ML20206B504
| ML20206B504 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/10/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206B508 | List: |
| References | |
| GL-83-36, NUDOCS 8606190119 | |
| Download: ML20206B504 (44) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5
'j WASHINGTON, D. C. 20555
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1 COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET N0. 50-254 OUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-29 i
^
1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated September 26, 1984, complies with the standards and requirements cf the Atomic Energy Act of 1954, as amended (the Acti and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by the addition of License Condition 3.L., and by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. DPR-29 is hereby amended to read as follows:
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8606190119 860610 PDR ADOCK 05000254 l
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 94, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
New License Condition 3.L. is added to read as follows:
3.L.
Post-Accident Sampling A program will be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant chimney effluents, and containment 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 samplino and analysis equipment.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGUL ORY OWISSION L.
s John. Zwolinski, Director BWR oject Directorate #1 Division of RWR Licensino
Attachment:
Changes to the Technical Specifications Date of Issuance: June 10, 1986
ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT I
ii 11 3.2/4.2-3 3.2/4.2-3 3.2/4.2-4 3.2/4.2-4 3.2/4.2-5 3.2/4.2-5 3.2/4.2-8 3.2/4.2-8 3.2/4.2-15 3.2/4.2-15 3.2/4.2-15a 3.2/4.2-15a 3.2/4.2-15aa 3.2/4.2-15b 3.2/4.2-15b 3.2/4.2-15c 3.2/4.2-15c 3.2/4.2-15d 3.2.4,2-15d 3.?/4.2-17 3.2/4.2-17 3.2/4.2-18 3.2/4.7-18 3.2/4.2-18a 3.2/4.2-19 3.2/4.2-19 s
3.8/4.8-20 3.2/4.2-20 3.8/4.8-14a 3.8/4.8-14b 3.8/4.8-19 i
l
QUAD CITIES DPR-29 TABLE OF CONTENTS (Cont'd)
Page 3.5/4.5-1 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 3.5/4.5-3 B.
Containment Cooling Mode of the RHR System 3.5/4. 5-4 C.
HPCI Subsystem 3.5/4.5'-5 D
Automatic Pressure Relief ~ Subsystems 3.5/4.5-6' Reactor Core Isolation Cooling Systent E.
3.5/4.5-6 Minimunr Core and Containment Cooling System Availability F.
3.5/4.5-7 G.
Maintenance of Filled Discharge Pipe 3.5/4.5-8 Ccndensate Pump Room Flood Protection 3.5/4.5-9 H.
Average Planar Linear Heat Generation Rate (APLHGR)
I.
3.5/4.5-9 J.
Local LHGR 3.5/4.5-10 K.
Minimum Critical Power Ratio (MCPR) 3.5/4.5-11 3.5 Limiting Condittons for Operation-Bases 3.5/4.5-16 4.5 Surveillance Requirements Bases
~
3.6/4~.6-T 3.6/4.6 PRIMARY SYSTEM BOUNDARY 3.6/4.6-T l
A.
Thermal Limitations 3.6/4.6-1 l
B.
Pressurization Temperature 3.6/4.6-2 C.
Coolant Chemistry 3.6/4.6-3 O.
Coolant Leakage 3.6/4.6-4 E.
Safety and Relief Valves 3.6/4.6 :
F.
Structural Integrity 3.6/4.6-5 G.
Jet Pumps 3.6/4.6 H.
Recirculation Pump Flow Mismatch 3.6/4.6-5a I.
Shock Suppressors (Snubbers) 3.6/4.5-8 3.6 Limiting Condttions for-Operation Baser 3.7/4.T-I 3.7/4.7 CONTAINMENT SYSTEMS l
3.7/4.T-1 A.
Primary Containment 3.7/4.7-7 l
B.
Standby Gas Treatment System 3~.7/4.7-8 C.
Secondary Containment 3.7/4.7-9 D.
Primary Containment Isolation Valves 3.7/4.7-l T 3.7 Limiting Conditions for Operation Baser 3.7/4.7-15 4.7 Surveillance Requirements Baser 3.8/4.8-1 i
3.8/4.8 RADIOACTIVE EFFLUENTS 3.8/4.8-1 i
A.
Gaseour Effluents.
3.8/4.8-6a.
i B.
Liquid Effluents 3.8/4.8-9 C.
Mechanical Vacuum Pump 3.8/4.8-10r.
l D.
Environmental Monitoring Progrant 3.8/4. 8-13~
E.
Solid Radioactive Waste 7.8/4.8-14 F.
Miscellaneous. Radioactive Materia.lr Sources:
- 3. 8/ 4. 8-14 a
-L Control Room Emergency Filtration System 3.8/4.8A. Limiting Conditions for Operation and Surveillance 3.8/4.8 Req. Bases f
Amendment No. 94
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QUAD-CITIES DPR-29 F.
Control Room Ventilation System F.
Control Room Ventilation System
N 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 uater level, high main stream-ventilation shall be as line flou,high toxic gas concentration, specified in Table 4.2-1.
high radiation in either of the reactor i
t building ventilation exhaust ducts, or manually. Limiting conditions for operatio.i shall be as indicated in Table 3.2-1 and Specifications 3.2.H.
and 3.2.E.2.
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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 i
trip setpoint set at:
refueling outage, a.
Chlorine concentration < 5 ppm.
b.
A==onia concentration < 50 ppm.
c.
Sulphur dioxide concentration <
3 ppm.
The provisions of Specification 3.0.A.
are not applicable.
G.
