ML20085D435
| ML20085D435 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/07/1991 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20085D433 | List: |
| References | |
| NUDOCS 9110160180 | |
| Download: ML20085D435 (14) | |
Text
._
ENCLOSURE (A)
QUAD CITIES UNITS 1 &
2 DPR-29 & DPR-30 TECHNICAL SPECIFICATIONS APPENDIX A TABLE OF CONTENTS E!A's8as!Ma886 P
_ ~_
QUAD CITIES UNITS 1 &2 DPR-29 & DPR-30 TECHNICAL BPECIFICATIQHR APPENDI.K_A 1
TAD 1R_,97 CONTENTS RECTXQH _
TITLE EAQE 1.0 DEFINITIONS 1.0-1 1.1/2.1 FUEL CLADDING INTEGRITY
. 1/2.1-1 1.1 Safety Limits
- 1..'./ 2.1-1 A.
Theraa*. ' de r
.igh Pressurs 1.1/ 2..t-1 and High rios B.
Thet'41 PoWou av wtepsure 1.1/ 1.1-3 or Low Flow C.
Power Transient 1.1/2.1-4 D.
Reactor Vessel Wate< 7evel 1.1/2.1-5 2.1 Limiting Safety System Settings 1.1/2.1-1 A.
Neutron Flux Trip Settings 1.1/2.1-1 B.
APRM Rod Block Setting 1.1/2.1-3 C.
Other Reactor Protection 1.1/2.1-4 System Instrumentation Setpoints D.
Reactor Low Water Level ECCS 1.1/2.1-5 Initiation E.
Main Ste.am Line Low Pressure 1.1/2.1-6 Isolation 1.1 Safety Limit cases B 1.1/2.1-1 2.1 Limiting Safety System Setting B 1.1/2.1-6 Dases 1.2/2.1 REACTOR COOLANT SYSTEM 1.2/2.2-1 1.2 Safety Limit 1.2/2.2-1 A.
Reactor Coolant System 1.2/2.2-1 Pressure Setting 2.2 -Limiting Safety Systou Settings 1.2/2.2-1 A.
Reactor Coolant System High 1.2/2.2-1 Pressure Scram Setting
-. - - = -
QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 B.
Primary System Safety Valve 1.2/2.2-1 Settings 1.2 Safety Limit Bases B 1.2/2.2-1 2.2 Limiting Safety System Setting B 1.2/2.2-3 Bases 3.0/4.0 APPLICABILITY 3.0/4.0-1 3.0 Limiting Conditions for Operation 3.0/4.0-1 4.0 Surveillance Requircments 3.0/4.0-3 3.0 LCO Bases B 3.0/4.0-1 4.0 Surveillance Requirement Bases B 3.0/4.0-6 3.1/4.1 REACTOR PROTECTION SYSTEM 3.1/4.1-1 A.
Reactor Protection System 3.1/4.1-1 B.
APRM Scram and Control Rod Block 3.1/4.1-2 Flow Biased Upscale Setpoints 3.1 LCO Bases B 3.1/4.1-1 4.1 Surveillance Requirement Bases B 3.1/4.1-6 3.2/4.2 PROTECTIVE IN3TRUMENTATICN 3.2/4.2-1 A.
Primary Containment Isolation 3.2/4.2-1 Functions B.
Core and Containment Cooling 3.2/4.2-3 Systems Initiation and Control C.
Control Rod Block Actuation 3.2/4.2-4 D.
Refueling Floor Radiation 3.2/4.2-5 Monitors E.
Postaccident Instrumentation 3.2/4.2-6 F.
Control Room Ventilation Systera 3.2/4.2-6 Isolation G.
Steam Jet Air Ejector (SJAE) 3.2/4.2-9 Radiation Monitors 3.2 LCO Bases B 3.2/4.2-1 4.2 Surveillance Requirement Bases B 3.2/4.2-7 3.3/4.3 REACTIVITY CONTROL 3.3/4.3-1 A.
Shutdown Margin 3.3/4.3-1 B.
Reactivity Anomalies 3.3/4.3-2 C.
Control Rod Operability 3.3/4.3-2
. ~-.
4 QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 K.
Maintenance of Filleo Dischargo 3.5/4.5-13 Pipes for RCIC and IIPCI L.
Condensato Pump Room Flood 3.5/4.5-13 Pr'.toction H.
