Text

Proposed Tech Spec 3.1 Re Primary Coolant Sys & Table 4.1.3 Re Min Frequencies for Checks,Calibrs & Testing of Miscellanious Instrumentation & Controls
	ML18051A754
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Site:	Palisades
Issue date:	12/13/1983
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
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CONSUMERS POWER COMPANY PALISADES PLANT - DOCKET 50-255 - LICENSE DPR-20 PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST PROPOSED PAGES 8312190105 83121 3 1 /

PDR ADOCK 05000255 p

PDR

_," __ /

7 Pages 0Cll83-0010A-NL02

SECTION 1.1 1.2 1.3 1.4 2.0 2.1 2.2 2.3 3.0 3.1 3.1.1 3.1. 2 3.1.3 3.1.4

3. 1. 5 3.1.6 3.1. 7 3.1. 8

3. L9 3.1.10 3.2 3.3 3.4 3.5 3.6

-3. 7 3.8 3.9 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 3.11 3.11.1 3.11.2 3.12 3.13 OC1183-0009A-NL02 PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE.OF CONTENTS - APPENDIX A.

DESCRIPTION DEFINITIONS Reactor Operating Conditions Protective Systems Instrumentation Surveillance Miscellaneous Definitions PAGE NO 1-1 1-1 1-3 1-3 1-4 SAFETY LIMITS A1'D LIMITING SAFETY SYSTEM SETTINGS 2-1 Safety Limits - Reactor Core Safety Limits - Primary Coolant System Pressure Limiting 'safety System Settings - Reactor Protective System LIMITING CO:t-.'DITIONS "FOR 'OPERATION Primary Coolant System Operable Components Beatup and Cooldown Rate Minimum Conditions for Criticality Maximum Primary Coolant Radioactivity

Primary Coolant System Leakage Limits Maximum Primary Coolant Oxygen and Halogens Concentrations Primary and Secondary Safety Valves Overpressure Protection Systems Proposed Leakage Detection Systems

Chemical and Volume Control System Emergency Core Cooling System Contaiment Cooling

Steam and Feed-Water Systems Containment System Electrical Systems Refueling.Operations Effluent Release Control Rods & Power Distribution Limits Shutdown Margin Requirements Individual Rod Worth Part-Length Control Rods Misaligned or Inoperable Control Rod or Part-Length Rod Regulating Group Insertion Limits Shutdown Rod Limits Low Power Physics Testing Center Control Rod Misalignment Power Distribution Instruments Incore Detectors Excore Power Distribution Monitoring System Moderator Temperature Coefficient of Reactivity Containment Building and Fuel Storage.

Building Cranes 2-1

. 2-3 2-4 3-1 3-1 3-1 3-4 3-15 3-17 3-20 3-23 3-25 3-25a 8/30/82 3-25c 3-2(;

3-29 3-34 3-38 3-40 3-41 3-46 3-50 3-58 3-58 3-58 3-58 3-60 3-60 3-61 3-61

. 3-61 3-65 3-65 3-66a 3-67 3-69 PROPOSED

3.1 PRIMARY COOLANT SYSTEM (Continued) 3.1.10 Leakage Detection Systems Basis S~ecifications

a.

The following primary coolant system leakage detection systems shall be OPERABLE, except as specified in part (b) below, whenever the reactor is in a HOT SHUTDOWN, HOT STANDBY, or POWER OPERATION condition:

1.

A containment atmosphere monitoring system detecting gaseous radioactivity.

2.

A containment atmosphere monitoring system detecting humidity.

3.

A containment sump water level monitoring system.

4.

A containment air cooler condensate flow system.

b.

Operations may continue for a period up to 30 days provided:

1.

At least two of the four systems of part (a) are OPERABLE, and

2.

Grab samples of the containment atmosphere are.obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in the event that both of the containment atmosphere monitoring systems (gaseous and humidity) are INOPERABLE.

c. If less than two systems of part.(a) are OPERABLE the reactor must be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

By maintaining the availability of the primary coolant system leakage detection systems in accordance with parts a, b and c above, in addition to the daily primary coolant system leakage inventory calculation, adequate leakage detection is assured at all times.

The leakage detection systems given in part a, of the above specifications, have a sensitivity. sufficient to detect leakage that is within the requirements of Section 3.1.5 Primary Coolant System Leakage Limits.

References (1) Regulatory Guide 1.45 (2) NUREG-0820, October 1982 Section 4.15.2 (3) NRC letter dated June 22, 1983 3-25b TS1083-0002A-NL02 PROPOSED

TABLE 4.*l.3 Minimum Frequencies for Checks, Calibrations, and Testing of Miscellanous instrumentation and Controls

1.