Radioactive Liquid Effluent Instrumentation G.
Radioactive Liquid Effluent Instrumentation The effluent nonitoring instrumentation shown in Table 3.2-5 shall be operable with Each radioactive liq 3id effluent alarm hetpoints set to ensure that the monitoring instrumenh 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 t
test operations at the frequencica shown in Table 4.2-3.
1.
With a radioactive liquid effluent monic' ring instrument alarm / trip setp;1nt 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 setpoint so it is acceptably conservative.
3.2/4.2-3 Amendment No. 94 l
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QUAD-CITIES DPR-2 9 2.
With one or more radioactive liquid
,,g 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 Radioaccive 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.
H.
Radioactive Gaseous Ef fluent H.
Radioactive Gaseous Effluent Instrumentation
, Instrumentation O.
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 ODCI.
functional test operations at the frequency shown in Table 4.2-4.
1.
With a radioactive 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-
, point so it is acceptably conservative.
k.J 3.2/4.2-4 Amendment No. 94
QUAD-CITIES DPR- &
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2.
With one or more radioactive gaseous effluent monitoring instruments inoperable, take the action shoun 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 Releast 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 4
in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
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3.2/4.2-5 Arendment 94 t
QUAD-CITIES DPR 29..
fs so that none of the activity released during the refueling accident leaves the reactor building via the nor=al ventilation stack but that all the activity is processed by the standby gas treat =ent system.
The instrumentation which is provided to monitor the postaccident condition is listed in Table 3.2-4 The instru=entation listed and the limiting conditions for operation on these systems ensure adequate monitoring of the contain=ent 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-mation he can =ake logical decisions regarding postaccident recovery.
The specifications allow for postaccident instrumentation to be out of service for a period 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 j
of an instrument being out of service and an accident occurring in the 7-day period, and on engineering judgment.
The normal supply of air for the control room ventilation system Trains "A" and "B" is l
outside the service building. In the event of an accident, this source of air may be.
rsquired 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 air duct, signals which indicate an accident, i.e.
high drywell pressure, low water 1svel, main streamline high 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 immediate isolation of the control room ventilation system and thus minimize any radiation dose. Manual isolation capability is also provided. Isolation e'*from high toxic chemical concentration has been added as a result of the " Control Room 1
k / abitability Study" submitted to the NRC in December 1981 in response to NUREG-0737 H
i 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 l
the odor threshold, so that the toxic chemical will not achieve toxicity limit con-
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cantrations in the Control Room.
1 I
The radioactive liquid and gaseous effluent instrumentation is provided to monitor the j
release of radiqactive materials in liquid and gaseous effluents during releases. The i
alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the itsits of 10 CFR 20.
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3.2/4.2-8 Amendment No. 94 I
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QUAD-CITIES.
DPR"29 TABLE 3.2-4 POSTACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS (2)
Instrument Minimus Number Readout of Operable Location Number Chennels(1)(3)
Parameter Unit 1 Provided Range 1
Reactor pressure 901-5 1
0-1500 psig i
2 0-1200 psig 1
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 Torus water level indicator 901-3
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-5 inches -- +5 inches (narrow range) ~
2(a)
Torus water level indicator 901-3 2
0-30 feet (vide range)
Torus water level sight glass 1
18 inch range (narrow range) 1 Torus pressure 901-3 1
-5 inches Hg to 5 psig 2
Drywell pressure 901-3 1
-5 inches Hg to 5 psig 0 to 75 psig 2
0 to 250 psig l
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 paid 1
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
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- position, valve temperature monitor Main steam SV 901-21 I per NA.
l position, acoustic valve
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monitor j
l 2/ valve (s)
Main steam SV 901-21 1 per C-600*F valve l
_ position, temperature monitor i
3.2/ 4.2 Amendment No. 94,
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QUAD-CITIES DPR-29 Notes 1.
Instrument. channels required during power operation to monitor postaccident condi,tions.
2.
Pr'avisions are made for local sampling and monitoring of drywell atmosphere.
3.
In the event any of the instrumentation becomes inoperable for more than 7 days during reactor operation, initiate an orderly slutdown 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 From and af ter the date that one of these paranaters 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 neber of position indicators is reduced to one indication on one or 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
up until all position indication is restored.
In the event that all position indication is lost on one or more valves and asch indication cannot be restored in 30 days, an orderly shutdown shall be initiated, and the reactor
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shall be As.a.wurned 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 instruents are sooner made operable. In I
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 nisaber 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 />, l
l and:
I a.
either restore the inoperable channel (s) to operable status within 7 days of the event, or b.
prepara 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 actiedule for restoring the system to operable status.
I 3.2/4.2-15s Amendment No. 94 r.
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QUAD CITIth DPR-29 8.
From and af ter the date that one of the drywell hydrogen monitors becomes inoperable, continued reactor operation is permissible, a.
If both dryvell 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..
If all drywell hydrogen monitoring capability is lost, continued reactor operation is permissible for up to 7 days.
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3.2/4.2-15 aa Amendment No. 94
QUAD-CITIES DPR-29 Table 3.2-5 RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Min imu.r No.
of Operable Total No.
Channels of Channels Parameter Action (1)
I 1
Service Water A-Effluent Gross Activity Monitor I
1 Liquid Radwaste C
Ef fluent Flow Rata Monitor i
I Liquid Radw'aste 8
Effluent Gross Activity Monitor i
1
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Notes:
Action A; With less than the minimum number of ooerable 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 sampics are collected and analyzed for beta or gamma activity at an LLD of less than or equal to 10-7 uCi/mi.