Avtrage Planar LilGR 3-5/4.5-15 N.
Local LilGR 3.5/4.5-16 O.
Minimum Critical Power Ratio 3.5/4.5-16 (MCPR) 3.5 LCO Bases B 3.5/4.5-1 4.5 Surveillance Requirement Bases B 3.5/4.5-12 3.6/4.6 PRIMARY SYJTEM 9OUNDARY 3.6/4.6-1 A.
Th'ermal Limitations 3.6/4.6-1 B.
Pressurization Temperature 3.6/4.6-2 C.
Coolant Chemistry 3.6/4/6-3 D.
Coolant Specific Activity 3.6/4.6-5 E.
Coolant Leakage 3.6/4.6-6 F.
Coolant Leakage Detection Systems 3.6/4.6-7 G.
Safety and Relief Valvoc 3.6/4.6-7 H.
Structural Integrity 3.6/4.6-8 I.
Jet Pumps 3.6/4.6-9 J.
Recirculation Pump Flow 3.6/4.6-11 Limitations K.
Idle Recirculation Loop Startup 3.6/4.6-13 L.
Shock Suppressors (Snubbers) 3.6/4.6-14 3.6 LCO Bases B 3.6/4.6-1 3.7/4.7 CONTAINMENT DYSTEMS 3.7/4.7-1 A.
Primary Containment Integrity 3.7/4.7-1 B.
Primary Containment Icakage 3.7/4.7-1 C.
Primary Containra t Airlock 3.7/4.7-4 D.
Suppression Chamber 3.7/4.7-5 E.
Drywell-Suppression Chamber 3.7/4.7-8 Differential Pressure F.
Primary Containment Isolation 3.7/4.7-10 Valves G.
Pressure Suppression Chamber-3.7/4.7-12 Drywell Vacuum Breakers H.
Pressure Suppression Chamber-3.7/4.7-14
. Reactor Building Vacuum Breakers I.
Secondary containment Integrity 3.7/4.7-14 J.
Secondary Centainment Automatic 3.7/4.7-15 Isolation Dampers K.
Standby Gas Treatment System 3.7/4.7-17 L.
Primary Containment Oxygen 3.7/4.7-19 Concentration
a e
QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 3.7 LCO Bases B 3.7/4.7-1 4.7 Surveillance Requirement Bases B 3.7/4.7-11 3.8/4.8 RADIOACTIVE EF7LUENTS 3.8/4.8-1 A.
Explosive Gas Mixture 3.8/4.8-1 t
D.
Main Condenser 3.8/4.8-2 C.
Mechanical Vacuum Pump 3.8/4.8-3 1
D.
Scaled Source Contamination 3.8/4.8-4 E.
Control Room Emergency Filtration 3.8/4.S-5 System 3/4.8 Radioactive Effluents Bases B 3.8/4.8-1 3.9/4.9 AUXILIARY ELECTRICAL SYSTEMB 3.9/4.9-1 A.
A.C.-Sources - Operating 3.9/4.9-1 B.
A.C. Sources - Shutdown 3.9/4.9-4 C.
Station Batteries - Operating 3.9/4.9-5 D.
Station Batteries - Shutdown 3.9/4.9-7 E.
Onsite Powcr Distribution Systems 3.9/4.9-8
- Operating F.
Onsite Power Distribution Systems 3.9/4.9-9
- Shutdown G.
Reactor Protection Bus Power 3.9/4.9-10 Monitoring System 3.9 LCO Bascs B 3.9/4.9-1 4.9 Surveillance Requirement Lases B 3.9/4.9-5 3.10/4.10 REFUELING 3.10/4.10-1 A.
Refueling Ir.terlocks 3.10/4.10-1 B.
Core Monitoring 3.10/4.10-2 C.
Fuel Storage Pool Water Level 3.10/4.10-4 D.
Control Rod and Control Rod Drive 3 10/4.10-4 Maintenance
- Single Control J
Rod Removal i
E.
Extended Core Maintenance -
3.10/4.10-6 I
Multiple Centrol Rod Removal F.
Spent Fuel Cask Handling 3.10/4.10-7 G.
Control Rod Position 3.10/4.10-8 H.
Communications 3.10/4.10-9 I.
