ML20098F180

Proposed Tech Specs Addressing Concerns Re Installation of New Equipment Per Generic Ltr 83-36 & NUREG-0737,Items II.B.1,II.B.3,II.F.1.1,II.F.1.2,II.F.1.3,II.F.1.4,II.F.1.5, II.F.1.6 & III.D.3.4

ML20098F180
Person / Time
Site:	Quad Cities
Issue date:	09/26/1984
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20098F172	List: ML20098F171 ML20098F180
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.3, TASK-2.F.1, TASK-3.D.3.4, TASK-TM GL-83-36, NUDOCS 8410020429
Download: ML20098F180 (40)

Text

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DPR-29 t

3.

The MCPR Limiting Conditioning for Operation (LCO) will be increased 0.03 to 1.38 for 7 x 7 and 8 x 8 fuel (T.S.

i, 3. 5. K) 4.

'The Minimum Average Planar Linear Heat Generation Rate (MAPLHGR) limits will;be reduced by 0.7 for all fuel types.

(T.S. reference 3.5.I) 5.

The APRM Scram and Rod Block Setpoints and the RBM Setpoints shall be reduced by-3.5% to read as follows:

T.S. 2.1.A.I Si. 58 WD + 58.5 T.S. 2.1.A.1*-

S.L(.58 WD + 58.5) FRP/MFLPD T.S. 2.1.B SL.58 WD + 46.5 T.S. 2.1.B*

Si. (.58 WD + 46.5) FRP/MFLPD T.S. 3.2.C.

(TABLE 3.2.3) :

APRM Upscalef._(.58 WD + 46.5) FRP/MFLPD RBM Upscale $__.65 WD + 38.5 6.

The suction valve in the idle loop is closed and electrically isolated until the idle loop is being prepared for return to service.

7.

APRM flux noise will be measured once per shift and the recirculation pump speed will be reduced if the flux noise averaged over 1/2 hour exceeds 5% peak to peak, as measured on the APRM chart recorder.

8.

The core plate delta p noise will be measured once per shift and recirculation pump speed will be reduced if the noise exceeds 1 psi peak to peak.

6

• In the event that MFLPD exceeds FRP.

L.

Post-Accident Sampling A program will be established, implemented, and maintained which will ensure the capability to obtain and analy=e reactor coolant, radioactive iodines and particulates in plant chimney effluents, and containmene atmosphere samples under accident conditions.

The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

4.

This license is effective as of the date of issuance, and shall expire at midnight, February 15, 2007.

Date of Issuance: December 14, 1972 9410020429 840926 PDR ADOCK 05000254 P

pg

r QUAD CITIES OPR-29

-TABLE OF' CONTENTS (Cont'd)

Page 13.5/4.5.. CORE CONTAINMENT COOLING SYSTEMS 3.5/4.5-1

'A.

Core Spray Subsystems and the LPCI Mode of the RHR System 3.5/4.5-T B.

Containment Cooling Mode of the RHR Sy:: tem 3.5/4.5-3 3.5/4.5 C.

HPCI Subsystem; D.

Automatic Pressure Relief Subsystems 3.5/4.5 5~

E.

Reactor Core Isolation Cooling Systent 3.5/4. 5 F.

Minimunt Core and Containment Cooling System AvaiTability 3.5/4.5-6 G.

Maintenance of Filled Discharge Pipa 3.5/4.5-T H.

Condensate Pump Room Flood Protection 3.5/4.5-8 I.

Average Planar Linear Heat Generation Rate (APLHGR) 3.5/4.5-9 3.5/4.5-9 J.

Local LHGR K.

Minimum Critical Power Ratio (MCPR) 3.5/4.5-10 3.5/4.5-11 3.5 Limiting Conditions for Operatforr Bases 4.5 Surveillance Requirements Bases 3.5/4.5-16 3.6/456-T 3.6/4.6 PRIMARY. SYSTEM BOUNDARY A.

Thermal Limitations 3.6/4' 6-T B.

Pressurization Temperature 3.6/4.6-1 3.6/4.6-2.

C.

Coolant Chemistry 3.6/4.6-3 D.

Coolant Leakage E.

Safety and Relief Valves 3.6/4.6-4 3.6/4.6 -

F.

Structura1 Integrf ty 3.6/4.6-5 G.

Jet Pumps FTow Mismatch 3.6/4.5 Recirculation Pump (Snubbers) 3.6/4.6-Ea-H.

Shock Suppressors I.

3.6/4.5-8 3.6' Limiting Conditions for 0peration Baser 3.7/4.T-1 3.7/4.7 CONTAINMENT SYSTEMS 3.7/4.T-T A.

Primary Containment 3.7/4.T-T B.

Standby Gas Treatment System 3'.7/4.T-8 C.

Secondary Containment 3.7/4.7-9 D.

Primary Containment Isolation Valves 3.7/4.T-li 3.T~ Limiting Conditions for Operation Bases 3.7/4.T-15 4.T Surveillanca Requirements Bases 3.8/4.8-1 3.8/4.8 RADI0 ACTIVE EFFLUENT 5' 3.8/4.8-T A. Gaseous Effluents.

3.8/4.8-6a.

B.

Liquid Effluents 3.8/4.8-9 C. Mechanical Vacuum Pumpt 3.8/4.8-10; 0.

Environmental Monitoring Progran J.8/4~.8 E.

Solid Radioactive-Waste 3'.8/4.8 F. Miscellaneous. Radioactive. Matertalr. Sources.

^

3.8/4.8-14a

-H.-Controi-Rovm Emergefid?Mltration System 3;8/4.8Ai Limiting Conditions for Operation and Surveillance 3.8/4,8-15 Req. Bases A

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QGAD-CITIES

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J DPR-29

F.

Control Room Ventilation System F~

Control Room Ventilation System

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I D

Isolation Isolation 1.

The control room ventilation systems 1.

Surveillance for instrumen-are isolated from outside air on a tation which initiates signal of high drywell pressure, low isolation of control room water level, high main stream-ventilation shall be as line flov high' toxic gas concentration, specified in Table 4.2-1.

y high radiation in either of the. reactor

. building ventilation exhaust ducts, or manually. Limiting conditions for-cperation shall be as indicated in Table '.2-1 and Specifications 3.2.H..

and 3.0.I.2.

2.

The toxic gas detection instrumentation 2.

Manual isolation of the control shall consist of a chlorine, amannia, room ventilation systems shall and sulphur dioxide analyzer with each be de onstrated once every trip setpoint set at:

refueling outage.

a.

Chlorine concentration j,5 ppm.

b.

Ammonia concentration j_50 ppm.

c.

Sulphur dioxide concentration _<_

3 ppm.

The provisions of Specification 3.0. A.

_ g are not applicable.

- V C.

Radioactive Liquid Effluent Instrumentation G.

Radioactive Liquid Effluent Instrumentation The effluent monitoring instrumentation shown in Table 3.2-5 shall be operable with Each radioactive liquid effluent alarm setpoints set to ensure that the monitoring instrument shown in limits of Specification 3.8.B. are not Table 4.2-3 shall be demonstrated exceeded. The alarm setpoints shall be operable by performance of the determined in accordance with the ODCM.

given source check, instrument check, calibration, and functional test operations at the frequencica shown in Table 4.2-3.

1.

With a radioactive liquid effluent monitoring instrument alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpcint so it is acceptably conservative.

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QUAD-CITIES DPR-2 9 2.