Action B:
With less than the minimum number of operable 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 4.8.8.1., and at least 2 members of the facility staff independently verify the. release calculation and discharge valving.
Otherwise, suspend release "o~f~ radioactive ef flu-ents via this pathway.
Action-C:
With-less than the minimum nu=ber of ooerable channels, releases via this pathway may continue, provided th 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 r#1 eases.
Pumo curves cay be l
utilized to estimate flow.
3.2/4.2_155
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4
GCAL-CITIts cPR-29 fable 3.2-6 7PI.UENT MONITOPING INSTREMENTATICN Pa rarne te r Actien'2 SJAE Radiatien r
Monitors Main Chimney Noble A
Gas Activity Monitor Main Chimney Iodine C
Sampler Main Chimney C
Particulate Sainpler Reactor Bldg. Vent E
Sampler Flow Rate Monitor Reactor Bldg. Vent c
Iodine Sampler Reactor Bldg. Vent C
Particulate Sampler Main Chimney Sampler B
Flow Rate Moniter Main Chimney Flow E
Rate Monitor Reactor Bldg. Vent E
Noble Gas Monitor Main Chimney F
High Range Noble Gas Monitor le during SJAE operation.
For other at all times.
Q( cperable channels less than the Ininimum taent. releases via this pathway may continue, let? ate [taken at least once per 8 bcur s.". i f t 4ti an'alyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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h')elpereA1le}channelslessthantheminimum
" gel leesesivia.thispathwaymaycontinue h rate'is' estimated at least once per 4
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Table 3.2-6 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUKENTATION' Minimum No.
of Operable Total No.
Channels (1) of Channels Parameter Action (2) 1 2-SJAE Radiation D
t Monitors 1
2 Main Chimney Noble A
Gas Activity Monitor i
1 1
Main Chimney Iodine C
Sampler i
1 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 1
Main Chimney Sample:
B j
s Flow Rate Monitor 1
1 Main Chimney Flow B
Rate Monitor 1
2 Reactor Bldg. Vent E
Noble Gas Monitor 1
1 Main Chimney F
Bigh Range Ncble Gas Mcnitor 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, 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 /> 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 />.
Action B: With the number of operable channels less than the' minimum required, effluent' releases via this pathway may continue 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 />.
- ~
Amendment no. 94
QUAD-CITIES DPR-29 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.
Acticn Dr With less than the minimumr channels.. operable, gases froma the sain condenser off gas system may be released to the 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 less.than the minimum channels operable,.immediately suspend release of radioactive effluents via this pathway.
Action F: With less than the minimum channels operable, initiate the l
preplanned alte'rnate method cf 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 />, 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.
s 3.2/4.2-15d Amendment No. 94 i
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I
QUAD-CITIES DPR-29 TABLE 4.2-1 (cont'd)
Instrument Instrument Functignal Channel Testt2s C'alibration(2)
Instrugn C_ heck t2 HPCI Isolation 1.
Steamline hign flow (1)(9)
Once/3 months None 2.
Steamline area nigh temperature Refueling outage Refueling outage None 3.
Low reactor pressure (1)
Once/3 montt.s None Reactor Building Ventilation System Isolation and Standby Treatment System Initiation 1.
Refueling floor radiation (1)
Once/3 months Once/ day monitors Steam Jet Air Ejector Off-Gas Isolation 1.
Off-gas radiation monitors (1) (4)
Refueling outage Once/ day Control Room Ventilation System Isolation 1.
Reactor low water level (1)
Once/3 months Once/ day 2.
Drywell nigh pressure (1)
Once/3 months None 3.
Main steam ine high flow (1)
Once/3 months Once/ day 4.
Toxic. gas an lyzers (chi rine, Once/ month once/18 months Once/ day ammonia, sul hur dioxide Notes:
1.
Ingtially once per month until exposure hours (M 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 other boiling water reactors for whch the same design instrument operates in environment similar to that of Quad Cities Units 1 and 2.
a 2.
Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or tripped.
3.
Tnis instrumentation is excepted from the functional test definition. The function test shall consist of injecting a simulated electric 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 each startup or 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 sytems.
8.
Functional tests shall include verification of operation of the degraded voltage 5
minute timer and 7 second inherent timer.
9.
Verification of the time delay setting of 3 4_ t 310 seconds shsll be performed during each refueling outage.
3.2/4.2-17 Amendment No. 94 i
4
QUAD-CITIES DPR f29 TABLE 4.2-2 POSTACCIDENT MONITORING INSTRUMENTATION SURVEILIANCE REQUIREMENTS Ins trument Minimum Number Readout of Operable location Chennels*
l'aramet e r Unit 1 Calibration Instrument Check 1
Reactor pressure 90 1-5 Once every once per day 3 months 1.
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 r
1 Torus pressure 90 1-3 Once every once per day 3 months 2
Drywell pressure 901-3 Once every once per day 1
3 months 2
Drywell temperature 901-21 Once every once per day l
3 months
, 2 Neutron monitoring 90 1-5 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 pei-31 days 18 months I
Main steam RV 901-21 Once per position, acoustic 31 days monitor 2/ valve Main steam RV 901-21 once every once per
- position, 18 months 31 days I
tempe rature -
U monitor 3.2/4.2-18 Amendment No. 94 m
QUID-CITIES DDR-29 Instrument Minimum Number Readout of Operable lo cation Ch*nnels*
Parameter Unit 1 Calibration Instrument Check Main stean SV 901-21 Once per position, acoustic 31 days monitor
~
2/ valve Main steam SV 901-21 Once every Once per
- position, 18 months 31 days temperature monitor
- Instrianent 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/h:;; and a one-point calibration check of the detector below 10 R/hr with an installed or portable gamma source.
