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{{#Wiki_filter:-- - - -ATTACHMENr -*-** .. --* - -- -- -
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Consumers Power *company Palisades Plant Docket 50-255 PROPOSED PAGES PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST ALLOWABLE QUANTITY.OF SOURCE          MATERI~L June 20, 1986
Consumers Power *company Palisades Plant Docket 50-255 PROPOSED PAGES PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST ALLOWABLE QUANTITY.OF SOURCE          MATERI~L June 20, 1986 10 Pages TSP0686-0097-NL04
_ .......
10 Pages TSP0686-0097-NL04


                             * -- -* - UNITED* STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC      20555 CONSUMERS POWER COMPANY (Palisades Plant)
                             * -- -* - UNITED* STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC      20555 CONSUMERS POWER COMPANY (Palisades Plant)
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: 1. Provisional Operating License No DPR-20 applies to the Palisades Plant, a pressurized, light water moderated and cooled reactor, and electric generating equipment (the facility). The facility is located in Covert Township on*the Consumers Power site in Van Buren County, Michigan, and is described in the "Final Safety Analysis Report", as supplemented and amende*d.
: 1. Provisional Operating License No DPR-20 applies to the Palisades Plant, a pressurized, light water moderated and cooled reactor, and electric generating equipment (the facility). The facility is located in Covert Township on*the Consumers Power site in Van Buren County, Michigan, and is described in the "Final Safety Analysis Report", as supplemented and amende*d.
: 2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Power Company (the licensee):
: 2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Power Company (the licensee):
A. Pursuant to Section 104b of the Atomic Energy Act of 1954, as amended (the Act), and 10 CFR Part50, "Licensing of Production and Utilization Facilities~, to po~sess, use and operate the facility as a utilization facility at the designated location; B. Pursuant to the Act and lO CFR Part 70, "Special Nuclear Material", to receive, possess and use 15,000 kilograms of Uranium-235 and 96 grams of encapsulated plutonium-beryllium in connection with operation of the facility; C. Pursuant to the Act. and 10 CFR Part 30, "Rules of General Applicability of Licensing of Byproduct Material", to receive, possess and use in connection with operation of the facility 1500 curies of Polonium~210 as two.sealed sources not to exceed 750 curies each, 1000 curies of Cesium~137 as multiple sealed calibration sources and up to 50~ millicuries per nuclide of any byproduct material with Atomic Numbers 3 to 83, inclusive, without restriction to chemical and physical form to a total of 10 curies; TSP0686-0097-NL04
A. Pursuant to Section 104b of the Atomic Energy Act of 1954, as amended (the Act), and 10 CFR Part50, "Licensing of Production and Utilization Facilities~, to po~sess, use and operate the facility as a utilization facility at the designated location; B. Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material", to receive, possess and use 15,000 kilograms of Uranium-235 and 96 grams of encapsulated plutonium-beryllium in connection with operation of the facility; C. Pursuant to the Act. and 10 CFR Part 30, "Rules of General Applicability of Licensing of Byproduct Material", to receive, possess and use in connection with operation of the facility 1500 curies of Polonium~210 as two.sealed sources not to exceed 750 curies each, 1000 curies of Cesium~137 as multiple sealed calibration sources and up to 50~ millicuries per nuclide of any byproduct material with Atomic Numbers 3 to 83, inclusive, without restriction to chemical and physical form to a total of 10 curies; TSP0686-0097-NL04


PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A
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PALISADES PLANT TECHNICAL SPECIFICATIONS
PALISADES PLANT TECHNICAL SPECIFICATIONS
                                                                        *
                                     . TJiaLE OF *CONTENTS - .APPENDIX A
                                     . TJiaLE OF *CONTENTS - .APPENDIX A
... --. SECTION - ------ --*---                      DESCRIPTION-                      PAGE NO 4.0                    SURVEILLANCE REQUIREMENTS                              4-1 4 .1                  INSTRUMENTATION AND CONTROL                            4-1 Table 4.1.1      Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System                    4-3 Table 4.1. 2    Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls                            4-6 Table 4.1.3      Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls                                            4-10 4.2                  EQUIPMENT AND SAMPLING TESTS                            4-13 Table 4.2.1      Minimum Frequencies for Sampling Tests                  4-14 Table 4.2.2      Minimum Frequencies for Equipment Tests                4-15 Table 4.2.3      HEPA Filter and Charcoal Adsorber Systems              4-15c 4.3                  SYSTEMS SURVEILLANCE                                    4-16 Table 4.3.1      Primary Coolant System Pressure Isolation Valves        4'.""19 Table 4.3.2      Miscellaneous Surveillance Items                        4-23 4.4                  PRIMARY COOLANT SYSTEM INTEGRITY TESTING                4-24 4.5                  CONTAINMENT TESTS                                      4-25 4.5.1              Integrated Leakage Rate Tests                          4-25 4.5.2              Local Leak Detection Tests                              4-27 4.5.3              Recirculation Heat Removal Systems                      4-28 4.5.4              Surveillance for Prestressing System                    4~29 4.5.5              End Anchorage Concrete Surveillance                    4-30 4.5.6              Liner Plate Surveillance                                4-31 4.5.7              Penetrations Surveillance                              4-32 4.5.8              Dome Delamination Surveillance                          4-32a 4.6                  SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS    4-39.
... --. SECTION - ------ --*---                      DESCRIPTION-                      PAGE NO 4.0                    SURVEILLANCE REQUIREMENTS                              4-1 4 .1                  INSTRUMENTATION AND CONTROL                            4-1 Table 4.1.1      Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System                    4-3 Table 4.1. 2    Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls                            4-6 Table 4.1.3      Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls                                            4-10 4.2                  EQUIPMENT AND SAMPLING TESTS                            4-13 Table 4.2.1      Minimum Frequencies for Sampling Tests                  4-14 Table 4.2.2      Minimum Frequencies for Equipment Tests                4-15 Table 4.2.3      HEPA Filter and Charcoal Adsorber Systems              4-15c 4.3                  SYSTEMS SURVEILLANCE                                    4-16 Table 4.3.1      Primary Coolant System Pressure Isolation Valves        4'.""19 Table 4.3.2      Miscellaneous Surveillance Items                        4-23 4.4                  PRIMARY COOLANT SYSTEM INTEGRITY TESTING                4-24 4.5                  CONTAINMENT TESTS                                      4-25 4.5.1              Integrated Leakage Rate Tests                          4-25 4.5.2              Local Leak Detection Tests                              4-27 4.5.3              Recirculation Heat Removal Systems                      4-28 4.5.4              Surveillance for Prestressing System                    4~29 4.5.5              End Anchorage Concrete Surveillance                    4-30 4.5.6              Liner Plate Surveillance                                4-31 4.5.7              Penetrations Surveillance                              4-32 4.5.8              Dome Delamination Surveillance                          4-32a 4.6                  SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS    4-39.
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Proposed.
Proposed.
PAL TC
PAL TC
* PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A
 
