ML18057A554

Proposed Tech Specs Change Request Re Neutron Monitoring Upgrade Page Changes

ML18057A554
Person / Time
Site:	Palisades
Issue date:	11/02/1990
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057A553	List: ML18057A552 ML18057A554
References
NUDOCS 9011070261
Download: ML18057A554 (20)

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~I r

ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST NEUTRON MONITORING UPGRADE

~9011070261 901102 PDR ADOCK 05000255 p

Poe*

)

I I

I PAGE.CHANGES November 2, 1990 9 Pages

r 3.17 INSTRUMENTATI' AND CONTROL SYSTEMS (Cont'd) e If the bypass is not effected, the out-of-service channel (Power Removed) assumes a tripped condition (except high rate-of-change power, variable high power and high pressurize~ pres$ure), <1> which

-results in a one-out-of-three Channel logic.

If, in the 2 of 4 logic system of either the reactor protective system or the engineered safeguards system, one channel is bypassed and a second channel manually placed in a tripped condition, the resulting logic is 1 of

2.

At rated power, the minimum operable variable high power level channels is 3 in order to provide adequate flux tilt detection.

If only 2 channels are operable, the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts.

The engineered safeguards system provides a 2 out of 4 logic on the signal used to actuate the equipment connected to each of the 2 emergency diesel generator units.

Two source-range channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is not visible on the wide-range nuclear instrumentation or above 10-4% of rated power.

This ensures that redundant source-range instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are only visible on the source-ran*ge channels.

In the event only one source-range channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of wide-range instrumentation, a startup can be performed in accordance with footnote (d) of Table 3.17.4.

The Recirculation Actuation System (RAS) initiates on a 1 out.of 2 taken twice logic scheme.

Any one channel declared inoperable shall be placed in a bypass condition to ensure protection from ~n inadvertent RAS Actuation. Since the bypassing of a _channel introduces the possibility for a failure to receive an automatic RAS actuation signal, the time period in the bypassed condition is limited.

The Zero Power Mode Bypass can be used to bypass the low flow, steam generator low pressure, and TM/LP trips <2> for all four Reactor Protective system -channels to perform -contra l rod testing or* to per-form low power physics testing below normal operating -

temperatures.

The requirement to maint~in cold shutdown boron concentration when in the bypass condition provides additional assurance that an accidental criticality will not occur.

To allow

_*low power physics testing at reduced temperature and pressu~e, the requirement for cold shutdown boron concentration is not required and the allowed power is increased to 10- 1%.

References (1)

Updated FSAR, Section 7.2.7 (2)

Updated FSAR, Section 7.2.5.2 3-77 Amendment No. JJ~, ii~

TSPR9004

Table 3.17.1 Instrumentation Operating Requirement for Reactor Protective System

2.

3.

4.

5.

6.

7.

8.

9.

IO.

Functinal Unit Manual (Trip Buttons) (g)

Variable High Power Level (g)

Wide Range Channels (g)

Thermal Margin/

Low-Pressurizer Pressure (g)

High-Pressurizer Pressure (g)

Low Flow Loop (g)

Loss of Load (h)

Low Steam Generator Water Level (g)

Minimum Operable Channels I

2

• 2

I 2/Steam Gen Cb>

Low Steam*

2/Steam Generator Pressure Gen Cb>

(g)

High Containment Pressure (g)

(a)

Bypass automatically removed.

Minimum Degree of Redundancy *

• None I

I I

I None I/Steam Generator I/Steam Generator I

Permissible Bypass Conditions None None Below Io*43<e> or Above I5% Rated Power (a)

Except as Noted in (c).

Below Io*43<e> of Rated Power<a> and greater than cold shutdown boron concentration.

None Below Io*43<e> of Rated Power <a> and greater than cold shutdown boron concentration.

None None Bel ow Io*43<e> of Rated Power <a> and greater than cold shutdown boron concentration.

None (b).

One of the inoperable channels must be in the tripped conditton.