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I 3.2/4.2-18*-
Amendment No. 94
QUAD CITIES DPR-29 TABLE 4.2-3 RADIOACTIVE LIQUID EFFLUENT MONITORING 4
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 Service Water D
R Q (7)
R Effluent Gross a
Activity Monitor Liquid Radwaste (4)
R NA NA Effluent Flow Rate Monitor Notes:
(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) Call bration shall include performance of a source check.
- 6) Sa'urce check shall consist of observing instrument response 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 Amendment No. 94
QUAD-CITIES DPR 29 Table 4.2;4' RADIOACTIVE GASEOUS EFFLUENT F.ONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibra-Functional Source Instrument Mode (2)
Check (1) tion (1) (4)
Test (1) (3 )
Check (1)
Main Chimney NoblevCas-Bt 1
R-Q-
M-Activity Monitor Main Chimney Sampler B
D R
Q (Ji)
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 Sampler Reactor Bldg. Vent Iodine B
D(5)
NA NA NA and Particulate Sampler Main Chimney High Range B
D(5)
R Q
R Noble Gas *Nonitor Notes (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 (2) A = during SJAE operation B = at all times (3) The Instrument Functional Test shall also demonstrate that control room alarm annunciatiort occurs,. if. any. of. the following conditiona, exist,.. wtteses applicable s 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 locd switches providing low flow alarm.
.......___ Amendment N.o. 9.4 _....
._s QUAD-CITIES DPR,,2,9 O
H.
Control Room Emergency Filtration H.
Control Room Emergency Filtration System System
~
}
1.
The control room emergency 1.
At least once per month, initiate r
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-im theehesters operables-required, except as specified in j
Sections 3.8.H.l.a. and b.
i a.
After the control room emergency filtration system is made or found to be inoperable for any reason, reactor operation and fuel baA14ng 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 be placed in a condition for
]
which the control room emergency filtration system is not required in accordance with Specification 3.7.C.l.a. through d.
A b.
Specification 3.8.H.l.a. above
\\./
does not apply during performance 1
or post-maintenance testing, or during removal of the charcoal test canister.
4 l
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 1%
following painting, fire, or toxic DOP penetration.
chemical release in any ventilation zone communicating with the intake i
i b.
The results of in-place of the system while the system is balogenated hydrocarbon tests at operating that could contaminate the 2000 cfm (110%) on the charcoal HEPA filters of charcoal absorbers, j
banks shall show I 1% penetration.
perform the following:
c q
i c.
The results of laboratory carbon
filter banks. co verify leaktight y
methyl iodide removal efficiency-integrity.
0 when tested at 130 C and 95% R.H.
'k.
In-place test the charcoal absorber banks with halogenated hydrocarbon tracer to verify leaktight integrity, 4
A i
V 1
3.8/4.8-14a' Amendment No. 94 1
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QUAD-CITIES DPR 99 J
- 3) Remove one carbon test
'n canister from the charcoal absorber. Subject this sample to a laboratory analysis to verify methyl iodide removal efficiency.
b.. At leasteonce.pec.operaring. cycle, but not to exceed 18' months, the following conditions = shall be demonstrated:
- 1) Pressure drop across the combined filters is less than 6 inches I
of water at 2000 cfm (110%)
flow rate.
l
- 2) Operability of inlet heater demonstrates heater AT of 15 F.
i 3.
Postmaintenance Requirements 3.
Postmaintenance Testing l
t a.
After any maintenance or heating
,.a.
After any maintenance or testing j
that could affect the HEPA filter that could aff,ect the leaktighr'in '
or HEPA filter mounting frame tegrity of theiHEPA filters, perform O
leak-tight integrity, the results in-place DOP t'ests on the HEPA of the in-place DOP tests at 2000 filters' in accordance with Specifica-cfm (110%) on REPA filters shall tion 3.8.H.2.a.
~
show < 1% DOP penetration, b.
After any maintenance or testing b.
After 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 on the charcoal ad (110%) shall show < 1% penetration, sorbers in accordance with Specifi-cation 3.8.H.2.b.
n O
3.8/4.8-14b Amendment No,'94 J
..n
QUAD-CITIES DPR-E3 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 raactor through the main steamline to the main condenser.
The fission product radioactivity would be sensed by the main steamline radio-activity monitors which initiate isolation 3.8/4.8.F.
MISCELLANEOUS RADIOACTIVE MATERIALS.' 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.
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 General Design Criteria 60 of Appendix A to 10. CFR Parr 50.
l 3.8/4.8.H CONTROL ROOM AIR FILTRATION The purpose of these specifications is to assure availability of the control O room emergency air filtrations 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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3.8/4.8-19 Amendment No. 94 f
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UNITED STATES f
p, NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D. C. 20555
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1 COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated September 26, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized and safety of the public, and (ii) that such activities will be conducted in compliance with the C9 mission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by the addition of License Condition 3.L., and by changes to the Technical Specifications as. indicated in the attachment to this license amendment. Paragraph 2.C.(2) of Facility Operatino License No. DPR-29 is hereby amended to read as follows:
1
. (2) Technical Specifications
/
The Technical Specifications c'ontained in Appendices A and B, as revised.throuah Amendment No.