Water Level - Reactor Vessel 3.10/4.10-9 3/4.10 Refueling Bases B 3.10/4.10-1 3.11/4.11 Deleted 3.12/4.12 Deleted f
j
QUAD CITIES Ull1TS 1 & 2 DPR-29 & DPR-30 5.0 DESIGN FEATURES 5.0-1 6.0 ADMINISTRATIVE CONTROLS 6.1-1 6.1 Organization, Moview, _
6.1-1 Investigation, and Audit 6.2 Plant Operating Proceduros and 6.2-1 Progrows 6.3 Reportablo Event Action 6.3-1 6.4-Action to bo Taken in the Event a 6.4-1 Safety Limit is Exceeded 6.5 Plant Operating Records 6.5-1 6.6. Reporting Requirements 6.6-1 6.7 Environmental Qualificatiott 6.7-1 6.8 Offsite Doso Calculation Manual 6.8-1 (ODCM) 6.9 Process Control Program (PCP) 6.9-1 6.10 Major Changes to Radioactivo 6.10-1 Waste Treatment Systems (Liquid, Gascous, Solid)
I f
l I
t I
T l
QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 IRCHN LCA k_S H.01EICATIQRR AEPINDILA LIST QE_TARLER I
HDEhMK Title EA9A 3.1-1 Reactor Protection System (Scram) 3.1/4.1-4 Instrumentation Requirements 4.1-1 Roactor Protection S',..cm (Scram) 3.1/4.1-9 Instrumentation Char ro.1 Functional Test Requiroments 4.1-2 Reactor Protection System (Scram) 3.1/4.1-13 Instrumer.tation Channel Calibration Rog irements 3.2-1 Instrumentation that Initiates Primary 3.2/4.2-10 Containment Isolation Functions 3.2-2 Instrumentation that Initiates or 3.2/4.2-14 Controls the Coro and Containment cooling Systems 3.2-3 Instrumentation that Initiates Rod 3.2/4.2-17 Block 3.2-4 Postaccident Monitoring 3.2/4.2-21 Instrumentation Requirements 4.2-1 Minimum Test and Calibration Frequency 3.2/4.2-24 for Coro and Containment Cooling Systems Instrumentation, Rod Blocks, and Isolations 4.2,
Postaccident Monitoring 3.2/4.2-30 Instrumentation Survoillance Requirements 4.6-1 Revised Withdrawal Schedule for Quad 3.6/4.6-22 Cities Units 1 & 2 4.6-2 Snubber Visual Inspection Interval 3.6/4.6-23 3.7-1 Primary Conta!.nment Isolation 3.7/4.7-21 t
i
QUAD CIT 1.S UllITS 1 & 2 DPR-29 & DPR-30 TECH 1U_ CAL _0RClELCAT1011a AEEZURIX_A LLET_QF FIGEP&E Mumbatt Elgitta Engo 2.1-1 APRM Flow Reference Scram and APRM Rod 1.1/2.1-7 Block Settings 2.1-2 APRM Flow Bias Scram Relationship to 1.1/2.1-8 Normal Operating Conditions 3.4-1 Sodium Pentaborate Solution 3.4/4.4-4 Temperaturo Requirements
- 3. 6+ 1 Minimum Temperaturo Requirements por 3.6/4.6-19 Appendix G of 10 CFR 50 3.6-2 Minimum Reactor Pressurization 3.6/4.6-20 Temperature 4.6-1 Chloride Stress Corrosion Test Resultu 3.6/4.6-21 at 500 dog F 4
ENCLOSURE (B)
)
QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 TECHNICAL SPECIFICATIONS APPENDI-X B ENVIRONMENTAL PROTECTION PLAN (NON - R ADIOLOGICAL) w -'
ve w
,+y
,ww w-v w-
..se, y--n----
-e p-
'm my e-g
-,v'+--
I APPENDIX B TO FACILITY OPERATING LICENSE NOS. DPR-29 & DPR-30 QUAD CITIES STATION UNITS 1&2 COMMONWEALTH EDISON COMPANY DOCKET NOS. 50-254 AND 50-265 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL) r' l
l _-
QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 1.0 Objectives of the-Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protection of environmental values during construction and operation of the nuclear facility.
The principal objectives of the EPP are as follows:
(1)
Verify that the plant is operated in an environmentally acceptat manner, at established by the FES and other NRC eny_
imental impact assessments.