(c)

Two channels required if TM/LP, low steam generator or low-flow channels are bypassed.

(d)

If only two channels are operable, load shall be reduced to 70% or less of rated power.

(e)

For low power physics testing, io*4% may be increased to I0. 1% and cold shutdown boron concentration is not required.

(f)

Axial Offset operability requirements are given in Specification 3.Il.2.

(g)

Required operable if any clutch power supply is energized.

(h)

Automatically bypassed below I5% power.

3-78 Amendment No.

JJ~, ii~

TSPR9004

J Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Minimum Minimum Permissible Operable Degree of Bypass No.

Functional Unit Channels Redundancy Conditions 1

S IRWT Low-Level 4

NA

One channel may be Switches inoperable for a period of 7 days.

2 AT-Power 3<c>

1 None Comparator 3

(Deleted) 4 Air Cooler Service 1

None None Water Flow Instruments 5

Primary and 1

None N/A Secondary Rod Insertion and Out-of-Sequence Monitors 6

Fuel Pool Building

1.

None As Requested Under Crane Interlocks Administrative Controls. <a>

7 Source-Range 2

1<d)

Not required Above 10*43 Channels of Rated Power.

(a)

Crane shall not be used to move material past the fuel storage pool unless the interlocks are available.

(b)

If a channel is declared inoperable, it shall be placed in a bypass condition.

Minimum degree of redundancy is not applicable to the SIRWT low-level switches.

(c)

If only two channels are operable, load shall be reduced to 70% or less of rated power.

(d)

Minimum operable channels shall be one (1) and minimum degree of redundancy is zero (0) if shutdown neutron power levels indicated on the wide range channels are greater than three times the lowest decade in which neutron visibility can be confirmed.

Neutron visibility will be ccinfirmed through observation of reactivity changes on neutron power level (including a l/M plot during reactor start-up) and comparing the observed changes to the changes noted on previous similar start-ups.

Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.

3-81 TSPR9004

~)f~lid¢/'4PJ /'/J Amendment No. JiJ, Ji~

I

Table 3.25.1 ALTERNATE SHUTDOWN MINIMUM EQUIPMENT

.. No Instrumentation Minimum Equipment.Readout *Location 1

Pressurizer Pressure 1

Cl SO (PI-0110) 2

• Pressurizer Level I

CISO (LI-0102E) 3 Reactor Coolant Hot Leg I/Loop ClSOA Temperature (TI-0112HAA)

(TI-0122HAA) 4 Reactor Coolant Cold.

,I/Loop ClSOA Leg Temperature (TI-Ol 12CAA)

(TI-0122CAA)

.. 5 Steam Generator l/S.G..

• ClSOA Pressure (PI-0751E)

(PI-0752E) 6 St~am Generator Level l/S.G.

Cl SO (LI-0757C)

( LI-0758C) 7 Source Range 1

ClSOA Neutron Monitor (NI-l/3C) 8 Auxiliary Feedwater I

CISO Suction Pressure (PS-07410) 9 SIRW Tank Level I

. tlSOA (LT-03328) 10 Auxiliary Feedwater l/S.G.

CISO Flow Rate (Fl-07278)

(Fl-07498) 3-135 Amendment No. iii TSPR9004

3-136 Amendment No. iii TSPR9004

TABLE 4.1.1 HinilllJll Fr~uencies for_Checks, Calibrations and Testing of Reactor Protective System(S)

Channel Description

1.

Power ~ange Safety Channels

2.

Wide-Range Neutron Monitors

3.

Reactor Coolant Flow

4.

Thermal Margin/Low Pressurizer Pressure

5.

High-Pressurizer Pressure TSPR9004 Surveillance Function

a. Check (7)

b. Check(3)

, c. Test

d.

Cal ibrate(6)

a. Check

b. Test

c. Calibrate

a. Check

b.

Calibrate

c. Test

a. Check: (8)

( 1) Teq:ierature Input (2) Pressure Input

b. Calibrate

( 1) Teq:ierature Input (2) Pressure Input

c. Test

,a. Check (8)

,b. Calibrate

• C.