2.

3.

4.

Surveillance Channel Description Start-up Range Neutron Monitors Primary Rod Position Indication System Secondary Rod Position Indication System Area Monitor.a

a. Containment High-Range Monitors

{RIA-2321 and 2322)

b. Containment Isola-tion Monitors (RIA-

18'05' 1806, 1807 and 1808)

TS1183-0001A-NL02 Function Frequency

a.

Check S.

b.

Test p

a.

Check S(S)

b.

Check M(S)

c. Calibrate/Check(l) RC

a.

Check

b.

Check

c.

Calibrate/Check(l) RC

a.

Check s

b.

Calibrate R

. c.

Test M

a.

Check s

b.

Calibrate RC 4-10 s*urveillance Method

a.

Comparison of both channel count rat el Indications when in service.

b.

Internal test signals.

a.

b.

Comparison of output data with secondary RPIS.

Check of power dependent insert.ion limits monitoring system.

c.

Physicaily 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.

b.

c.

a.

b.

Comparison of two independent monitor readings relative to expected response ratios.

Calibration by electronic signal substitution for ranges above 10 R/hr.

One-point exposure to a krtown radiation source below 10 R/hr.

Internal Test Signal.

Normal readings observed and Iriternal Test Signals used to verify Instrument operation.

Calibration by electronic signal substitution for ranges above

1 I

10 R/hr. One-point exposure to a known radiation source below 10 R/hr. i ProJ.

5/14/80 Proposed 11/5/82

TABLE 4.1.3 (Continued)

Minimum Frequencies for Checks, Calibrations, and Testing of Miscellanous Instrumentation and Controls Surveillance Channel Description

4.

Area Monitors (Continued).

5.

6.

7.

8.

b. (continued)

c. Spent Fuel Pool Criticality Monitors (RIA-2313 and 5709)

This item deleted.

Environmental Honitors Pressurizer Level Instruments Control Rod Drive System.Interlocks TS1183-0001A-NL02 (1)

Function

c.

Test

d.

Test

a.

Check

b.

Calibrate

c.

Test

a.

check

b.

Calibrate

a.

Check

b.

Calibrate

c.

Test

a.

Test

b.

Test Frequency M

RC s

R M

M A

s<5)

RC M(S).

RC p

4-11

c.

d.

a.

b.

c.

a.

b.

a.

b.

c.

a.

Surveillance Method Dector exposed to radiation check so~rce~

Simulation of CHR 2/4 Logic trip wit~

Proposed test switch to verify actuation relaYis, 11/5/82 including containment isolation *.

Normal readings observed and Internal test signals used to verify instrument o~eratioh..

1 Exposurt:! to known external radiation :

sources, Exposure to a radioactive source or :

confirm~tion of a significant instrument reading above natural background by '

radiation field measurement is used to verify instrumentation operation.

Operational check.

Verify airflow indicator.

Conipar::i..son of six independent level readings.

Krtown differential pressure applied to sensor.

Signal to meter relay adjusted with test device.

Verify proper operation of all rod dr::i..ve control system interlocks, using simulated signals where necessary.

I Proposed 6/25/82

~

Proposed 5/14/80 I

b.

Same as 8(a) above, if not done within three months.

TABLE 4.1.3 (Continued)

Minimum Frequencies for Checks, Calibrat;:ions, and Testing of Miscellanous Instrumentation and Controls Surveillance Channel Description Function

9.

Flux-fl T Power Comparator a.

Calibrate

b.

Test

10.

Calorimetric

a.

Calibrate <2 Instrumentation

11.

Containment Building Humidity Detectors

12.

Interlocks - Isolation Valves on Shutdown Cooling Line

13.

Service Water Break Detector.in Containment

14.

Control Room Ventilation

15.

Auxiliary Feed Pump Flow Indication

16.

Auxiliary Feed Pump Auto Initiation

17.

Power-Operated Relief Valves and Pressurizer Code Safety Relief Valves Postion Indication

a.

Temperature TS1183-0001A-NL02

a.

Test

a.

Calibrate

a.

Test

a.

Test

b.

Test

a.

Check

b.

Calibrate

a.

b.

Test Calibration

a.

Calibrate

b.

Check Frequency R(S)'

M RC RC RC RC R

R M(3)(5)

R R

s

4-lla Surveillance Method

a.

Use simulated signals.

b.

Internal test signal.

a.

Known differential pressure applied to feed-water flow sensors.

a.

Expose sensor to high humidity.

atmosphere.

a~

Known pressure applied to sensor.

a.

