA g.

Pressure ES EN 25.

Emergency Plan Radiation

  • M R

M NA Includes those named in the emergency Instruments procedure (referenced in Spec. 6.5.A.6) 26a. Protection Systems NA NA M

NA Includes reactor trip logic for both the Logic Channel Testing undervoltage and shunt trips 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 yg trip attachment.

26c. Manual Reactor Trip NA NA R

NA Includes independent testing of both

,g' undervoltage and shunt trip circuits.

m:

The test shall also verify the operabil-t" g

ity of the bypass breaker.

J J

yy TABLE TS.4.1-1 (Pcgi 4 cf 5)

Nd E3 MINIMUM FREQUENCIES FOR CHECRS. CALIBRATIONS AND "W

TEST OF INSTRUMENT CHANNELS UU My Channel Functional Response E, g, Description Check Calibrate Test Test Remarks E E 26d. Reactor Trip Bypass NA NA M(1)

R'(2)

1) Manually trip the undervoltage trip
  1. p Breaker attachment remotely (i.e. from the protection system racks).

w, e

2) Automatically trip the undervoltage g

trip attachment a g 27.

Turbine Overspeed NA R

M NA s'

Protection Trip Channel e

E E 28.

Deleted 29.

Deleted z z

? ? 30.

Deleted pg 31.

Seismic Monitors R

R NA NA 32.

Coolant Flow - RTD S

R M

NA

." ?

Bypass Flowmeter pR 33.

CRDM Cooling Shroud S

NA R

NA FSAR Page 3.2-56 m

34.

Reactor Gap Exhaust Air

.'?

Temperature S

NA R

NA

$ $ 35a. Post-Accident Monitoring Instruments M

R NA NA Includes all those in Table TS.3.15-1 oo ai (except for containment hydrogen monitors which are separately specified in this table)

b. Post-Accident Monitoring Qp Radiation Instruments D

R M

NA Includes all those in Table TS.3.15-2 g{

36.

Steam Exclusion Actuation 3g System W

Y M

NA See FSAR Appendix I,Section I.14.6 o.

mn 37.

Overpressure Mitigation System NA R

R NA Instrument Channels for PORV Control

  • 4 Including Overpressure Mitigation System i

o yy TABLE TS.4.1-1 (P;ge 5 cf 5) na

,j MINIMUM FREQUENCIES FOR CHECKS. CALIBRATIONS AND s*

nn TEST OF INSTRUMENT CHANNELS Oo MM SS Channel Functional Response yy Description Check Calibrate Test Test Remarks

o. o.

yp 38.

Degraded Voltage pp 4 KV Safeguard Busses NA R

M NA we 39.

Loss of Voltage-

.8 8

4 KV Safeguard Busses NA R

M NA i

f f 40.

Auxiliary Feedwater

.g g Pump Suction Pressure NA R

R NA ll 41.

Auxiliary Feedwater Pump Discharge Pressure NA R

R NA f f 42.

NaOH Caustic Stand Pipe Level W

R M

NA 43.

Control Room Ventilation gg System Chlorine Monitors S

Y M(1)

NA 44.

Hydrogen Monitors S

Q(2)

M NA mm 45.

Containment Temperature g

Monitors M

R NA NA E*

~

S - Shift

    • D - Daily o,

W - Weekly f*,0*

M - Monthly gy Q - Quarterly Qp P - Prior to each startup if not done previous week T - Prior to each startup following shutdown in excess of 2 days if not done in the previous 30 days Y - Yearly

  • H vs R - Each refueling shutdown b

NA - Not applicable ww See Specification 4.1.D i

  • 4 1

(1) Verification of the chlorine monitor control logic only.

(2) Test will be conducted per manufacturer's recommendations.

Table TS.4.1-2A MINIMUM FREQUENCIES FOR EQUIPMENT TESTS FSAR Sect.

Test Frequency Reference 1.

Control Rod Assemblies Rod drop times All rods during each 7

of full length refueling shutdown or rods following each removal of the reactor vessel head; affected rods following maintenance on or modification to the control rod drive system which could affect performance of those specific rods l

2.

Control Rod Acsemblies Partial move-Every 2 weeks 7

ment of all rods 3.

Pressuriger* 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 PORVs Functional Every 18 months 8.

Deleted 9.

Primary System Leakage Evaluate Daily 4

10.

Deleted 11.

Turbine stop valves, Functional Monthly (l) 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.