With one or more radioactive liquid

'f.

effluent monitoring instruments inoperable, take the action shown in Table 3.2-5.

Exert best efforts to return the inst;ument to operable status within 30 days and, if un-successful, explain in the next Semi-Annual Radioactive, Effluent Release--

Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER.

3.

In the event a lLatting condition for operation and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, provide a 30-day written report to the NRC, and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.

H.

Radioactive Gaseous Effluent H.

Radioactive Gaseous Effluent Instruaentation Instru=entation 0,

The effluent monitoring instrumentation Each radioactive gaseous radiation shown in Table 3.2-6 shall be operable with monitoring instrument in Table 4.2-4 alarm / trip setpoints set to ensure that the shall be demonstrated operable by limits of Specification 3.8.A. are not performance of the given source check, exceeded. The alarm / trip setpoints shall instrument check, calibration, and be determined in accordance with the ODCf.

functional test operations at the frequency shown in Table 4.2-4.

1.

With a radioactive gaseous effluent monitoring instrument alarm /ttip setpoint less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected instrument, or declare the instru-ment inoperable, or change the set-

. point so it is acceptably conservative.

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QUAD-CITIES-.

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• l.

.9 2.

With one or more radioactive gaseous effluent monitoring instruments inoperable, take the action shown in Table 3.2-6.

Exert

..we efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoperability was not correctad in 'a timely manner.

This is.in lieu of an LER.

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3.

In the. event a limiting condition for operation'and ascociated action requirements cannot be gatisfied because of circumste. aces in excess of those addressed in the specifica-tions, provide a 30-day written report I

to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.

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QUAD-CITIES DPR-2 9_

ro that none of the activity released during the refueling accident leaves the reactor fsg

- building via the normal ventilation stack but that all the activity is processed by the standby gas treatment system.

The instrumentation which is provided to monitor the postaccident condition is listed in Table 3.2-4.

The instrumentation listed and the limiting conditions for operation on thase systems ensure adequate monitoring of the containment following a loss-of-coolant accident. Information from this instrumentation will provide the operator with a detailed knowledge of the conditions resulting from the accident; based on this infor-nation he can make logical decisions egarding postaccident recovery.

The specifications allow for postaccident instrumentation to be out of service for a p;riod of 7 days. This period is based on the fact thht several diverse instruments are available for guiding the operator should an accident occur, on the low probability of an instrument being out of service and an accident occurring in the 7-day period, cad on engineering judgment.

l The normal supply of air for the control room ventilation system Trains "A" and "B" cutside the service building. In the event of an accident, this source of air may be rrquired to be shut sown to prevent high doses of radiation in the control room. Rather than provide this isolation function on a radiation monitor installed in the intake cir duct, signals which indicate an accident, i.e.,

high drywell pressure, low water 1svel, main streamline h.gh flow, or high radiation in the reactor building ventilation duct, will cause isolation of the intake air to the control room. The above trip signals result in im=ediate isolation of the control room ventilation system and thus minimize any radiation dose. Manual isolation capability is also provided.

Isolation

/~% from high toxic chemical concentration has been added as a result of the " Control Room U abitability Study" submitted to the NRC in December 1981 in response to NUREG-0737 H

Item III D.3.4.

As explained in Section 3 of this study, ammonia, chlorine, and sulphur dioxide detection capability has been provided. The setpoints chosen for the control room ventilation isolation are based on early detection in the outside air supply at the odor threshold, so that the toxic chemical will not achieve toxicity limit con-ccntrations in the Control Room.

ThJ radioactive liquid and gaseous effluent instrumentation is provided to monitor the ralease of radiqactive materials in liquid and gaseous effluents during releases. The clarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of 10 CFR 20.

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QUAD-CITIES; DPR"29 TABLE 3.2-4 POSTACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS (2)

Iastrument Minimum Number Readout of Operable location Number Z

Channels (1)(3).

Parameter Unit 1 Provided Range 1

Reactor pressure 901-5 1

0-1500 psig 1

0-1200 psig 1.

P.eactor water level 901-3 1

-243 inches +57 inches 1

Torus water temperature 901-21 2

0-200*F 1

Torus air temperature 901-21 2

0-600*F t

Torus water level indicator 901-3

'l

-5 inches -- +5 inches (narrow range)'

'2(a)

Torus water level indicator 901-3 2

0-30 feet (wide range)

Torus water level sight glass 1

18 inch range (narrow range)

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1 Torus pressure 901-3 1

-5 inches Hg to 5 psig 901-3 1

-5 inches Hg to 5 psig 2

Drywell pressure 0 to 75 psig 2

0 to 250 psig 2

Drywell temperature 901-21 6

0-600*F 8

2 Neutron monitoring 901-5 4

0.1-10 CPS 2(4)

Torus to drywell 2

0-3 paid

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differential pressure 1(s)

Drywell Hydrogen concentration 901-55,56 2

0-4%

l 2(7)

Drywell radiation monitor 901-55,56 2

1.to 10s R/hr l

Main steam RV 901-21 1 per NA position, acoustic valve monitor 2/ valve (s)

Main steam RV 901-2'1' 1 per 0-600*F '

position, valve temperature monitor Main steam SV 901-21 1 per NA,

l-position, acoustic valve monitor 2/ valve (s) g,ta.,tes,sy 901-21 1 per IO-600*F

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QUAD-CITIES DPR-29 Notes 11 Instrument. channels required during power operation to monitor.postaccident

.25-conditions.

2.

Pr'ovisions are made for local sampling and monitoring of drywell atmosphere.

i 3.

In the event iny of the instrumentation becomes inoperable for more than 7 days. during reactor operation, initiate an orderly-sktdown and be in the f

cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. See notes 4, 5, 6, 7, and 8 for exceptions to this requirement.

4.

From and af ter the date that one of these paraneters is reduced to one indication, continued operation is not permissible beyond thirty days unless such instrumentation is sooner made operable. In the event that all indication of these' parameters is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in twenty-four (24) hours.

5.

If the number of position-indicators is reduced to one indication on one or L

more valves, continued operation is permissible; however, if the reactor is in a cold shutdown condition for longer than"12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, it may not be started l

2 up until all position indication is restored.

In the event that all position indication is lost on one or more valves and such indication cannot be restored in 30 days, an orderly shutdown shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6.

From and af ter the date that this parameter is reduced to either one narrow-range indication or one wide-range indication, continued reactor operation is not permissible beyond 30 days unless such instrument is sooner made operable.

In the event that either all narrow-range indication or all vide-range indication is disabled, continued reactor operation is not permis-sible beyond 7 days unless such instruments are sooner made operable.

In the event that all indication for this parameter is disabled, and such indication cannot be ' restored in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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7. - With less than the minimum number of operable channels, initiate the d

pre-planned alternate method of monitoring this parameter within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

a.- eitter restore the inoperable channel (s) to operable status within 7 dayi of the event, or-b.

prepare and submit a special report to the NRC within 30 days following the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.

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8. - From and af ter the date that one of the drywell hydrogen monitors becomes inoperable, contintied reactor operation is permissible, a.

If both dryvell hydrogen monitors are inoperable, continued reactor cperation is permissible for up to 30 days provided that during this time the HRSS hydrogen monitoring capability for the drywell is operable.

b..

-If all drywell hydrogen monitoring capability is lost, continued reactor operation is permissible for up to 7 days.

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m QUAO-CITIES ORR'-27 Table 3.2-$

RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ttin imunr uo.

of Operable To ta l No.