Known differential pressure applied to sensors.

a.

Check da~per operation for DBA 111ode with HS-1801 and isol~tion signal.

b.

Check cotitrol room for positive pressure.

a.

Comparison of Channels.

b.

Known Differential Pressure Applied to senstfrs.

a.

b.

Internal Test Signal.

Know Differential Pressure Applied to sensors.

a.

Known Resistance Substitute for RID '

b.

Comparison of Channels

TABLE 4.1.3 (Continued)

Minimum Frequencies for Checks, Calibrations, and Testing of Miscellanous Instrumentation and Controls S.urveillance Channel Description Function

17.

(Continued) b~ Acoustic.Monitor

a.

Calibrate

18.

Subcooling Margin Monitor

a.

b.

Check Calibrate

19.

20.

21.

22.

23.

Containment Spray

a.

Check Header Level

b.

Calibrate Containment Pressure

a.

Check Wide Range

b.

Caiibrate Containment Sump

a.

Check Water Level Instrument

b.

Calibrate Containment Floor

a.

Check Water Level Instrument

b.

Calibrate Process Monitors a*. Applies to:

Steam Generators Blow-

a.

Check down Monitor (RIA-0707),

Waste Gas Monitor (RIA-1113), Radwaste Dis-

b.

Calibrate charge Monitor (RIA-1049), Turbine Build-

c.

Test ing Sump Monitor (RIA-5211 )~ Steam Generators Blowndown Tank Vent (RIA-2320) and Engineered Safe-guards Rooms Ventilation Monitor (RIA-1810 and 1811)

TS1183-0001A-NL02 Frequency R

s RC w

R s

R D

R M

4-llb Surveillance Method

a.

Inject Calibrated Test Signal.

a.

Comparison of Channels.

b.

Known Resistance Substituted for RID Coincu1nt with Known Pressure Input

a.

Normal Readings Observed.

b.

Known Pressure Applied to Sensor.

a.

Comparisbn of Channels.

b.

Known Pressure Applied to Sensors.

a.

Co~pari~~n rif Channels.

b.

Known Differential Pressure Applied to Sensors.

a.

Comparison of Channels.

b.

Known Level Applied to Transducer.

a.

Normal readings observed and Internal Test Signals used to verify instrument operatioh.

b.

Exposure to known external radiation source.

c.

Exposure to a radioactive source or 1

confirmation of a significant instrument reading above natural background by radiation field measurement is use.cl to verify instrument operation.

Proposed 14/80 Proposed 6/25/82 Propo::icd 11/5/82

TABLE l1.1. 3

( Continued)

Minimum Frequencies for Checks, Calibrations, and Testing of Miscellanous Instrumentation and Controls Surveillance Channel Description Function Frequency

, I Surveillance Method

23.

Process Monitors (Continued)

b. Applies to:

I Particulate Stack

a.

Check s

a.*

Normal readings observed and internal Monitor (RIA-2325),

test signals used to verify instrumept Normal Range Noble operation.

I Gas Stack Monitor

b.

Calibrate R

b.

Exposure* to a known radiation source.*

(RIA-2326), High-Calibratibn need not cover entire Range Noble Gas range of tnonitor due to the personnel Stack Monitor (RIA-exposure hazard of high-range 2327) and Main Steam calibrations.

Safety and Dump Valve

c.

Test M

c.

Exposure to a radioactive source or Discharge Monitor confirmation of a significant (RIA-2323 and 2324) instrumerit reading above natural fie~d measuremetit is used to verify instrument I

operation.

24.

Containment Hydrogen

a.

Check D

a.

Visual observation of control room Monitor (C161 and Cl62) panels for expected indications.

b.

Calibrate RC

b.

Calibration to a known hyrodgen gas-. :

Gas sampie between 0 and 10 volume percent.

25.

Condensate Flow

a.

Test R

a.

Move* float and verify control from Air Coolers Room Alarm I

NOTES:

(1)

Criticality monitors for fuel handling in the containment building are calibrated and routine checks of their operability are controlled by refueling procedures.

(2)

Deleted.

(3)

(4)

(5)

Test method to be alternated to include starting auxiliary f eedwater pump from the control room from 'the control room hand switch, from the breaker and from the automatic start in a three-month period.

In conjunction with Item 4(b), Table 4.1.1 *.

It is not necessary to perform the specified testing during prolonged periods in the cold shutdown o~

refueling conditions.

If this occurs, omitted testing will be performed prior to returning the plan~

to service.

4-llc PROPOSED 11/5/82 PROPOSED

ML18051A754

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