Test Frequency s

D H(2)

R s

p R

s R

H(2) s R

M(2) s R

M(2) 4-3

a.

b.

c.

d.

Survei"l lance Method COll1>8rison of four-power channel* readings.

Channel adjustment to agree with heqt balance calculation. Repeat whenever flux-6T power COll1>8rators alarms.

Internal test signal.

Channel alignment through measurement/adjustment of internal test points.

a. COll1>8rison of channel indications.

b.

Internal test signal.

c. Channel alignment through measurement/adjustment of internal test points.

a.

COll1>8rison of four separate total flow indications.

b.

Known differential pressure applied to sensors.

c. Bistable trip tester.(1)(4)

a. Check:

(1)

COll1>8ri son of four separate calculated trip pressure set point indications.

(2) COll1>8rison of four pressurizer pressure indications.

Same as S(a) below.

b. Calibrate:

(1)

Known resistance substituted for RTD coinci dent with known pressure and power input.

(2) Part of S(b) below.

c. Bistable trip tester.(1)

a.

COll1>8rison of four separate pressure Indications.

b.

Known pressure applied to sensors.

c. Bistable trip tester.(1)

Amendnent No.Je, t.I>, 118, 1Je

TABLE 4.1.3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous InstrLmentation and Controls (Cont'd)

Channel Description

1.

Source Range Neutron Monitors

2.

Primary Rod Position Indication System

3.

Secondary Rod Position Indication System

4.

Area Monitors Note:Process Monitor Surveillance Requirements are located in Tables 4.24-1 and 4.24-2

5.

Emergency Plan Radiation Instruments

6.

Environmental Monitors

7.

Pressurizer Level Instruments TSPR9004 Surveillance Function

a. Check

b. Test

c. Calibrate

a. Check

b. Check

c. Calibrate

a. Check

b. Check

c. Calibrate

a. Check

b. Calibrate

c. Test

a. Calibrate

b. Test

a. Check 1 b. Calibrate

a. Check

b. Calibrate I,c. Test Frequency s

p R

s M

R s

M R

D R

M A

M M

A s

R M

4-10 Surveillance Method

a. Comparison of both channel count rate indications when in service.

b.

Internal Test Signals.

c. Channel alignment through measurement/adjustment of internal test points.

a. Comparison of output data with secondary RPIS.

b.

Check of power dependent insertion limits monitoring system.

c. Physically measured rod drive position used to verify system accuracy.

Check rod position interlocks.

a. Comparison of output data* with primary RPIS.

b.

Same as 2(b) above.

c. Same as 2(c) above, including out-of-sequence alarm function.

a.

Normal readings observed and internal test signals used to verify instrLment operation.

b.

Exposure to known external radiation source.

c. Detector exposed to remote operated radiation check source or integral electronic check source.

a. Exposure to known radiation source.

b *. Battery check.

a. Operational check.

b.

Ve~ify airflow indicator.

a. Comparison of two wide and two narrow range independent level readings..

b.

Known differential pressure applied to sensor.

c. *signal to meter relay adjusted with test device.

Amendment No.12, J8, 87, 117, 118

~.

Table 4.21.1 (Cont'd>

ALTERNATE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Surveillance Chal'Vlel Description Function Frequency Surveillance Method

7. Source Range Neutron Monitor CNI-1/3C)

a. Test Prior to Startup 141*

a.* Internal test signal (performed under Table 4.1.3)

8. Auxiliary Feedwater Low Suction Pressure Switch CPS-07410)

9. SIRW Tank Level Indication CLl-033280

10. Auxiliary Feedwater Flow Rate (2)

Indication (FI -On7B)

( F 1-07498)

11. Auxiliary Feedwater Flow Control (3)

Valves CCV-On7 & CV-0749)

12. Auxiliary Feedwater PUil> Inlet Steam Valve CCV-05228)

NOTES:

a. Calibrate

a. Check (1)

b. Calibrate

a. Calibrate

a.