Channels of Channels-Parameter Action (1) 1 1

Service Vater A,

Effluent Gross Activity Monitor I

1 Liquid Radwaste C

Effluent Flow Rata Monitor i

I Liquid Radw'aste 8

Effluent Gross Activity Monitor

/

Notes:

Action A:

With less than the minimum number of coerable channels, releases via this pathway may cor tinue, provided that at least ence per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples' are collected and analy:ed for beta or gamma activity at an LLD of less than or equal to 10~7 uCi/ml.

Action 3:

With less than the minimum number of ooerable channels, ef fluent releases via this pathway may continue, provided that prior to initiating a release, at least.2 Independent samples are analyzed in accordance with Speci fication 4.8.S. I., and at feast 2 members of the facility staff independently verify the-release calculation and discharge valving. Otherwise, suspend release'er radioactive efflu-ents via this pathway.

Acti on-C:

With-less than the minimum nu=her of ocerable channels, releases via this pathway r.ay continue, provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Fuma curves may be utilized to estimate flow.

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Table 3.2-6~

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

• Minimus No.

of Operable Total No.

Channels (1) of Channels Parameter Action (2)

~ 1.

2-SJAE Radiation D

Monitors 1.

2 Main Chimney Noble A

Gas Activity Monitor I

-1 1

Main Chimney' Iodine C'

Sampler

'L 1

Main Chimney C

Particulate Sampler 1

1 Reactor Bldg. Vcnt B

Sampler Flow Rate Monitor 1

1 Reactor Bldg. Vent C

Iodine Sampler 1

1 Reactor Bldg. Vent C

Particulate Sampler 1

1 Main Chimney Sampler B

Flow Rate Monitor 1

1 Main Chimney Flow B

Rate Monitor P

N, 1

2 Reactor Bldg. Vent E

Noble Gas Monitor 1

1 Main Chimney High Range Noble Gas Monitor

' Notes (1)

For SJAE monitors, applicable during SJAE operation. For other Instrumentation, applicable at all times.

(2) Action As With the number of operable channels less than the minimum requirement, effluent releases via this pathway may continue, l.

Provided grab samples are taken at least once per 8 houc shif t and these samples are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i Action B: With the number of operable channels less than tho' minimum required, effluent' releases via this pathway may continue i

provided that the flow rate is estimated at-least once 'per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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QUAD-CITIES, DPR-29 Action C: With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are cont.inuously collected with auxiliary sampling equipment, as required in Table 4.8-1.

Action D:- With;less'than the minimuw channels. operable, gases-from-the main condenser off gas system may be released to the environment; for up to 72~ hours provided at least-one chimney, monitor is operable; otherwise, be in hot stand-by in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Actiorras With less*,than the minimur enannels operable,.immediately suspend release of radioactive effluents via this pathway.

Action F: With less than the minimum channels operable, initiate the preplanned alte' enate method of monitoring the appropriate parameter (s)- within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and (1) either restore the inoperable channel (s) to operable status within 7 days of the event, or (2) prepare and submit a Special Report to the Commission within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

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QUAD-CITIES DPR-29 TABLE 4.2-1 (Cont'd)

,,s Instrument Ins trumant Funcqional Instryment Channel Test-Calibration,-

Check-HPCI Isolation l'.

Steamline high flou

(.1) (9)

Once/3 months Noner.

l 2.

Steamline area high temperature Refueling outage Refueling outage None 3.

Low reactor' pressure (1)

Once/3 months None Reactor Building Ventilation System Isolation And Standby Treatment System Initiation 1.

Refueling floor radiation mon:.cors (.1)

Once/3 months Onca/ day Control Room Ventilation System Inolation 1.

Reactor low water level (1)

Once/3 months once/ day 2.

Drywell high pcessure (1)

Once/3 months None 3.

Main steamline high flow (1)

Once/3 months Once/ day 4.

Toxic gas analyzers (chlorine.

Once/ month One/18 months Once/ day I

ammonia,. sulphur dioxide)

Notes:

5 1.

Initially once per month until exposure hours (M as defined on Figure 4.1-1) are 2.0 X 10,

thereaf ter, according to Figtre 4.1-1 with an interval not less than 1 month nor more than 3 months. The compilation of instrument failure rate data may include data obtained from

()

other boiling water reactors for which the same design instrument operates in an environ-ment similar to that of Quad-Cities Units 1 and 2.

2.

Functional tests, calibrations, and instrument checks are not requited when these instruments are not required to be operable or are tripped.

3.

This instrumentation is excepted from the functional test definition. The functional test nhall consist of injecting a simulated electrical signal into the measurement channel.

4 This Lastrument channel is excepted from the functional test definitions and shall be calibrated using simulated t.lectrical signals once every 3 months.

5.

Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calitirations shall be performed during controlled shutdowns with a required. frequency not to exceed once per week.

6.

The positioning mechanism shall be calibrated overy refueling outago.

7.

Logic system functional tests are performed as specified in the applicable section for these systems.

8.

Functional test shall include verification or operation of the degraded voltage 5-minute timer and 7 second inherent timer.

9.

Verification of the time delay setting of 3 < + < 10 seconds snall be perfor=ed during each refueling outage.

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QUAD-CITIES DPR 729 TABLE 4.2-2 POSTACCIDENT MONITORING INSTRUMENTATION SURVEILIANCE REQUIREMENTS Ins trument Minimum Number Readout cf Operable Incation

~Ch'unels*

Parameter-Unit 1 Calibration Instrument Check

~

1 Reactor pressure-90 1-5 Once every Once.per day 3 months L

Reactor water-level 901-3 Once every-Once per. day 3 months-1 Torus water temperature 901-21 Once every once per day 3 months 1

Torus air temperature 901-21 Once every Once per day 3 months Torus water level indicator 901-3 Once every once per day (narrow range) 3 months 2

Torus water level indicator 90 1-3 Once every once 'per 31 days (vide range) 18 months Torus water level sight glass N/A None 1

Torus pressure 90 1-3 Once every Once per day 3 months 2

Drywell pressure 901-3 Once every Once /per day 3 months

~

2 Dryvell temperature 901-21 Once every once per day 3 months

, 2 Neutron monitoring 90 1-5 Once every Once per day 3 months 2

Torus to drywell Once every Nona differential pressure 6 months 1

Drywell Hydrogen concentration 901-55,56 Once every once per 31 days 4

3 months

-2' Drywell radiatiotr monitor' 901-55,56 Once every***- Once pee-31 days 18 months Main steam RV 901-21 Once per position, acoustic 31 days monitor 2/vcive Main steam RV 901-21 Once every once per

position, 18 months, 31 days I

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QUAD-CITIES D?R-29 Ins trinnent Minimum. Number-EeM oot cf Operable tocation Ch~nnels*

Parameter Unit 1 Calibration Instrument Check Main steam SV 901-21 Once per position, acoustic 31 days monitor

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2/vnive.

Main. steam ST 901-21 Once every once. per

position, 18 months 31 days tempe rature monitor

• Instrisment channels required during power operation to monit r postaccident conditions.

o

• • Functional tests will be conducted before startup at the end of each refueling outage or after maintenance is performed on a particular safety or relief valve.

• • • Calibration shall consist of an electronic calibration of the channel, not-including the detector, for range decades above 10 R/hr; and a one-point calibration check of the detector below 10 R/hr with an installed or portable gamma source.

-d 3.2/4.2-184.