(2)
Coordinate C requirements and maintain consistency with other
- Federal, State and local requirements for environmental protection.
(3)
Keep NRC informed of the environmental effects of facility' construction and operation and of actions taken to control those effects.
Environmental concerns identified in the FES which relate O
to. water quality matters are regulated by way of the licensee's National Pollutant Discharge Elimination
-(NPDES) permit, issued by the Illinois Environmental Protection Agency.
e l
i~
11 l
_ _, _. -. _ ~. _ _
QUAD CITIES UNITS 1-& 2 DPR-29 & DPR 30 2.0 Consistency Requirements 1
2.1 Plant Design and Operation i
i The licensee may make changes in station design or operation or perform tests or experiments affecting the environment provided such changes, tests or experiments do not involve an unroviewed environmental question.
Changes in plant design or operation or pcrformance of tests or experiments which do not af fect the environment i
are not subject to this requirement. Activit.ios governed by Section 2.3 are not subject to the requirements of this Section.
Before engaging in unauthorized construction or open tional activities which may af fect the environment, the licensee shall prepare and record an environmental evaluation of such activity.1 When the 'ovaluation indicates that such activity involves and unreviewed l
environmental question, the licensco shall provide a l
written evaluation of such activities and obtain prior l-approval from the NRC.
A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final environmental statement (FES) as modified by staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change l
in effluents or power level (in accordance with-10 CFR I
Part 51.5 (b) (2)) or (3) a matter. not previously reviewed I
and evtluated in the documents specified in-(1) of this Subsection, which may have significant adverse environmental impact.
The licensee shall maintain records of changes in l
facility design or operation and of tests and experiments L
. carried out pursuant to this Subsection.
These records shall include a. written evaluation which provides bases for the determination that the change, test or experiment l-1 L
Activitics are excluded - from this requirement if all L
measurable nonradiological effects are confined to the l
on-site areas previously disturbed during site preparation and plant construction.
2-1 l
l
.. ~
~. -
-c_-
QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 does not involve an unreviewed environmental questien.
2.2 Reporting Related to the NPDES Permits and State Certifications Violations of the NPDES Permit or Stato c4.rtification (pursuant to Section 401 of the Clean Water Act) shall be reported to the NRC by submittal of copics of the reports required by the NPDES Permit or certification.
The licensee shall also provide the NRC with copies of the results of environmental studies at the same time they are submitted to the permitting agency.
Changes and additions to the NPDES Permit or the State certification shall be reported to the NRC within 30 days following the date the change is approved.
If a
permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.
The NRC shall be notified of changes to the offective NPDES Permit proposed by the licens.e by providing NRC with a copy of the proposed change at the same time it is submitted to the permitting agency.
The licensee shall provide the NRC a copy of the application for renewal of the NPDES Permit at the same time the application is submitted to the permitting agency.
2.3 Changes Pequired for Compliance with Other Environmental Regulations Changes in plant design or operation and performance of tests or experiments which are required to achieve compliance with other
- Federal, State, or lo':al environmental regulations are not subject
&L the requirements of Section 2.1, 2-2
t t.
QUAD CITIES UNITS 1&2 DPR-29 & DPR-30 3.0 Environmental Conditions s.
3.1 Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant envitcntner impact causally re'.ated to station operation shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a written report within 30 days.
No routine monitoring programs are required to implement this condition.
The written repo n,shall (a)
- describe, analyze, and evaluate the event, ncluding extent and magnitude of the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the act >n taken to correct the reported event, -(d) indicate e
corrective action taken to preclude repetition of the event and to prevent similar occurrences involving
- systems, and (e) ind.icate the similar components agencies notifie6.tv s heir preliminary resI.nses.
Events reportabl.
.inder this subcection which also require reports te ther Federal, State or 1.ocal agen:les shall be report.m in accordance with those reporting requirements it lieu of the rcquirements of this subsection.
The NRC shall be provided a c(.2. of such repcrt at the same time it is submitted to the other agency.
The follo..ing are uamples of unusual or important events: excesetve bird impaction events; onsite plant or animcl disease outbreaks; mortality or unusual occurrence ut any species protected by th, Endangered Species Act of 1973; unusual fish 'Aills; incraase in nuit.ance organisms or conditions; and unanticipated or emergency discharge of waste water or chemical substances.
3-3 I
___________- _____________ _