90, are hereby incorporated in the license. The licensee shalk'nperate the facility in accordance with the Technical Specificitions.'
New License Condition 3.L. is added to read as follows:
3.L.
Post-Accident Samplina A program will be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant chimney effluents, and containment 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 eauipment.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY OMMISSION i
i
.~ J John A. Zwolinski, Director RWR Project Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications 1
Date of Issuance:
June 10, 1986 9
8
+
{
ATTACHMENT TO LICENSE AMENDMENT NO. 90 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and conte.in marginal lines indicating the area of change.
REMOVE INSERT 11 11 3.2/4.?-3 3.2/4.2-3 3.2/4.2-4 3.2/4.2-4 3.2/4.2-5 3.2/4.2-5 3.2/4.2-8 3.2/4.2-8 3.2/4.2-15 3.2/4.2-15 3.2/4.7-15a 3.2/4.2-15a 3.2/4.2-15aa 3.7/4.2-15b
.3.2/4.2-15b 3.2/4.2-15c 3.2/4.2-15c 3.2/4.2-15d 3,7.4,2-15d 3.2/4.2-17 3.?/4.2-17 3.2/4.2-18 3.2/4.2-18 3.2/4.2-18a 3.2/4.?-19 3.2/4.2-19 3.8/4.8-20 3.2/4.?-20 t
3.8/4.8-14a 3.8/4.8-14b 3.8/4.8-19
QUAD CITIES DPR-3~0 TABLE OF CONTENTS (Cont'd)
Page 3.5/4.5-1 3.5/4.5 CORE CONTAINMENT COOLING SYSTEMS 3.5/4. 5-1 Core Spray Subsystems and the LPCI Mode of the RHR System A.
3.5/4.5-3 B.
Containment Cooling Mode of the RHR System 3.5/4.5-4 C.
HPCI Subsystem 3.5/4.5-5 D.
Automatic Pressure Relief Subsystems 3.5/4.5-6 Reactor Core Isolation Cooling System 3.5/4.5-6 E.
Minimum Core and Containment Cooling System Availability F.
3.5/4.5-7 G.
Maintenance of Filled Discharge Pipe 3.5/ 4. 5-8 Condensate Pump Room Flood Protection 3.5/4.5-9 H.
Average Planar Linear Heat Generation Rate (APLHGR)
I.
3.5/4.5-9 J.
Local LHGR 3.5/4.5-10 K.
Minimum Critical Power Ratio (MCPR) 3.5/4.5-11 3.5 Limiting Conditions for Operation Bases 3.5/4.5-16 4.5 Surveillance Requirements Bases 3.6/4. 6-1 3.6/4.6 PRIMARY SYSTEM BOUNDARY
- 3. 6/4. 6-1 A.
Thermal Limitations
- 3. 6/4. 6-1 B.
Pressurization Temperature 3.6/4.6-2 C.
Coolant Chemistry 3.6/4.6-3 D.
Coolant Leakage 3.6/4.6 l E.
Safety and Relief Yalves 3.6/ 4.6-4 F.
Structural Integrity 3.6/4.6-5 G.
Jet Pumps 3.6/4.6-5 Flow Mismatch Recirculation Pump (Snubbers) 3.6/4.6-5a H.
Shock Suppressors I.
3.6/4.6-8 3.6 Limiting Conditions for Operation Bases 3.7/4.7-1 3.7/4.7 CONTAINMENT SYSTEMS 3.7/4.7-1 A.
P-imary Containment 3.7/4.7-7 B.
Standby Gas Treatment System 3.7/4.7-8 C.
Secondary Containment 3.7/4.7-9 D.
Primary Containment Isolation Valves 3.7/4.7-11 3.7 Limiting Conditions for Operation Bases 3.7/4.7-15 4.7 Surveillance Requirements Bases 3.8/4.8-1 3.8/4.8 RADI0 ACTIVE EFFLUENTS 3.8/4.8-1 A.
Gaseous Effluents 3.8/4.8-6a B.
Liquid Effluents 3.8/4.8-9 C.
Mechanical Vacuum Pump 3.8/4.8-10 D.
Environmental Monitoring Program 3.8/4.8-13 E.
Solid Radioactive Waste 3.8/4.8-14 i
F.
Miscellaneous Radioactive Materials Sources 3.8/4.8-14a l
H.
Control Room Emergency Filtration System 3.8/4.8A Limiting Conditions for Operation and Surveillance 3.8/4.8-15 Req. Bases N
Amendment No. 90
QUAD-CITIES DPR-30 F.
Control Room Ventilation 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 floghigh toxic gas concentration, specified in Table 4.2-1.
high radiation in either of the reactor building ventilation exhaust ducts, or manually. Limiting conditions for operation shall be as indicated 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 sha.u 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 150 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 alaru/ 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 setpoint so it is acceptably conservative, m
V 3.2/4.2-3 Amendment No. 90
QUAD-CITIES DPR 30 2.
With one or more radioactive liquid effluent monitoring instruments inoperable, take the action shown in Table 3.2-5.
Exert best efforts to return tne 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 liciting 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 Caseous Effluent H.
Radioactive Caseous Effluent Instrumentation Instrumentation O.
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 alars/ trip setpoints shall instrument check, calibration, and be detergined in accordance with the ODC:1.
functional test operations at the frequency shown in Table 4.2-4 1.
With a radioactive 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-
. point so it is acceptably conservative.
(.A 3.2/4.2-4 Amendment No. 90
4 QUAD-CITIES DPR-30
^-
2.