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QUAD CITIES DPR-29 TABLE 4.2-3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Functional Source Instrument Check (1)

Calibration (1)(3) Test (1)(2) Check (1)

Liquid Radwaste D

R Q (7)

(6)

Effluent Gross Activity Monitor S:rvice Water D

R Q (7)

R Effluent Gross Activity Monitor Liquid Radwaste (4)

R NA NA Effluent Flow Rate M:nitor N9tes:

(1) D = once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = once per 31 days Q = once per 92 days R = once per 18 months S = once per 6 months (2) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.

a. Instrument indicates levels above the alarm setpoint.

b. Circuit failure.

c. Instrument indicates a downscale failure

d. Instrument controls not set in OPERATE mode.

3) Calibration shall include performance of a functional test.

4) Instrument Check to verify flow during periods of release.

5) Callabration shall include performance of a source check.

6) Source check shall consist of observing instrument responso during a discharge.

7) Functional test may be performed by using trip check and test circuitry associated with the monitor chassis.

3.2/4.2-19

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QUAD-CITIES DPR-29 Table 4.2;4' RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibra-Functional Source

~ Instrument Mode (2)

Check (1) tion (l) (4)

Tes t (1) ( 3 )

Check (1)

Main Chimney' Noble, Gas

!A D

R-Q:

M-Activity Monitor.

Main Chimney Sampler B

D-R Q(In NA Flow Rate Monitor Reactor Bldg. Vent Sampler B

D R-Q(6)

NA Flow Rate Monitor Main Chimney Flow Rate B

D R

Q NA Monitor Reactor Bldg. Vent B

D R

Q Q

Activity Monitor SJAE Activity Monitor A

D R

Q R

Main Chimney Iodine and B

D(5)

NA NA NA Particulate Sc.apler Reactor Bldg. Vent Iodine B

D(5)

NA NA NA and Particulate Sampler l

Main Chimney High Range B

D(5)

R Q

M Noble Gas Monitor Notes s

(1)

D - once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = once per 31 days Q = once per 92 days r

R = once per 18 months (2). A = during SJAE operation B = at all times (3) The Instrument Functional Tt.st shall also demonstrate that control room alarm' annunciation occurs,.if_ any, of the following conditions. exist,.wiresos applicables a.

Instrument indicates levels above the alarm setpoint b.

Circuit failure c.

Instrument indicates a downscale failure d.

Instrument controls not set in OPERATE mode (4) Calibration shall include performance of a functional test.

(5)

Instrument check to verify operability of the= instrument; that the instrument is in-place and functioning properly.

(6) Functional test shall be performed on local switches providing low flow alarm.

3.2/4.2-20 u

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c QUAD-CITIES DPR j,9 O'.H.

Control Room' Emergency Filtration 11. Control Room Emergency Filtration

~*

System System 1.' The control room emergency 1.

At least once per month, initiate

. filtration system, including at 2000 cfm (110%) flow through the least one booster fan shall be control room emergency filtration operable at all times when system for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with secondary containment

• integrity-i>

the, heaters;operables-required, except as specified in Sections 3.8.II.1.a. and b.

a.

Af ter the control room emergency-filtration system is made or found to be inoperable for any-reason, reactor operation and fuel handling are permissible only-during the succeeding 14 days. tiithin 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following s

the 14 days, the reactor shall be placed in a condition for which the control room emergency filtration system is not required in accordance with Specification 3.7.C.1.a. through d.

b.

Specification 3.8.11.1.a. above O'

does not apply during performance or post-maintenance testing, or during removal of the charcoal test canister.

2.

Periodic Performance Requirements 2.

Performance Requirement Tests a.

The results of the in-place DOP a..

At least once per operating cycle tests at 2000 cfm (110%) on but not to exceed 18 months, or HEPA filters shall show 11%

following painting, fire, or toxic DOP penetration.

chemical release in any ventilation zone communicating.with the intake b.

The results of in-place of the system while the system is halogenated hydrocarbon tests at operating that could contaminate the i

2000 cfa. (1102) on the charcoal

!! EPA filters of charcoal absorbers, banks shall show 11% penetration.

perform the followingt c.

The results of laboratory carbon

1) In-place DOP test the llEPA sample analysis. shall show 2,90%

filter banks; to verify leaktight methyl iodide removal efficiency +

integrity..

when tested at 130 C and 95% R.ll.

2.

In-place test the charcoal absorber banks with halogenated hydrocarbon tracer to verify leaktight integrity, mV 3.8/4.8-14a

_e_.-

- a. -.

QUAD-CITIES DPR,89

3) Remove one carbon test I) canister f rom the charcoal absorber. Subject this sample to a laboratory analysis to verify methyl iodide removal efficiency.

b.. At.leastsonce poc. operating cycle, but nor to exceed 18' months, the following conditions shall be demonstrated:

1) Pressure drop across the combined filters is less than 6 inches of water at 2000 cfm (110%)

flow rate.

2) Operability of inlet heater 0

demonstrates heater AT of 15 F.

3.

Postmaintenance Requirements 3.

Postmaintenance Testing a.

Af ter any maintenance or heating a.

Af ter any maintenance or testing that could af fect the HEPA filter that could affect the leaktight in

O or llEPA filter mounting f rame tegrity of the llEPA filters, perform leak-tight integrity, the results in-placa DOP tests on the !! EPA of tha in-place DOP tests at 2000 filters' in accordance with Specifica-cfm (t10%) on llEPA filters shall tion 3.8.!!.2.4.

ahuw 1 1% DOP penetration.

b.

After any maintenance or testing b.

Af ter any maintenance or testing that could affect the charcoal that could affect the leaktight in-absorber lenktight integrity, the tegrity of the charcoal absorber results of in-place halogenated banks, perform haloganated hydro-hydrocarbon tests at 2000 cfm carbon tests on the charcoal ad-(110%) shall show 11% penetration.

sorbers in accordance with Specif1-cation 3.8.!!.2.b.

W P 3.8/4.8-14b

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• QUAD-CITIES DER-s'T 3.8/4.8.C.

!1ECHANICAL VACUUM PlatP The purpose of isolating the mechanical vacum line is to limit release of cctivity from the main condenser. During an accident, fission products vould be transported from the reactor through the main steamline to the main condenser.

The fission product radioactivity would be sensed by the main steamline radio-activt.::y monitors which initiate isolatiott 3.8/4.8.F.

MISCELI.ANEOUS RADIOACTIVE ttATERIAI.1 SOURCES The objective of this specification is to assure that leakage from byproduct, source and special nuclear material sources does not exceed allowable limits The limitations on removable contamination for sources requiring leak testing..

including alpha emitters, is based on 10 CFR 70.39 (c) limits for plutonium.

3.8/4.8.E.

SOI.ID RADIOACTIVE WASTE The operability of the solid radioactive vaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped off-site. This specification implemeats the requirements cf 10 CFR 50.36a. and General Design criteria 60 of appendix A to 10 CFR Part 50.

3.8/4.8.H CONTR0T. ROOM AIR FILTRATION The purpose of these specifications is to assure availahility of the control Q room emergency air filtrations unit that has been installed in response to NUREG-0737 Ites III D.3.4.

Operation of this unit in described in the " Control Room Itabitability Study" for Quad-Cities Station whie.h was submitted to the NRC in December 1981.

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DPR-30 3.

The MCPR Limiting Conditioning for Operation (LCO) will be increseed 0.03 to 1.38 for 7 x 7 and 8 x 8 fuel (T.S.

i

3. 5. K) 4.