Check

a.

Check Refueling*

cycle Quarterly Refueling cycle Refueling cycle Refueling cycle Refueling cycle

--(-1) Quarterly checks are not required when the plant is less than 325°F.

<2>

Satisfies Table 4.1.3-15 Requirement.

(3) See Specification 4.9b.

(4) Prior to each startup, if not done previous week.

a.

Apply known pressure to pressure sensor.

a.

Coq>are indepeudent level readings.

b.

Apply known differential pressure to level sensor.

a.

Apply known differenti.al pressure to sensor(s).

a.

Verify Control.

a.

Verify Control.

(Next page is 4-90) 4-88 Amenctnent No.I,, J22 TSPR9004

c.

5.3 5.3.2 NUCLEAR STEAM,PPLY SYSTEM (NSSS) (Cont'd) e Reactor Core and Control

a.

The reactor core shall approximate a right circular cylinder with

_ - an equivalent diameter of about 136 inches and.an active height of about 132.inches.

b.

The reactor core shall consist of approximately 43,000 Zircaloy-4 clad fuel rods containing slightly enriched uranium in the form of sintered U02 pellets. The fuel rods shall be grouped into 204 assemblies. A core plug or plugs may be used to replace one or more fuel assemblies subject to the analysis of the resulting

• power distribution.

c.

The fully loaded core shall contain approximately 211,000 pounds U02 and approximately 56,000 pounds of Zircaloy-4.

Poison may be placed in the fuel bundles for long term reactivity control.

d.

The.core excess reactivity shall be controlled by a combination of boric acid chemical shim, cruciform control rods, and mechanically fixed absorber rods where required.

Forty-five control rods shall be distributed throughout the core as shown in Figure 3-5 of the FSAR.

Four of these control rods may consist of part-length absorbers.

5.3.3 Emergency Core Cooling System TSPR9004 An emergency core cooling system shall be installed consisting of var*; ous subsystems each with i nterna 1 redundancy.

These subsystems shall include four safety injection tanks, two high-pressure and two low-pressure safety injection pumps, a safety injection and refueling water storage tank, and interconnecting piping as shown in Section 6 of the FSAR.

5-3 Amendment No. ~~' ~~

- !I ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST NEUTRON MONITORING UPGRADE

. MARKED* UP PAGES November 2, 1990 9 P.ages

'3. 17

.INSTRUMDrl'A. AND CONTROL SYSTEMS (Coutd) e If the bypass is not effected, the out-of-service channel (Power Removed) assumes a tripped condition (except high rate-of-~y,nge power, variable high power and high pressurizer pressure),

which results in a one-out-of-three channel logic. If, in the 2 of 4 logic system of either the reactor *protective systea or the -

engineered safeguards system, one channel is bypassed and a second channel manually placed in a tripped condition, the resulting logic is 1 of 2.

At rated power, the minimum operable variable high power level channels is 3 in order to provide adequate flux tilt detection.

If only 2 channels are operable, the reactor power level 1.s reduced to 70% rated power which protects the reactor from possibly exceeding desig~ peaking factors due to undetected flux tilts.

The engineered safeguards system provides a 2 out of 4 logic on the signal used to actuate the equipment connected to each of the 2 emergency diesel generator units.

S' Ov l>C&.

• P °"""'-At..

Two ela~e Yp channels are available any time reactivity changes are deliberately being introdused into the reacto.r and the neutron power is not visible on the.le;~range nuclear instrumentation or above 10-~% of rated power.

This ensures that redundant ltait!...,ap--'-q_,_

instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are onlv visible on

S!l!l~-~.._

S'ov-.'&4,-

the 1K4M'C=up channels.

In the event only one acasc-up range channel is available and the neutron.power level is,~ffici~ntly high that -

it is being monitored by both channels of ~-range instrumentation,.

a startup can be performed in accordance with footnote _(d) of Table 3.17.4.