Prairie Island Unit 1 - Amendment No. 26, 47,. 49, 57, 66, 75 Prairie Island Unit 2 - Amendment No. 26, 41, da, 51, 54,68

,f UNITED STATES e

' 't e

NUCLEAR REGULATORY COMMISSION 3

..1 WASHINGTON, D. C. 20555 e

e

\\,,,,,/

. NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR-60 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

-T6e application for amendment by Northern States Power Company (the licensee) dated April 5, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon l

defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part l

51 of the Comission's regulations and all applicable requirements have been satisfied.

l

i l

ATTACHMENT TO LICENSE AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE N0. DPR-60 DOCKET NO. 50-306 THIS AMENDMENT IS EFFECTIVE UPON CYCLE 10 STARTUP SCHEDULED FOR NOVEMBER 1985 On the effective date of this amendment, replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert Table TS 3.5 Table TS 3.5-2 (page 1 of 2)

(page 1 of 2)

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

(page 2 of 2)

Table TS. 4.1-1 Table TS. 4.1-1 (5 pages)

(5 pages)

Table TS. 4.1-2A Table 4.1-2A W

-,,-,._r-m,

.,e~

~,--.

,,, ~, - -.,,,, - --,, - ~,

n

--,~,

c-e.-.

,y TABLE TS.3.5-2 (Page 1 of 2)-

OS yp INSTRUMENT OPERATING CONDITIONS FOR REACTOR TRIP CC g g 1

2 3

4 MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF yy OPERABLE DEGREE OF BYPASS CONDITIONS OF COLUMN 0

0-FUNCTIONAL UNIT CHANNELS REDUNDANCY CONDITIONS (1) 1 OR 2 CANNOT BE MET s

pp 1.

Manual 2

1 Notes 3, 4 l

N*

2.

Nuclear Flux Power Range

  • i 5 '

low setting 3

2 2 of 4 power Maintain hot shutdown

  • gg high setting 3

2 range channels positive rate 3

2 gFeater than y@

negative rate 3

2 10% F.P. (low g@

setting only) nn 3.

Nuclear Flux Intermediate 2

1 2 of 4 power Maintain hot shutdown 22 Range range channels Note 2 my greater than O'

  • 10% F.P.

4.

Nuclear Flux Source Range 2

1 1 of 2 inter-Maintain hot shutdown mediate range Note 2 channels greater than 10 10 amps 5.

Overtemperature AT 3

2 Maintain hot shutdown 6.

Overpower AT 3

2 Maintain hot shutdown 7.

Low Pressurizer Pressure 3

2 Maintain hot shutdown 8.

Hi Pressurizer Pressure 2

1 Maintain hot shutdown ne 9.

Pressurizer-Hi Water Level 2

1 Maintain hot shutdown 7 @.

on w 10.

Low Flow in one loop (>10% F.P.)

2/ loop 1/ loop Maintain hot shutdown Low Flow both loops (>10% F.P.)

2/ loop 1/ loop

" d.

o 11.

Turbine Trip 2

1 Maintain < 50% of

"'F (Overspeed Protection) rated power O

12.

Lo-Lo Steam Generator 2/ loop 1/ loop Maintain hot shutdown Water Level

.1

TABLE TS.3.5-2 (Page 2 of 2) mm EU INSTRUMENT OPERATING CONDITIONS FOR REACTOR TRIP W7 1

2 3

4 gy MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF yy OPERABLE DEGREE OF BYPASS CONDITIONS OF COLUMN CONDITIONS (1) 1 OR 2 CANNOT BE MET g&

FUNCTIONAL UNIT CHANNELS REDUNDANCY cc l

EE 13.

Undervoltage 4KV RCP Bus 1/ bus 1/ bus Maintain hot shutdown 14.

Underfrequency 4KV Bus 1/ bus 1/ bus Maintain hot shutdown gg 15.

Control Rod Misalignment Monitor gg

a. Rod position deviation 1

Log data required by

b. Quadrant power tilt 1

TS 3.10 I and TS 3.10 J

a. a.

g8 16.

RCP Breakers Open 2

1 Maintain hot shutdown co 17.

Safety Injection Actuation Signal 2

1 Maintain hot shutdown 18.

Lo Feedwater Flow 1/ loop 1/ loop Maintain hot shutdown

,y co m 19.

Automatic Trip Logic including Reactor Trip Breakers **

2 1

Notes 3, 4 Note 1: Automatic permissives not listed Note 2: When bypass condition exists, maintain normal operation Note 3: With the number of operable channels one less than the minimum operable channels requirement, 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 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.