The Minimum Average Planar Linear lleat Generation Rate (MAPL!!CR) limits will be reduced by 0.7 for all fuel types.

(T.S. referenco 3.5.I) 5.

Tbt APRM Scram and Rod Block SotpJints and the RBM Setpoints shall be reduced by 3.5% to read as follows:

T.S. 2.1.A.I Si.58 WD + 58.5 T.S. 2.1.A.1*

Si(.58 WD + 58.5) FRP/MPLPD T.S. 2.1.8 SL.58 WD + 46.5 T.S. 2.1.B*

Si (.58 WD + 46.5) FRP/MFLPD T.S. 3.2.C (TABLE 3.2.3) :

APPM Upecale L(.58 WD & 46.5) FRP/MFLPD RBM Upscale 1. 65 WD + 38.5 6.

The suction valve in the idle loop is closed and electrically isolated until the idle loop is being prepared for return to service.

7.

APRM flux noise will be measured once per shif t and the recirculation pump speed will be reduced if the flux noise averaged over 1/2 houc exceeds $s peak to peak, as measured on the APRM chart recorder.

8.

The core plate delta p noise will be measured once per shift and recirculation pump speed will be reduced if the noise exceeds 1 psi peak to peak.

i

• In the event that MTLPD exceeds FRP.

L.

Post-Accident sampling A program will be established, implemented, and maintained which will ensure the capability to obtain and analyse reactor coolant, radioactive iodines and particulates in plant chimney effluents, and containment atmosphere samples under accident conditions.

The program shall include the followings 1.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

4.

This license is effective as of the date of issuance, and shall expire at midnight, February 15, 2007.

Date of Issuance r December 14, 1972 4

QUAD CITIES DPR.TO TABLE OF CONTENTS (Cont'd)

Page

- 3.5/4.5 CORE CONTAINMENT COOLING-SYSTEMS 3.5/4.5-1 A.

Core Spray Subsystems and the LPCI Mode of the RHR System 3.5/4.5-1 B.

Containment Cooling Mode of the RHR System

- 3.5/4.5-3 C.

HPCI Subsystem

.3.5/4.5-4 D.

Automatic Pressure Relief Subsystems 3.5/4.5-5 E.

Reactor Core Isolation Cooling System

3. 5/4. 5-6~

F.

Minimum Core and Containment Cooling System Availability 3.5/4.5-6

.G.

Maintenance of Filled Discharge Pipe '

3.5/4.5-7 H.

Condensate Pump Room Flood Protection 3.5/4.5-8 I.

Average Planar Linear Heat Generation Rate (APLHGR)

.3.5/4.5-9 3.5/4.5-9 J.-

Local:LHGR K.

Minimum Critical Power Ratio (MCPR) 3.5/4.5-10 3.5 Limiting Conditions for Operation Bases 3.5/4.5-11 4.5 Surveillance Requirements Bases-3.5/4.5-16

~

3.6/4.6' PRIMARY SYSTEM BOUNDARY

.3.6/4.6-1 A.

Thermal Limitations 3.6/4.6-1

.B.

Pressurization Temperature 3.6/4.6-1 C.

Coolant Chemistry 3.6/4.6-2 D.

Coolant Leakage 3.6/4.6-3 E.

Sefety and Relief Valves

3. 6/4. 6-4--

F.

Structural Integrity 3.6/4.6 3.6/4.6-5 G.: Jet Pumps H.

Recirculation Pump Flow Mismatch

.3.6/4.6-5~

I.

Shock Suppressors (Snubbers) 3.6/4.6-Sa 3.6 - Limiting Ccnditions f'or Operation Bases 3.6/4.6-8 3.7/4.7 3.7/4.7 jCONTAINMFJ(T SYSTEMS 3.7/4.7-1 A.

Primary' Containment 3.7/4.7-7 B.

Standby Gas Treatment System 3.7/4.7-8 C.

SecondarysContainment 3.7/4.7-9 y

D.

Primary Containment Isolation Valves N

s s.

3.7/4.T-11 Limiting. Conditions for Operation Bases 3.7/4.7-15

~

3'.7

. b 4.7 Surveillance Requirements Bases 3.8/4.8-1

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i38/4'8 RADI0 ACTIVE EFFLUENTS 3.8/4.8-1 A.

Gaseous Effluents 3.8/4.8-6a B.

Liquid Effluents 3.8/4.8-9 m.

e C.

Mechanical Vacuum Pump 3.8/4.8-10 D.. Environmental Monitoring Program

',E 3.8/4.8-13 E.1 Solid Radioactive Waste 3.8/4.8-14 F.

Miscellaneous Radioactive Materials Sources.

~

3.8/4.8-14a v

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H.-Control-Room Emergency" Filtration System

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3.8/4.8A L_imiting Con'ditions for-Operation and Surveillance s

3.8/4.8-15 Req.-Bases s'

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QUf.D-CITIES DPR #30 F.

Control Room "entilation System F.

Control Room Ventilation System O

Isolation Isolation 1.

The control room ventilation systems 1.

Surveillance for instrumen-are isolated from outside air on a tation which initiates signal of high drywell pressure, low isolation of control room water _ level, high main stream-ventilation shall be as line flov high toxic gas concentration, specified in Table 4.2-1.

y high radiation in either of the reactor building ventilation exhaust ducts, or

. manually.. Limiting conditions for operation shall be as Lindicated in Table 3.2-1 and Specifications 3.2.H.

'and 3.2.E.-2.

2.

The toxic gas detection instrumentation 2.

Manual isolation of the control shall consist of-a chlorine, ammonia, room ventilation systems shall and sulphur dioxide analyzer with each be demonstrated once every trip setpoint set at:

refueling outage.

a.

Chlorine concentration 1 5 ppm.

b.

Ammonia concentration < 50 ppm.

c.

Sulphur dioxide concentration 1 3 ppm.

The provisions of Specification 3.0.A.

are not applicable.

G.

Radioactive Liquid Effluent Instrumentation G.

Radioactive Liquid Effluent Instrumentation The effluent monitoring instrumentation shown in Table 3.2-5 shall-be operable with Each radioactive liquid effluent alarm setpoints set to ensure that the monitoring instrument shown in limits of Specification 3.8.B. are not Table 4.2-3 shall be demonstrated exceeded. The alarm setpoints shall be.

operable by performance of the determined in accordance with the ODCM.

given source check, instrument check, calibration, and functional test operations at the frequencies shown in Table 4.2-3.

1.

'With a radioactive liquid effluent monitoring instrument alarm / trip setpoint less conservative than required, without. delay suspend the release of radioactive liquid effluents cronitored by the affected instrument, or-declare the instrument inoperable, or change the betpoint so it is acceptably conservative, m

b 3.2/4.2-3

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QUAhCITIES DPR 30

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_2.

With one or more radioactive liquid

,?1

-effluent monitoring instruments inoperable, take the action shown in Table 3.2-5.

Exert best efforts to return the; instrument to operable status'within 30 days and,-if un-

, successful, ' explain in the next Semi-Annual Radioactive = Effluent Release.

Report why the inoperability was not

-corrected in a timely manner. :This is

~

in lieu'of'an LER.

.3.

In the event a limiting condition

'for operation and associated action requirements cannot be satisfied

- because of circumstances in excess of those addressed-in the specifications, provide a 30-day written report to the

.NRC, and no changes are required in the operational condition of the plant, and this' does not prevent' the plant from entry into an operational mode.

E.

Radioactive Gaseous Effluent H.

Radioactive Gaseous Effluent Instrumentation Instrumentation O..