The Recirculation Actuation System (RAS) initiates on a 1 out of 2 t~en twice logic scheme.

Any one channel declared inoperable shall be placed in a bypasa condition to ensure protection from an inadvertent RAS actuation.

Since the bypassing of a channel intro-duces the possibility for a failure to receive an automatic RAS actuation signal, the time period in the bypassed condition is limited.

Tba Zero Power Koda Bypa** can ba uaad to bypf~' the lov flov, steam generator lov presaure, and TM/LP trip*

for all four Reactor Protective sy*tea channel* to parfo1:11 control rod testing or to perf 01:11 lov povar phy*ica teatina below normal operating temperature*.

The requir..-nt to_.. intain cold shutdown boron--

.. --*concentration when in the bypaaa* condition provide* additional aaauranc* that an accidental criticality will not occur.

To allov low power pbyaic* teating at reduced t911perature and preaaura, the requirem.nt for cold abutdown boron concentration i* not required and the allavecl power ia incraaaed to 10-1%.

Ref erencea (1)

Updated FSAll, Section 7.2.7.

(2)

Updated FSAa, Section 7.2.5~2

/

/

I I

I 3-77 AMDdaent Ro. tu. -+i*-

" 31, UH TSP0389-0001-RL02

J.1 I.

Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System Minimum Operable No.

1.

Fun~tional Unit Channels Manual (Trip 1

Buttons) (g)

2.

Variable High Power Level (g) tv1i:I~

3.

~Range Channels (g)

4.

Thermal Margin/

Low-Pressurizer Pressure (g).

s.

6.

High-Pressurizer Pressure (g)

Low Flow Loop (g)

7.

Loss of Load (h)

8.

Low Steam Gen-erator Water Level (g)

9.

Low Steam Gen-erator Pressure (g)

10.

High Contaimlent Pressure (g) 2(b,d) 2 1

2/S~~fD.

Gen (a) Bypass automatically remO'led.

Minimum Degree of Redundancy None 1

1 1

1 None 1 /Steam

• Generator l/Steam.

Generator 1

Permissible Byp@SS Conditions None None Below 10-4%(e) or Above 15% Rated Power(a) Except as Noted in (c)

Below 19-4%(e) of Rated Power(a and greater than cold shutdown boron con-centration.

None

• -4 (e)

Below(19 of Rated Power a and greater than cold shutdown boron con-centration.

None None Below 19-4%(e) of Rated Power(a and greater than cold shutdown boron con-centration.

None (b) One of the iJloperable channels must be in the tripped condition.

(c) Two channela"rtq111re41 if TM/LP, low steam generator or lov-flov channels are bypassed~

(d) If only two channels are operable, load shall be reduced to 70% or less of rated power.

_4 1

(e) For low power physics testing, 10

% may be increased to 10- % and cold shutdown boron concentration is not required.

( f) Axial Off set operability requirements are giyen-in Spaeification J-*~ 11. 2.

(g) Required operable if any clutch power supply is energized.

(h) Automatically bypassed below 15% power.

3-78 TSP0588-0025-NL02-NL04 Amendment No. U8, -He-March i3, 199C"

/

i_

No 2

3 4

5 6

. 7 (a)

Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Minimum Minimum Operable Degree of Functional Unit Channels Redundanci SIRWT Low-Level 4

NA(b)

. Switches 6T - Power 3(c) 1 Comparator (Deleted)

Air Cooler Service 1

None Water Flow Instruments Primary and Secondary 1

None Rod Insertion and Out-of-Sequence Monitors Fuel Pool Building 1

None Crane Interlocks

~

....... lia,.. -.

l(d)

Statt Hp Channels 2

Crane shall not be used to move material past the fuel unless the interlocks are available.

Permissible Bypass Conditions One channel may be inoperable for a(b) period of 7 days None None NA As Requested Under AdministtUive Controls No!4Required Above I

10

% of Rated Power storage pool (b)

If a channel is declared inoperable, it shall be placed in a bypass l

condition.