With one or = ore radioactive gaseous effluent monitoring instruments inoperable, take the action shown in Table 3.2-e.
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.
(
l 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 l
4 to th2 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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'd 3.2/4.2-5 Amendment No. 90
0 QUAD-CITIES DPR-30 sa that none of the activity released during the refueling accident leaves the reactor
,rs 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 listec and the limiting conditions for operation on these syste=s 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-mation he can make logical decisions regarding postaccident recovery.
The specifications allow for postaccident instrumentation to be out of service for a psriod of 7 days. This period is based on the fact th'at several diverse instruments r.re 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, cnd on engineering judgnent.
The normal supply of air for the control room ventilation system Trains "A" and "B" j$
l outside the service building. In the event of an accident, this source of air may be required 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 air duct, signals which indicate an accident, i.e., high drywell pressure, low water 1svel, main streamline high flow, or high radiation in the reactor building ventilation duct, will cause isolation of the intake air to the control room. The above trip
,U signals result in i= mediate, 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 k / 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 oder threshold, so that the toxic chemical will not achieve toxicity limit con-ctntraticns 4n the Control Room.
The 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 instru=ents are provided to ensure that the alarms will occur prior to exceeding the itsics of 10 CFR 20.
es
'%.)
3.2/4.2-8 Amendment No. 90
QUAD-CITIES DPR ~-30 TABLE 3.2-4 POSTACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS (2)
Instrument Minimum Number Readout of Operable Location Number Channels (1)(3)
Parameter Unit 1 Provided h
1 Reactor pressure 901-5 1
0-1500 psig 2
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 Torus water level indicator 901-3
'l
-5 inches -
+5 inches (narrow range) 2(s)
Torus water level indicator 901-3 2
0-30 feet (vide range)
Torus water level sight glass 1
18 inch range (narrow range) 1 Torus pressure 901-3 1
-li inches Hg to 5 psig 2
Drywell pressure 901-3 1
-5 inches Hg to 5 psig 0 to 75 psig 2
0 to 250 psig 2
Drywell temperature 903-21 6
0-600*F 2
Neutron monitoring 901-5 4
0.1-10s CPS 2(4)
Torus to drywell 2
0-3 paid 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 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 Amendment No. 90
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- = e=
QUAD-CITIES l
D PR-3 0 i
Notes t
I 1.
Instraent. channels required during power operation to monitor postaccident conditions.
4 2.
Pr'ovisions are made for local supling and monitoring of drywell atmosphere.
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 i
exceptions to this requirement.
4.
From and af ter the date that ene of these parameters is reduced to one 4
j indication, continued operation is not permissible beyond thirty days unless such instruentation is sooner made operable. In the event that all indication l
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 i
be in a cold shutdown condition in twenty-four (24) hours.
5.
If the neber of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however, if the reactor is j
in a cold staatdown condition for longer than12 hours, it may not be started i
up until all position indication is restored.
In the evene that all position j
indication is lost on one or more valves and mach 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 paramet;er is reduced to either one 4
I narrow-range indication or one vide-range indication, continued reactor operation is not permissible beyond 30 days unless such instrument is sooner i
made operable. In the event that either all narrow-range indication or all I
wide-range indication is disabled, continued reactor operation is not permis-l
'l 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 staatdown 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 />.
5 7.
With less than the minimum neber of operable channels, initiate the pre-planned alternate method of monitoring this parasater 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.
prepara and submit a special report to the NRC within 30 days following the event, outlining the action taken, the cause of the inoperability, i
and the plans and schedule for restoring the syste to operable status.
i 4
l 3.2/4.2-15a Amendment No. 90 l
1
-- : r- :
- - _=,:- : : -
OUAD CITIES DV R-30 8.
From and af ter the date that one of the dryvell hydrogen monitors becomes inoperable, continued reactor operation is permissible.
a.
If both dryvell hydrogen monitors are inoperable, continued reactor operation is permissible for up to 30 days provided that during this time the HRSS hydrogen moaitoring capability for the drywell is operable.
b.. If all dryvell hydrogen monitoring capability is lost, continued reactor operation is permissible for up to 7 days.
l t
4 3.2/4.2-15 an Amendment No. 90 l
~my
QUAD-CITIES DPR-30 T&ble 3.2-3 RADICACTIVE LIQU10 EFFLUENT MONITORING INSTRUMENTATION Minimum'No.
of Operable Total No.
Channels of Channels Parameter Action (1) 1 I
Service Water A-Effluent Gross Activity Monitor I
1 Liquid Radwaste C
Effluent Flow Rata Monitor
~
I I
Liquid Radw'aste 8
i Effluent Gross Activi ty Monitor I
l Notes:
Action A( With 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 gamma activity at an LLD of less than or equal to 10~7 uCi/ml.
Action B:
With less than the minimum number of coerable 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 4.8.5.1., and at Teast 2 members of the facility staff independently verify the-release calculation and discharge valving.
O the rw i s e, suspend release'of radioactive efflu-ents via this pathway.
Actica C:
With less than the minimum nu=her of ocerable channels, releases via this pathway may 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.
Fume curves may ce utilized to estimate flow.
3.2/4.2-155 Amendment No. 90
....t_..
QUAD-CITIES DPR-30 Table 3.2-6 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION' l
Minimum No.
1 of Operable Total No.