'shown in_ Table 3.2-6 shall be operable with monitoring instrument in Table 4.2-4 The effluent monitoring instrumentation Each radioactive gaseous radiation alarm / trip setpoints set to ensure that the shall be demonstrated ' operable by limits of Specification 3.8.A. are not performance of the given source check, J exceeded. 'The alarm / trip setpoints shall instrument check, calibration, and be determined'in accordance with the ODCM.

functional test operations at the frequency shown in Table 4.2-4 1.

With airtdioactive gaseous effluent monitoring instrument alarm / trip setpoint less conservative than required, without delay _ suspend the release of radioactive. gaseous effluents monitored by the affected instrument,'or declare the instru-ment. inoperable, or change the set-

,,pcint'so it is acceptably.

conservative.

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M 3.2/4.2-4

c QUAD-CITIES DPR 30 f[';

2.- With'one or more radioactive gaseous effluent monitoring instruments. inoperable, take the action shown in Table 3.2-6.

Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release-Report why the inoperability was not corrected in a timely manner.

This is in lieu of an LER.

3..

In the. event a limiting condition for operation and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifica-tions, provide a 30-day written report I

to the NRC and no changes are required in the operational condition of the plant,-and this does not prevent the plant from entry into an operational mode.

O

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3.2/4.2-5 6_

QUAD-CITIES e

DPR-30 t

+:

jag so that none of the activity released during the refueling accident leaves the reactor

' building via the normal

ventiletion stack but that all the activity is processed by tha standby: gas treatment system.

Tha instrumentation _ which is provided to monitor the postaccident condition is listed in Table.3.2-4.

The-instrumentation listed and the limiting conditions for operation on'these systems ensure adequate monitoring of the containment following a loss-of-coolant accident. Information from this. instrumentation util provide. the operator with a detailed knowledge-of'the conditions resulting from-the accident; based on this infor-

>mation he can make-logical decisions regarding postaccident recovery.

Tha specifications allow for postaccident. instrumentation to be out of service for a psriod of 7. days. This period is based _on the fact thht several diverse instruments ara-available for: guiding the operator should an accident occur, on the low probability Lof an' instrument being out of service and an accident occurring in the 7-day period, end on engineering judgment.

-The normal supply'of air for the control room ventilation system Trains "A" and "B" is l

fcutside the service building. In the event of an accident, this source of air may be rIquired to be shut;down to prevent high doses of radiation in the control room. Rather than provide this isolation function on a radiation monitor installed in the intake hir duct, signals which indicate an accident,.i.e.. high drywell pressure, low water level, main streanline high flow, or high radiation in the reactor building ventilation duct, will'eause isolation of-the' intake air to the control room. The above trip

.zignals result in-immediate isolation of the control-room ventilation system and thus minimize any' radiation dose. Manual isolation t apability is also provided. Isolation-O from high toxic chemical concentration has been added as a result of the," Control' Room Habitability Study" submitted to the NRC in December 1981 in response to NUREG-0737.

Itta III D.3.4.

As explained in Section 3 of this study,. ammonia, chlorine, and sulphur

' dioxide detection capability has been provided. The setpoints chosen for the control room ventilation isolation are. based on early detection in the outside air ' supply at.

the odor threshold, so that the toxic-chemical will not achieve toxicity limit con-ctntrations in the Control Room.

LTha radioactive liquid and gaseous effluent instrumentation is provided to monitor the ralease of radiqactive materials in liquid and gaseous effluents during releases. The alarm setpoints for-the instruments are provided to ensure that the alarms will occur I

prior 'to exceeding the limits of 10 CFR 20.

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U 3.2/4.2-8

_ _ _ _ _ _ _. _.. - ~.

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DPR -30 TABLE 3.2-4 POSTACCIDEV.I' MONITORING INSTRUMENTATION REQUIREMENTS (2)

^

Instrument Minimus Number Readout of Operable-location Number Channels (1)(3)

Parameter Unit 1 Provided Range 1

Reactor pressure 901-5 1

0-1500 psig 1

0-1200 psig 1.

Reactor water: level 901-3 2-

-243 inches +57 inches 1

Torus water temperature 901-21 2

0-200*F 1

Torus air temperature 901-21 2

0-600*F e

Torus water level indicator 901-3

'l

-5 inches -- 45 inches (narrow range)'

~2(a)

Torus water level indicator 901-3 2

0-30 feet (wide range)

Torus water level sight. glass 1

18 inch range (narrow range) 1 Torus pressure 901-3 1-

-5 inches Hg to 5 psig 901-3 1

-5 inches Hg to 5 psig 2-Drywell pressure 0 to 75 psig 2

0 to 250 psig 2-Drywell temperature 901-21 6

0-600*F 2

Neutron monitoring 901-5 4

0.1-10s CPS 2(4) -

Torus to drywell 2

0-3 psid differential pressure 1(s)

Drywell Hydrogen concentration 901-55,56 2

0-4%

s 2(7)

Drywell radiation monitor 901-55,56 2

1.to lo R/hr

' Main. steam RV 901-21 1 per NA position, acoustic valve monitor 2/ valve (s)

Main steam RV 901-21' 1 per 0-600*F~

position, valve temperature monitor Main steam SV 901-21 1 per NA,

i.

_ position, acoustic valve monitor

- 2/ valve (s)-

Main steam-SV 901-21 1 per 0-600*F valve

position, temperature-monitor 3.2/ 4.2-15

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QUAD-CITIES D PR-30 Notes

'l.,

Instrtunent.L ehannels required during power operation to monitor postaccident

[-

conditions.-

~

'2. Pr'ovisions 'are made for local sampling and monitoring of drywell acnosphere.

3.

In the event any of the instrumentation becomes inoperable for more than 7

days during reactor operation, initiate an orderly shutdown and be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. See notes 4, 5, 6, ;7, and 8 for exceptions to this requirement.

4. - Frca and af ter the date that one of these parameters is reduced to one indication, continued operation is not permissible beyond thirty days unless such instrumentation is sooner made operable. In the event that all indication of these parameters is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in twenty-four (24) hours.

5.

If the number of position indicators is reduced to one indication on o'ne or more valves, continued operation is permissible; however, if the reactor is in a cold shutdown condition for longer than12 hours, it may not be started up until all position indication is restored.

In the event that all position-indication is lost on one or more valves and such indication cannot be restored in 30 days, an orderly shutdown shall be initiated, and the reactor shall be-depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6.

Frau and after th'e date that this paramet;er is reduced to either one narrow-range 1.tdication or one wide-range indication, continued reactor operation is not. permissible beyond 30 days unless such instrument is sooner-made operable. In the event that either all narrow-range indication or all wide-range indication is disabled, continued reactor operation is not permis--

sible beyond 7 days unless such instruments are sooner made operable.

In.

the event-that -all indication for this parameter is disabled, and such indication cannot be restored in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />...

7.

With'less than the minimum number of operable channels, initiate the pre-planned alternate method of monitoring this parameter within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />..

and:

a.

either restore the inoperable channel (s) to operable status within 7 days of the event, or b.

prepare and submit a special' report to. the NRC within 30 days following the event, outlining the action taken, the cause of the inoperability,

- and the plans and schedule for restoring the system to operable status..

~

3.2/4.2-15a L.

QUAD CITIES DPR-30 8.

From and af ter the date that one of the drywell hydrogen monitors becmes inoperable, continued. reactor operation is permissible, a.