Minimum degree of redundancy is not applicable to the SIRWT low-level switches.

(c)

If only two channels are operab.le,_ load shall be reduced to 70%- or less of rated power.

(d)

Mini!llWI operable channels shall be one (1) and minimum degree of redu:flJi.Y is zero (0) if shutdown_ neutron power levels indicated on the range channels are greater than three times the lowest decade

/

in which neutron visibility can be confirmed.

Neutron visibility will be confirmed through observation of reactivity changes on neutron power level (including a l/M plot during reactor start-up) and comparing the observed changes to the changes noted on previous similar start-ups.

Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.

3-81 TSP0389-0001-NL02 rJ:~4a~41*1>1 /J Amendment No. l%l, 124 May 31, 1989

.--i, Table 3.25.1 ALTERNATE SHUTDOWN MINIMUM EQUIPMENT Minimum No Instrumentation Equipment 1

Pressurizer Pressure 1

(PI-0110) 2 Pressurizer Level 1

(LI-0102E) 3 Reactor Coolant Hot Leg l/Loop

• Temperature (TI-0112HAA)

(TI-0122HAA) 4 Reactor Coolant Cold Leg

-1/~oop Temperature *

(TI-Oif2CAA)

(TI-0122CAA)

S Steam Generator Pressure l/S.G.

(PI-0751E)

(PI-0752E) 6

,:Steam Generator Level l/S.G.

(LI-0757C)

(LI-0758C).

'"S" 0 CJ,.. c Q.

7 Sta*t ~P Range Neutron Monitor

,/.

(Nw661A) {NI-I; 3C.)

8 Auxiliary Feedwa.ter

- Suction Pressure -

(P~l41D).

10 Auxiliary Feedwater Flow Rate (FI-07278)

(FI-07498)

TSP1185-03l5-NL04 l/S.G.

1 1

1 Readout Location Cl SO Cl50 ClSOA Cl50A Cl50A ClSO ClSOA ClSO ClSOA Cl SO Amendment No. -Hi -

May 19, 1989

/.

1 I

Table 3.25.l (Continued)

ALTERNATE SHUTDOWN MINIMUM EQUIPMENT No ll 12 13 14 No

. 15 16 Transfer Switches Minimum Equipment Switch Location

. HS-0102A 1

Cl50 HS-01028 1

Cl50 HS-0522C Cl50 HS-0102C 1

Cl50A Minimum Controls Control Circuits

. E~i2111ent From Auxiliary FW Flow 1

Cl SO Control (HIC-0727C)

Auxiliary FW Flov 1

ClSO Control (HIC-0749C) 3-136 TSP1185-0335-NL04 Function Control Room Alarm SIG Level Indications Pressurizer Level Indications.

Aux. FW Flow Indication Aux. FW Flow Control Opens Aux. FW Pullll> Steam Valve CV-05228 Control Room Alarm SIG Pressure.Indications Hot/Cold Leg Temperature Indications NaJtr!ll\\

Mo~.tor S.rt1c"' Po~c.,.

Function Controls B S/G Aux. FW Flow Control Valve (CV-0727)

Controls A S/G Auz. FW Flov Control Valve (CV-0749)

Amendment No. -rn--

. _.'.~>' 1 P; U!9

. I l

I j

I I

I I

I

}.

I

/..

'/

I 1

. I f

../

£~

/,;

,)

I... -

1-.

• 4 I

-~

I.

I l

t: r I

I 1*

I r

TABLE 4,1.1 Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System(S)

Channel Description

1. Power Range Safety <llannela

2.

.Wide-Range..,, **,~,.

Reutron Honitora 3, Reactor Coolant Flow 4, 1'henul Margin/Low

~aaurlzer Preaaure 5_.

Bip-Preaaurizer Pressure

'88-0181-NL04-NL02 I

~ I Survelllance Function

a.