Note 4: When in the hot shutdown condition with the number of operable channels one less than the minimum operable channels 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 gg trip breakers within the next hour.

gg F.P. = Full Power "d

= One additional channel may be taken out of service for low power physics testing o-

= Includes both undervoltage and shunt trip circuits and if either circuit becomes inoperable the respective w"y channel shall be considered inoperable.

N

L 6

mm Rg TABLE TS.4.1-1 (Page 1 of 5) l Eg MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND ss TEST OF INSTRUMENT CHANNELS i

Channel Functional Response Description Check Calibrate Test Test Remarks 55

  • i.

1.

Nuclear Power S(l)

D(2)

M(3)

R t

1) Once/ shift when in service we Ibnge M(4)

Q(4)

M(5)

2) Heat balance M(6) i
3) Signal to AT; bistable action gg P(7)

(permissive, rod stop, trips), with mo the exception of the items covered E.E.

in Remark #7.

I!

4) Upper and lower chambers for axial NE off-set using in-core detectors z z
5) Simulated signal for testing posi-tive and negative rate bistable t=* *a action
6) Quadrant Power Tilt Monitor w
7) P8 and P10 permissives and the 25%

w*

High Flux Low Setpoint Trip.

[E 2.

Nuclear Inter-

  • S(1)

NA T(2)

R

1) Once/ shift when in service mediate Range
2) Log Level; bistable action (permis-l M,o c

sive, rod stop, trips) 3.

Nuclear Source

  • S (l)

NA T(2)

R

1) Once/ shift when in service Range
2) Bistable action (alarm, trips) 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 T(3)
3) Control Rod Bank Insertion Limit Monitor mg ma 5.

Reactor Coolant Flow S

R M

NA g$

i mm 6.

Pressurizer Water Level S

R M

NA g

7.

Pressurizer Pressure S

R M

NA Q

8.

4KV Voltage & Frequency NA R

M NA Reactor protection circuits only 8a. RCP Breakers NA R

T NA

y'p2 TABLE TS.4.1-1 (Page 2 of'5)

~

l E!1 p, p, MINIMUM FREQUENCIES FOR CHECKS. CALIBRATIONS AND Oe TEST OF INSTRUMENT CHANNELS 5E yy Channel Functional Response

((

Description Check Calibrate Test Test Remarks i

k Analog Rod Position S(1)

R T(2)

NE ',

1) With step counters

" f[

9.

?

M(2)

2) Rod Position Deviation Monitor N P Tested by updating computer bank 8 :

I count and comparing with analog g-rod position test signal a5 10.

Rod Position Bank S(1,2)

NA T(3)

NA

1) With analog rod position

@u

" "g Counters M(3)

2) Following rod motion in excess of six inches when the computer is out of service
3) Control rod banks insertion limit

%ljg monitor and control rod position deviation monitors

  • a

}" ?* 11.

Steam Gene'rator Level S

R NA

- muu' 12.

Steam Generator Flow S

R M

NA Mismatch 13.

Charging Flow S

R NA NA 14.

Residual Heat Removal S(l)

R NA NA

1) When in operation Pump Flow 15.

Boric Acid Tank Level D

R(1)

M(1)

NA

1) Transfer logic to Refueling Water Storage Tank 16.

Refueling Water Storage W

R M(1)

'NA

1) Functional test can be performed

,s g Tank Level by bleeding transmitter EfE-a s.

17.

Volume Control Tank S

R NA NA ws 18a. Containment Pressure S

R M(1)

NA Wide Range Containment Pressure o"

SI Signal

1) Isolation Valve Signal

"' f' 18b. Containment Pressure S

R H

NA Narrow Range Containment Pressure

[

Steam Line Isolation

yy TABLE TS.4.1-1 (Page 3 of 5)

~

EE QQ MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND o ao TEST OF INSTRUMENT CHANNELS UU Ry Channel Functional Response

&E Description Check Calibrate Test Test Remarks ec

..NA EE 18c. Containment Pressure S

R M

Containment Spray j

ww 18d. Annulus Pressure (Vacuum Breaker)

NA R

R NA gg l

19.

Auto Load Sequencers NA NA M-NA

o. a.

H@

20.

Boric Acid Make-up Flow NA R

NA NA S%

Channel f f 21.

Containment Sump Level..

NA R

R NA Includes Sumps A, B, and C 22.

Accumulator Level and S

R R

NA ww Pressure p_*

23.

Steam Generator Pressure S

R M

NA 24.

Turbine First Stage S

R M

NA ww Pressure

$m 25.