If both drywell hydrogen monitors are inoperable, continued reactor operation is permissible for up to 30 days provided that during this time the HRSS hydrogen monitoring capability for the drywell is operable.

b '.. IE all drywell hydrogen monitoring capability is lost, continued reactor operation is permissible for up to 7 days.

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i QUAD-CITIES

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' DER ~- 3 0 Table 3.2-5 g

RADICACTIVE LIQUID EFFLUENT NONITORING INSTRUMENTATION Minimum-No.-

+

of Operable Total No.

Channels of Channels Parameter Action- (1)

I 1-Service Water A,

Ef fluent Gross Activi ty Moni tor i

i I

Liquid Radwaste C

Effluent Flow Rata Monitor I

I Liquid Radw'aste S

Effluent Gross Activity Monitor

?

/.

Notes:

Action A:

Wi th less than the minimum number of coerable channels, releases via this pathway may continue, provided that at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples' are collected and analy:ed for beta or ga ma activity at an LLD of less than or equal to 10-7 uCi/ml.

Action B:

With less than the minimum number of ocerable channels, effluent releases via this pathway may continue, provided that prior to initiating a release, at least.2 independent samples are analyzed in accordance wi th Speci fication 4.3.3.1., and at Teast 2 members of the facility staff independently verify the-release calculation and i

discharge valving.- Otherwise, suspend release 'of radioactive ef flu-ents via this pathway.

Action-C: With-lesse than the-minimum nu=cer of coerable channels, releases via this pathway may continue, provided the ficw rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Fumo curves may be utilized to estimate flew.

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QUAD-CITIES s

DPR"30 Table 3.2-6'~

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION' Minimum No.

'of' Operable Total No.

Channels'- (1) of Channels Ptrameter Action (2) 1.-

2-SJAE Radiation D

Monitors 1

2 Main Chimney Noble A

Gas Activity Monitor l'

1 Main Chimney Iodine C

Sampler l'

1 Main Chimney C

Particulate Sampler 1

1 Reactor Bldg. Vent B

Sampler Flow Rate Monitor 1

1 Reactor Bldg. Vent C

Iodine Sampler 1

1 Reactor Bldg. Vent C

Particulate Sampler 1

1 Main Chimney Sampler B

Flow Rate Monitor l-1 Main Chimney Flow B

Rate Monitor 1

2 Reactor Bldg. Vent E

Noble Gas Monitor 1.

1 Main Chimney F

High Range Noble Gas Monitor Notes (1)

For SJAE monitors, applicable during SJAE operation. For other instrumentation, applicable at all times.

'(2) 1.ction As With the number of operable channels less than the minimum-requirement, effluent releases via this pathway may continue, provided grab samples are taken at least once per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift and these samples are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Action ~B:- With the' number of operable channels less than the' minimum required, ef fluent' releases via this pathway may continue provided that the flow rate is estimated at-least once 'per 4

-hours.

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, 4 QUAD-CITIES; DPR 30 Action C: With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as

. required in Table 4.8-1.

ActionaD - With:less than' the' minimum-channels operable, gases' freethe main condenser off gas system may;be released to ther environment-for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided at least one chimney >

monitor is operable; otherwise, be in hot stand-by in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Action,E: With less9than the minimum channels operable, immediately suspend release of radioactive effluents-via.this pathway.

Action F: With less than the minimum channels operable, initiate the preplanned alte' nate method of monitoring the appropriate r

parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, ands -

(1) either restore the inoperable channel (s) to operable status within 7 days of the event, or (2) prepare and submit a Special Report to the Commission within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

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Instrument

~ Instrument-Funegional Instryment Channel ~

Test-Calibration 2 Check" HPCI Isolation 15 Steamline[high flow' (1) (9)

Once/3 months Nones l

-2.; Steamline area high temperature Refueling outage Refueling outage-None~

13.

Low reactor: pressure.

-(1)

Once/3 months

'None Reactor Building Ventilation System Isolation And Standby Treatment System Initiation

1. : Refueling. floor radiation monitors (1)

Once/3 months Once/ day Control Room Ventilation System Isolation 1.

Reactor low water level (1)

Once/3 months once/ day 2.

Drywell high pressure (1)

Once/3 months None

3.. Main steamline high flow (1)

Once/3 months once/ day

4. ' Toxic gas analyzers (chlorine, Once/ month One/18 months once/, day ammonia,.' sulphur dioxide)

Notes:-

5

~ 1. - ' Initially.once per month until exposure hours (E as defined on Figure 4.1-1) are 2.0 X 10,

thereafter, according to Figure 4.1-1 with an interval not less than 1 month nor more than 3 months. The compilation of instrument failure rate data may include data obtained from-O' other boiling water reactors for which the same design instrument operates in an environ-ment similar to that of Quad-Cities Units 1 and 2.

2.

Functional tests, calibrations, and instrument checks are not required when these

~ instruments are not required to be operable or are tripped.

3. 7 This instrumentation is excepted from thd functional test definition. The functiorial test shall consist of injecting a simulated electrical signal into the measurement channel.

4.

This instrument channel is excepted from the functional test definitions and shall be calibrated using simulated electrical signals once every 3 months.

5.

Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calibrations shall.be performed during controlled shutdowns with a required frequency not to exceed once per week.

6.

The positioning mechanism shall be calibrated every refueling outage.

7.

Logic system functional tests are. performed as specified in the applicable-section for these. systems.

8.

Functional test shall include verification of operation of the degraded voltage 5-minut'e tieer and 7 second inherent timer.

29.

Verification of the time delay setting of 31 + 110 seconds shall be performed during each refueling outage.

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QUAD-CITIES DPR. 30 TABLE 4.2-2 POSTACCIDENT MONITORING INSTRUMENTATION SURVEILIANCE REQUIREMENTS Ins trument Minimum Number Readout of Operable location Ch*nnels*

Parameter-Unit 1 Calibration Instrument: Check 1

Reactor pressure >

901-5 Once every once-per day 3 months 1-Reactor water-level 901-3 Once every-Once per. day i

3 months 1

Torus water temperature 901-21 Once every Once per day 3 months 1

Torus air temperature 901-21 Once every once per day 3 months Torus water level' indicator 901-3 Once every Once per day (narrow range) 3 months 2

Torus water level indicator 901-3 Once every once per 31 days (wide range) 18 months Torus water level sight glass N/A None 1

Torus pressure 90 1-3 Once every once per day 3 months 2

Drywell pressure 901-3 Once every once per day 3 months 2

Drywell tem >erature 901-21 Once every Once per day 3 months

, 2 Neutron monitoring 901-5 Once every Once per day 3 months 2

Torus to drywell Once every None differential pressure 6 months 1

Dryvell Hydrogen concentration 901-55,56 Once every once per 31 days 3 months 2~

Drywell radiation monitor-901-55,56-Once every***

Once pef 31 days 18 months Main stema RV 901-21 Once per position, acoustic 31 days monitor 2/vcive Main steam RV 901-21 Once every once per

position, 18 months 31 days tenperature+

monitor 3.2/4.2-18

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~ QUAD CITIES DPR-30 Ins trument Min imum. Nunber-

Readout, cf Operable Tocation Chann els*

Parameter Unit 1 Calibration Instrument Check Main steam SV 901-21 Once per position, acoustic 31 days monitor 2/vsive.

Main. steam ST 901-21 Once.every-Once. per-

position, 18 months 31 days temperature monitor

• Instrument channels required during power operation to monitor postaccident conditions.