D'leclt (7) b, Check(3)

c. Teat

d. Calibrate (6)

a.

b,

c.

a.

b.

c.

a, aaect Teat Cohb>or._

aieck

.. Calibrate Test Checlta (8)

(1) Tuiperature Input (2) Preaaure Input

b. Calibrate

c.

b.

c.

(1) Temperature Input (2) Preaaure Input Teat aieck (8)

Calibrate Test Frequency s

D H(2)

R

. s p

f<

s R

H(2) s R

b.

c.

d,

b.

c..

a.

b.

c.

a.

Surveillance Method Comparison of fo~r-power channel readings.

Channel adjustment to agree with heat balance calculation. Repeat whenever flux-la power comparators alaJ'1118.

Internal test signal, Channel alignment through measurement/adjustment of internal teat.points, Comparison of hat'1 "Illa Pante *aallllna._ c-ho..,,.o J 11tt/i~1tnif,r /

Internal test signal.

c6"'!"-n~l *1he.n_,r#1-1"e4 '"1114o"~~r;""'.,,.;r-...T 1 oJ! ~*7ll>tno/ "T-.,.rr po,,7r..r;.

Comparison of four separate total flow indications.

/

Known differential pressure applied to sensors.

Bistable trip teater.(1)(4)

Check:

(1) Comparison of four aepa~ate calculated trip pressure set point indications.

( 2) Comparison of four pressurizer pressure indications.

Same as S(a) below.)

b. Caltbrate:

(1) Known resistance substituted for RlD coinci-dent with known pressure and power input.

(2) Part of 5(b) below.

H(2)

c. Bistable trip teat~r.(1) s

a. Comparison of four separate pressure indications

• R b,

Known pressure applied to sensors, H(2)

c. Bistable trip teater.(1) 4-3 Amendment No. U,,_, tt*, ~

Mgrgli J!3, 1996

'll *

(..

TABLE 4.1.l Mln1aU11 Frequencle* for Olecka, Calibrations and Testing of Miscellaneous Instl"Ullentatlon and Controls

~l Deecrletl!!!

~Ulf&G.

1. lea1t Up Rana* ~ **

llonltora

b.

c.

2.

~.,, lad Po*ieiol!a IDdlcatlaa S,.tea

c.

. ~:.

' ~' ~.. Pl'J. -~ Poaitloa

a.

Iadlcatlcm S,*tm

b.

c.~

If'*;; ; *.

I..

4. u.. llllaltor*

a.

11oee1 ~

llDDitol' I

\\

~

. :e.n.111.. oe.... t~u b.

an located ID rabl*

c.

4.24*1.... 4.24*2

'*... l'llDCJ Pia ladtatlaa

a.

~-,,,..ta b *

~.

• \\

b.

7. Preaaurtaer Level Iaatnmmt*

b.

c.

TSPJ088-0181-NL04 Surveillance Function Freguencl Oleck s

re at p

CY.o/,'61-*r'-

~

<Jleck s

CJMck M

Calibrate I

Qaeck s

Oleck M

Calibrate I

~

D Calibrate I

r.. t II Calibrate A

re at M

C2aeck M

Calibrate A

Oleck s

Caltbrate I

THt M

Survel 1 lance Method

a. Comparlaon of both channel count rate Indication* when

/

In service.

. b. Internal teat alp1ala *

~. ~~/,:/if~?;~1.A.~.r",..__.T~c//11iT-.-.T /

a.

r180D oroor.:'f ~~a vfth aecondary RPIS

/

b *

<Jleck of power dependent Insertion lialts 111>nltorln1 ayate11.

c. Physically 11eaaured rod drive position used to.verify ay*t* accuracy. Oleck rod position Interlocks *

a. Ccmparleaa of output data vlth prlaary RPIS.

b. s... *aa 2(b) above. '

c. 5-u 2(c) above, lncludlna out*of-se_quence alara function.

a. lloraal readlnp obaened and Internal test slpals used to verify tnat111111111t,operatlon.

b. lxpoaure to known external radiation source.

c. Detector expoeed to l'ellOte operated radiation check aource or tntearal electronic check.aource.

a. Expoaute to known radiation aource *

b. Battery check.

a. Operational check.

b. Verify airflow lndlca~or.

a. Camparlaon of two wide and two narrow range independent level reading*.

b.