Channels (1) of Channels Parameter Action (2) 4 l
1 2-,
SJAE Radiation D
i Monitors i
1 2
Main Chimney Noble A
Gas Activity Monitor 1
1 Main Chimney Iodine C
j Sampler i
1 1
Main Chimney C
Particulate Sampler 1
1 Reactor Bldg. Vent B
t Sampler Flow Rate Monitor i
1 1
Reactor Bldg. Vent C
i Iodine Sampler I
1 1
Reactor Bldg. Vent C
[
{
Particulate Sampler 1
1 Main chimney Sampler B
N Flow Rate Monitor l
1 1
Main Chimney Flow B
l Rate Monitor l
1 2
Reactor Bldg. Vent E
J Noble Gas Monitor i
i 1 1
Main Chimney F
]
High Range Noble I
Gas Monitor Notes l
(1) For SJAE monitors, applicable during SJAE operation. For other i
instrumentation, applicable at all times.
l (2) Action As With the number of operable channels less than the minimum j
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 />.
I Action 8: With the number of operable channels less than tho' minimum required, effluent ~ releases via this pathway may continue 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 />.
3.2/4.2-15c Amendment No. 90 l
.... - ~
. _., _ _ _ _ _ ~. _. _. -.
QUAD-CITIES DPR. 30 Action C: With less than the minimum channels operable, effluent releases via this pathway may continue protided samples are continuously collected with auxiliary sampling equipment, as required in Table 4.8-1.
Action Dr With less than the minimurchannels. orarable, gases free the main condenser off gas system may be released to the-environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prev'.ded 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 />.
With less.than the minimum channels operable.,.immediately Action-E 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 Ccamission 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.
4 s
3.2/4.2-15d Amendment No. 90
QUAD-CITIES l
DPR-30 TA8LE 4.2-1 (cont'd) i Instrument Instrument Functignal Channel Testt2J Ca11bration(2)
Instrugkgj Chec HPCI Isolation 1.
Steamline hign flow (1)(9)
Once/3 months None i
l 2.
Steamline area high temperature Refueling outage Refueling outage None j
3.
Low reactor pressure (1)
Once/3 months None Reactor Building Ventilation System Isolation and Standby Treatment System Initiation
]
1.
Refueling floor radiation (1)
Once/3 months Once/ day monitors l
Steam Jet Air Ejector Off-Gas Isolation 1.
Off-gas radiation monitors (1) (4)
Refueling outage Once/ day J
Control Room Ventilation System Isolation 1.
Reactor low water level (1)
Once/3 months Once/ day 2.
Drywell nigh pressure (1)
Once/3 months None 3.
Main steamline high flow (1)
Once/3 months Once/ day 4.
Toxic gas analyzers (chlorine, Once/ month once/18 months once/ day ammonia,sulphurdioxide)
Notes:
1.
Ingtially once per month until exposure hours (M as defined on Figure 4.1-1) are 2.0 X 10 ; thereaf ter, according to Figure 4.1-1 with an interval not less than 1 month nor more than 3 months. The compilation of instrument failure ratd data may include data obtained from other boiling water reactors for whch the same design instrument operates in an environment 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 tripped.
1 3.
inis instrumentation is excepted from the functional test definition. The function test j
shall consist of injecting a simulated electric signal into the measurement channel.
4.
This instrument channel is excepted from the functional test definitions and shall be 4
caliorated using simulated electrical signals once every 3 months.
l S.
Functional tests shall be perfonned before each startup with a required frequency not to exceed once per week. Calibrations shall be performed during each startup or 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 perfonned as specified in the applicable section for 3
these sytems.
8.
Functional tests shall include verification of operation of the degraded voltage 5
minute timey and 7 second inherent timer.
9.
Vertf tcation of the time delay setting of 3 4_ t3 0 seconds shall be performed during 1
each refueling outage.
l 3.2/4.2-17 Amendment No. 90
~-
QUAD-CITIES DPR. 30 TABLE 4.2-2 POSTACCIDENT MONITORING INSTRUMENTATION SURVEILIANCE REQUIREMENTS 2
Ins trtanent Minimum Number Readout cf Operable Location Chmnelse Parameter Unit 1 Calibration Instrument Check 1
Reactor pressure 90 1-5 Once every once per day 3 months 1.
Reactor water-level 901-3 Once every Once per day j
3 months 1
Torus water temperature 901-21 Once every once per day i
3 months 1
Torus air temperature 901-21 Once every once per day 3 months i
j Torus water level indicator 90 1-3 Once every Once per day (narrow range) 3 months q
, 2 Torus water level indicator 90 1-3 Once every once per 31 days l
(vide range) 18 months i
Torus water level sight glass N/A None t
1 Torus pressure 90 1-3 Once every Once per day 3 months 2
- Drywell pressure 90 1-3 Once every Once per day 3 months 2
Drywell temperature 901-21 Once every once per day 3 months i
2 Neutron monitoring 901-5 Once every once per day 3 months i
i 2
Torus to dryvell Once every None i
differenti.t1 pressure 6 months 1
Drywell Hydrogen concentration 901-55,56 Once every once per 31 days 3 months l
2 Drywell radiation monitor 901-55,56 Once every**** Once pef-31 days 18 months Main steam RV 901-21 Once per position, acoustic 31 days monitor 2/ valve Main stami RV 901-21 Once every once per 4
- position, 18 months 31 days I
tempe rature -
b monitor 3.2/4.2-18 Amendment no. 90 I
,w-
4,
-r y-.g-.