• • Functional tests will be conducted before startup at the end of each refueling outage or after maintenance is performed on a particular safety or relief valve.

• • • Calibration shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr; and a one-point calibration check of the detector below 10 R/hr with an installed or portable gamma source.

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QUAD CITIES DPR-30 TABLE 4.2-3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Functional Source Instrument Check (1)

Calibration (1)(3) Test (1)(2) Check-(l)

-Liquid Radwaste D

R Q (7)

(6)

. Effluent Gross Activity Monitor Snrvice Water D

R Q (7)

R Eff'uent Gross Activity Monitor Liquid Radwaste (4)

R NA NA Effluent Flow Rate Monitor Notes:

-(l) D = once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = once per 31 days

Q = once per 92 days R.= once per 18 months-S = once per 6 months

.(2) The Instrument Functional Test shall also demonstrate that control room. alarm annunciation occurs, if any of the following conditions exist, where applicable.

a. Instrument indicates levels above the alarm setpoint.

b. Circuit failure.

c. Instrument indicates a downscale-failure

d. Instrument controls not set in OPERATE mode.

3) Calibration shall include performance of a functions 1 test.

4)-Instrument Check to verify flow during periods of release.

5) Callabration shall include performance of a source check.

6): Source' check shall-consist of observing instrument response during a discharge.

7) Functional test may be performed by using trip check and test circuitry essociated with the monitor chassis.

3.2/4.2-19

QUAD-CITIES

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RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibra-Functional Source Instrument Mode (2)

Check (l) tion (l) (4)

Tes t(1) (3 )

_ Check (l)

Main Chimney NobleeGas*

B1 In-R-

Q:

M-Activity Monitor.

Main Chimney Sampler B

D, R

Q (4)

NA Flow Rate Monitor Reactor: Bldg. Vent Sampler B

D R

Q(6)

NA Flow Rt.te Monitor

. Main Chimney Flow Rate B

D R

Q NA Monitor Reactor Bldg.. Vent B

D R

Q Q

Activity Monitor SJAE Activity Monitor A

D R

Q.

R Main Chimney Iodine and B

D(5)

NA NA NA Particulate Sampler Reactor Bldg. Vent Iodine B

D(5)

NA NA NA and-Particulate Sampler Main Chimney High Range B

D(5)

R Q

M Noble Gas Monitor Notes s

(1)

D - once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = once per 31 d,aye Q = once per 92 days R = once per 19 months (2) A = during SJAE operation B = at all times (3) The Instrument Functional Test shall also demonstrate that control room alarm annunciation. occurs,. it any2 of the-following. conditions, exist,.wh' eses applicable:

a.- Instrument indicates levels above the alarm setpoint b.

Circuit failure-c.

Instrument indicates a downscale failure d.

Instrument controls not set in OPERATE ~ mode (4) Calibration shall include performance of a functional test.

-(5)

Instrument check to verify. operability of the instrument; that.thC instrument.-

is in-place and-functioning properly.

(6) FuncH - 1 test shall be performed on local switches providing low flow alarm.

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Control Room Emergency Filtration H.

Control Room Emergency Filtration System System I

1.

The control room emergency 1.

At least once per month, initiate filtration system, including at 2000 cfm (110%) flow through the L

least one booster fan shall be control room emergency filtration operable at all times when system for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with secondary containment

• integrity-ism therheatersioperahle%

required, except as specified im Sections.3.8.H.1.a. and b.

l

a. ' Af ter the control room emergency-filtration system is made or found to be inoperable for any; reason, reactor operation and fuel handling are permissible only during the succeeding 14 days. Within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following the 14 days, the reactor shall l

be placed in a condition for which the control room emergency filtration system is not required in accordance with Specification 3.7.C.1.a. through d.

b.

Specification 3.8.H.l.a. above does not apply during performance or post-maintenance testing, or-during removal of the charcoal test canister.

2.

Periodic Performance Requirements 2.

Performance Requirement Tests a.

The results of the in-place DOP a.

At least once per operating cycle tests at 2000 cfm (110%) on but not to exceed 18 months, or HEPA filters shall show < 1%

following painting, fire, or toxic DOP penetration.

chemical release in any ventilation zone communicating with the intake b.

The results of in-place of the system while the system is halogenated hydrocarbon tests at operating that could contaminate the 2000 cfm (110%) on the charcoal HEPA filters of charcoal absorbers, banks shall show < 1% penetration.

perform the following c.

The results of laboratory carbon

1) In-place DOP test the HEPA sample analysis.shall show > 90%

filter banks..to verify leaktigh :

methyl iodide-removal efficiency-integrity._

when tested at 130 C and 95% R.H.

2.

In-place test the charcoal I

absorber banks with halogenated hydrocarbon tracer to. verify leaktight integrity.-

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3) Remove one carbon test canister from the charcoal absorber. Subject this sample to a laboratory analysis to verify methyl

~1odide removal efficiency.

b At_leastonce-pec. operating. cycle, but not to exceed 1F months, the following conditions.shalLbe demonstrated:.

1) Pressure drop across the combined filters--

is less than 6 inches of water at 2000 cfm (110%)

flow rate.

2) Operability of inlet heater demonstrates heater AT of 15 F.

0 3.

Postmaintenance Requirements 3.

Postmaintenance Testing a.- After any maintenance or heating a.

After any maintenance or testing s

that could affect the HEPA filter that could affect the leaktight in-p or HEPA filter mounting frame tegrity of the HEPA filters, perform

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leak-tight integrity, the results in-place DOP tests on the HEPA of the in-place DOP tests at 2000 filters' in accordance with Specifica-cfm (110%) on HEPA filters shall tion 3.8.H.2.a.

show < l'. DOP penetration.

b.

After any maintenance or testing b.

Af ter any ma'intenance or testing that could affect the charcoal.

that could affect the leaktight in-absorber leaktight integrity, the tegrity of the charcoal absorber results of in-place halogenated banks, perform halogenated hydro-hydrocarbon tests at 2000 cfm carbon tests o'n the charcoal ad--

(110%) shall show < 1% penetration sorbers in accordance with Specifi-cation 3.8.H.2.b.

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-QUAD-CITIES DPR-30

. 3.8/4.8.C.

MECHANICAL VACUUM PUMP The purpose of isolating the mechanical vacuum line is to limit release of activity from the main condenser. During an accident, fission products would be transported from the reactor through the main steamline to the main condenser.

The fission product radioactivity would be sensed by the main steamline radio-activityrmonitors which-initiate isolatiorr 3.8/4.8.F.

MISCELLANEOUS RADIOACTIVE MATERIAIK SOURCES The objective of this specification is to assure that leakage from byproduct, cource and special nuclear material sources.does not exceed allowable limits.

The limitations on removable contamination for sources = requiring leak. testing,.

including alpha emitters, is based on 10 CFK' 70.39 (c) limits for plutonium..

3.8/4.8.E.

SOLID RADIOACTIVE WASTE The operability of the solid radioactive waste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to.being shipped off-site. This specification implements the requirements of_10 CFR 50.36a. and GeneraLDesign Criteria. 60. of Appendix. A_ to.10.CFR Part 50.

3.8/4.8.E CONTROL ROOM AIR FILTRATION The purpose of these specifications is to assure availability of the control Q room emergency air filcrations unit that has been installed in response to NUREG-0737 Item III D.3.4.

Operation of this unit is described in the " Control Room Habitability Study" for Quad-Cities Station which was submitted to the NRC in December 1981.

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