IC.town differential preaaure applied to sensor.

c. Slpual to ileter relay adjusted with test device.

4-10 Amendment No. t1, JI,* tt,,.+Mr Ne\\emher 1§ 1 1911

TABLE 4.21.1 (Continued)

ALTERNATE SHUTDOWN MONITORING INSrRUMENTATION SURVEILLANCE REQUIREMENTS

7.

8.

Channel P.escription

'Sov.. ~e...

Sta£teu:p Rang~, ~~JlH'9'1.Monitor (N 66 lA)

( IY:Z-J/3 <:!..)

Auxiliary Fee~wa~er Low Suction Pressure Switch

. (PS-0741D)

9.

SIRW Tank Level Indication (LI.,-03328)

10. Auxiliary Feedwater Flow Rate(2)

Indication (FI-.07278)

(fl-07498)

~l. Auxiliary Feedwater Flow Control(3)

V~lves (CV-0727 & CV-0749) 12 *. Auxiliary Feedwater Pump Inlet St~am Valve (CV-05228)

NOTES:

Surveillance Function

a.

Test

a.

Calibrat.e

a.

Check(l)

b.

Calibrate

a.

Calibrate

a.

Check

a.

Check Frequency Prior to startup(4)

Refueling cycle Quarterly Refueling cycle Refueling cycle Refueling cycle

• Refueling cycle

{l)Quarterly checks are not required when the plant is less than 325°F.

(2)Satisfies Table 4.1. 3-15 Requirement.

(3)See Specification 4.9b.

(4)Prior to each startup, if not done previous week..

(Next page is 4-90) 4-88 TSP1185-0335-NL04 Surveillance Method

a.

Internal test signal (f/+/W4dv~~ 706/"'

~1. 3,. rr~1. 1,)

a.

Apply known pressure to pressure sensor

a.

Compare independent level readings

b.

Apply known differential pressure to level sens~r

a.

a.

a.

Apply known differential pressure to sensor(s)

Verify Control Verify Control Amendment No. SJ.~

May 19, 1989

• -~*

I I

I 'e

• ~ I' 5.3 NUCLEAR STEAK SUPPLY SYSTEM (NSSS)

(Continued) 5.3.2 5.3.3 Reactor Core and Control

a.

Th* reactor core shall appro~imate a right circular cylinder with an equivalent diameter of about 136 inches and an active

• height of about 132 inchea.

b.

The reactor core shall consist of approximately 43,000 Zircaloy-4 clad fuel rode containing slightly enriched uranium in the form of sintered UO pellets. The fuel rode shall be grouped into 204 aasembliel.

A core plug or plugs may be used to replace one or more fuel assemblies subject to the analysis of the reaulting power distribution.

c.

The fully loaded core shall contain approximately 211,000 pounds uo2 and approximately 56,000 pounds of Zircaloy-4.

Poison may be placed in the fuel bundles for long-term reactivity control.

qJ>s""~

d.

The core excess reactiv shall be controlled by a*combination of boric acid.chemic shim, cruciform control rod*, and mechanically fixed rods where required.

Forty-five

_ I control rods shall be distributed throughout the cote as shown in Figure 3-5 of the FSAR.

Four of these control rods may consist of part-length absorbers.

Emergency Core Cooling System An emergency core cooling system shall be installed consisting of

'various subsystem.8 each with internal redundancy.

These subsystems shall include four safety injection tanks, two high-pressure and two

~

low-pressure safety injection pumps, a safety injection and refueling water storage tank, and interconnecting piping as shown in Section 6 of the FSAR.

5-3 Amendment Mo If,.W

'*** l8u 198' TSP0887-0121-ML04