QUAD CITIES DPR-30 Instrument Minimum Number Readout cf Operable Location Chenn els*
Parameter Unit 1 Calibration Instrument Check Main stean SV 901-21 Once per position, acoustic 31 days monitor
.1:
2/vcive Main stean S7 901-21 Once every Once.per
~
- position, 18 months 31 days temperatu re monitor
- Instrtament 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 of the detector below 10 R/hr with Ms 10 R/hr; and a one-point calibration check the detector, for range decades abo:.
a installed or portable gamma source.
s, 3.2/4.2-18a.
Amendment No. 90
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 (1)
Liquid Radwaste D
R Q (7)
(6) l Effluent Gross Activity Monitor Service Water D
R Q (7)
R Effluent Gross Activity Monitor Liquid Radwaste (4)
R NA NA Effluent Flow Rate Monitor Notes:
(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 i
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) Caliabration 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 associated with the monitor chassis.
3.2/4.2-19 Amendment No. 90
QUAD-CITIES DPR-30 Table 4.254' RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibra-Functional Source Instrument Mode (2)
Check (1) tion (1) (4)
Test (1) (3 )
Check (1)
Main Chimney Noble *Cas+
BI D.
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 Rate Monitor Main Chimney Flow Rate B
D R
Q NA Monitor Reactor Bldg. Vent B
D R
Q Q
j 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 t
l Main Chimney High Range B
D(5)
R Q
M Noble Gas Monitor N
Notes (1)
D = once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i
M = once per 31 days l
Q = once per 92 days R = once per 18 months 1
(2) A = during SJAE operation i
B = at all times (3) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs,. it, any, of the following conditions, exist,. wiresas applicable i
a.
Instrument indicates levels above the alarm setpoint b.
Circuit failure c.
Instrument indicates a downscale failure 4
d.
Instrument controls not set in OPERATE mode j
(4)
Calibration shall include performance of a functional test.
(5)
Instrument check to verify operability of the instrumentr that.thh instrument is in-place and functioning properly.
1 (6) runctional test. shall be performed on local switches providing low flow alarm.
i 3.2/4.2-20
.... _ _ _. em.,ndment No 90...._.
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QUAD-CITIES DPR-30 Y
H.
Control Room Emergency Filtration l
Co[,:rolRoomEmergencyFiltration H.
Sys~cem 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 cont =f n==nt' integrity-1p therheaters.operakles required, except as specified in Sections 3.8.H.1.a. and b.
a.
After the control room emergency filtration system is made or j
found to be inoperable for any j
reason, reactor operation and
]
fuel handling are permissible l
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 t
the 14 days, the reactor shall l
be placed in a condition for which the control room emergency filtration system is not required f
in accordance with Specification i
3.7.C.1.a. chrough d.
)
b.
Specification 3.8.H.1.a. above p
iv does not apply during performance
}
or post-maintenance testing, or during removal of the charcoal i
i test canister.
1 2.
Periodic Performance Requirements 2.
Performance Raquirement Tests N
j 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 1%
following painting, fire, or toxic i
chemical release in any ventilation
]
zone communicating with the intake i
b.
The results of in-place of the system while the system is halogenated hydrocarbon tests at operating that could contaminate the l
2000 cfm (110%) on the charcoal HEPA filters of charcoal absorbers, banks shall show 1 1% penetration, perform the following:
c.
The results of laboratory carbon
filter banks. to verify leaktight methyl iodide removal efficiency-integrity when tested at 130'C and 95% R.H.
2.
In-place test the charcoal l
absorber banks with halogenated hydrocarbon tracer to verify leaktight integrity, i
n l
i 3.8/4.8-14a Amendment No. 90 1
i L
=_
QUAD-CITIES DPR-30
- 3) Remove one carbon test O
canister from the charcoal
'~
absorber. Subject this i
sample to a laboratory analysis to verify methyl iodide removal efficiency.
b.. Ar leaan once pec. operating cycle, but nor to exceed 18' months, the fallowing conditione,shall.be demonstrated:
i
- 1) Pressure drop across the combined filters is less than 6 inches t
of water at 2000 cfm (110%)
flow rate.
- 2) Operability of inlet heater 0
demonstraces heater AT of 15 F.
3.
Postmaintenance Requirements 3.
Postmaintenance Testing l
a.
After any maintenance or heating a.
After any maintenance or testing that could affect the HEPA filter that could affect the leaktight in-j p
or HEPA filter mounting frame tegrity of the HEPA filters, perform V
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 1 1% DOP penetration.
b.% After any maintenance or testing b.
After any ma'intenance or testing j
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-l hydrocarbon tests at 2000 cfm carbon tests o'n the charcoal ad-(110%) shall show 11% penetration.
sorbers in accordance with Specif1-cation 3.8.H.2.b.
i 1
i e,
G-I i
3.8/4.8-14b Amendment No.'90 i
i, i
}
_.., - _.,.. _. ~,.... _ - _
=.
QUAD-CITIES DPR-30 OV 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-activity-monitors which initiate isolatiotr.
3.8/4.8.F.
MISCELLANEOUS RADIOACTIVE MATERIALS: 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 sourcesirequiring leak testing,.
l including alpha emitters, is based on 10 CTR 70.39 (c) limits for plutonium.
3.8/4.8.E.
SOLID RADIOACTIVE WASTE a
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 General-Design Criteria 60 of Appendix A to 10 CFR Part 50.
3.8/4.8.H CONTROL ROOM AIR FILTRATION The purpose of those specifications is to assure availability of the control O room emergency air filtrations 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.
i i,
1 i
i i
d i
n
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Amendment No. 90 3.8/4.8-19 i
l i
_