E'ergency Plan Radiction

  • M R

M NA Includes those named in the emergency Instruments procedure (referenced in Spec. 6.5.A.6) 26a. Protection Systems NA NA M

NA Includes reactor. trip logic for both the Logic Channel Testing undervoltage and shunt trips 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.

g

2) Automatically trip the undervoltage trip attachment.

'o 4

26c. Manual Reactor Trip NA NA R

NA Includes independent testing of both undervoltage and shunt trip circuits.

m The test shall also verify the operabil-ity of the bypass breaker.

yy TABLE TS.4.1-1 (Page 4 of 5) j

~

EE EQ MINIMUM FREQUENCIES FOR CHECKS. CALIBRATIONS AND

" #8 TEST OF INSTRUMENT CHANNELS-55 5y Channel Functional Response E[

Description Check Calibrate Test Test Remarks E E 26d. Reactor Trip Bypass NA NA M(1)

R(2)

1) Manually trip the undervoltage trip

$p Breaker attachment remotely (i.e. from the

+

wg protection system racks),

i, i

2) Automatically trip the undervoltage trip attachment g

g 27.

Turbine Overspeed NA R

M NA E&

Protection Trip Channel a m E g 28.

Deleted z2 29.

Deleted 30.

Deleted

,Sg 31.

Seismic Monitors R

R NA NA 32.

Coolant Flow - RTD S

R M

NA Bypass Flowmeter l

,$R 33.

CRDM Cooling Shroud S

NA.

R NA FSAR Page 3.2-56

e. 34.

Reactor Gap Exhaust Air Temperature S

NA R

NA I

E % 35a. Post-Accident Monitoring ~ M R

NA NA Includes all those in Table TS.3.15-1 Instruments (except for containment hydrogen monitors which are separately specified in this table) l

b. Post-Accident Monitoring gy Radiation Instruments D

R M

NA Includes all those in Table TS.3.15-2 em 36.

Steam Exclusion Actuation 3g

-System W

Y M

NA See FSAR Appendix I,Section I.14.6 oF mn 37.

Overpressure Mitigation w

System NA R

R NA Instrument Channels for PORV Control

  • 4 Including Overpressure Mitigation System

f-TABLE TS.4.1-1 (Pcga 5 cf 5) l j

,,.o EO QQ MINIMUM FREQUENCIES FOR CHECKS CALIBRATIONS AND gg TEST OF INSTRUMENT CHANNELS e

ss$$

Channel Functional Response yg Description Check Calibrate Test Test Remarks

o. o.

gg 38.

Degraded Voltage

-(

pp 4 KV Safeguard Busses NA R

M NA !

f NH 39.

Loss of Voltage i I 4 KV Safeguard Busses NA R

M NA i f f 40.

Auxiliary Feedwater gg Pump Suction Pressure NA R

R NA V

ll 41.

Auxiliary Feedwater Pump Discharge Pressure NA R

R NA "n

f f 42.

NaOH Caustic Stand Pipe Level W

R M

NA 43.

Control Room Ventilation gg System Chlorine Monitors S

Y M(1)

NA

~~

44.

Hydrogen Monitors 5

Q(2)

M NA 45.

Containment Temperature gg Monitors M

R NA NA

.E.N S - Shift

    • D - Daily W - Weekly
  • " M - Monthly Q - Quarterly Qp

,y co m P - Prior to each startup if not done previous week T - Prior to each startup following shutdown in excess of 2 days if not done in the previous 30 days Y - Yearly

  • M R - Each refueling shutdown NA - Not applicable uL See Specification 4.1.D "4

(1) Verification of the chlorine monitor control logic only.

(2) Test will be conducted per manufacturer's recommendations.

.1

Table TS.4.1-2A MINIMUM FREQUENCIES FOR EQUIPMENT TESTS FSAR Sect.

Test Frequency Reference 1.

Control Rod Assemblies Rod drop times All rods during each 7

of full length refueling shutdown or rods following each removal of the reactor vessel head; affected rods following maintenance on or modification to the control rod drive system which could affect performance of those specific rods I

.2.

Control Rod Assemblies Partial move-Every 2 weeks 7

ment of all rods 3.

Pressurizeg _ 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 PORVs Functional Every 18 months 8.

Deleted 9.

Primary System Leakage Evaluate Daily 4

10.

Deleted 11.

Turbine et,p valves, Functional Monthly (l) 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.

Prairie Island Unit 1 - Amendment No. 26, 47, 49, 57, 66, 75 Prairie Island Unit 2 - Amendernt No. 26, 41, 45, 51, 54, 68

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