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A
--SECTION                                  *DESCRIPTION * -                  --PAGE NO 4.0                    SURVEILLANCE REQUIREMENTS (Continued) 4.24.6            Gaseous Waste System                                  4-91 4.24.7            Solid Radioactive Waste                                4-91 4.24.8            Total Dose                                            4-91 Table 4 .24-1. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements          4-92 Table 4.24-2  Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements          4-93 Table 4.24-3  Radioactive Liquid Waste Sampling and Analysis Program                                            4-95 Table 4.24-5  Radioactive Gaseous Waste Sampling and Analysis Program                                            4-97 5.0                    DESIGN FEATURES                                        5-1 5.1                  SITE                                                  5-1 5.2                  CONTAINMENT DESIGN FEATURES                            5-1 5.2.1.            Containment Structures                                5-1 5.2.2              Penetrations                                          5-2 5.2.3              Containment Structure Cooling Systems                  5-2 5.3                  NUCLEAR STEAM SUPPLY SYSTEM (NSSS)                    5;-2 5.3.l              Primary Coolant System                                5-2 5.3.2              Reactor Core and Control                              5-3 5.3.3              Emergency Core Cooling System                          5-3 5.4                  FUEL STORAGE                                          5-3 5.4.1              New Fuel Storage                                      5-3 5.4.2              Spent Fuel Storage                                    5-4 Figure 5-1    Site Environment TLD Stations                          5-5 6.0                    ADMiNISTRATIVE CONTROLS                                6-1 6.1                  RESPONSIBILITY                                        6-1 6.2                  ORGANIZATION                                          6-1 6.2.l              Off site                                              6-1 6.2.2              Plant Staff                                            6-1 6.2.3              Nuclear Activities Plant Organization (NAPO)          6-la 6.3                  PLANT STAFF QUALIFICATION                              6-lb 6.4                  TRAINING                                              6-1~
--SECTION                                  *DESCRIPTION * -                  --PAGE NO 4.0                    SURVEILLANCE REQUIREMENTS (Continued) 4.24.6            Gaseous Waste System                                  4-91 4.24.7            Solid Radioactive Waste                                4-91 4.24.8            Total Dose                                            4-91 Table 4 .24-1. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements          4-92 Table 4.24-2  Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements          4-93 Table 4.24-3  Radioactive Liquid Waste Sampling and Analysis Program                                            4-95 Table 4.24-5  Radioactive Gaseous Waste Sampling and Analysis Program                                            4-97 5.0                    DESIGN FEATURES                                        5-1 5.1                  SITE                                                  5-1 5.2                  CONTAINMENT DESIGN FEATURES                            5-1 5.2.1.            Containment Structures                                5-1 5.2.2              Penetrations                                          5-2 5.2.3              Containment Structure Cooling Systems                  5-2 5.3                  NUCLEAR STEAM SUPPLY SYSTEM (NSSS)                    5;-2 5.3.l              Primary Coolant System                                5-2 5.3.2              Reactor Core and Control                              5-3 5.3.3              Emergency Core Cooling System                          5-3 5.4                  FUEL STORAGE                                          5-3 5.4.1              New Fuel Storage                                      5-3 5.4.2              Spent Fuel Storage                                    5-4 Figure 5-1    Site Environment TLD Stations                          5-5 6.0                    ADMiNISTRATIVE CONTROLS                                6-1 6.1                  RESPONSIBILITY                                        6-1 6.2                  ORGANIZATION                                          6-1 6.2.l              Off site                                              6-1 6.2.2              Plant Staff                                            6-1 6.2.3              Nuclear Activities Plant Organization (NAPO)          6-la 6.3                  PLANT STAFF QUALIFICATION                              6-lb 6.4                  TRAINING                                              6-1~
         - Figure 6.2-1  Consumers Power-Company Offite Organization            6-2 Figure 6.2-2  Consumers Power Company Plant Organization            6-3 Table 6.2-1    Minimum Shift Crew Composition                        6-4 vi Proposed PAL TC
         - Figure 6.2-1  Consumers Power-Company Offite Organization            6-2 Figure 6.2-2  Consumers Power Company Plant Organization            6-3 Table 6.2-1    Minimum Shift Crew Composition                        6-4 vi Proposed PAL TC
* PALISADES PLANT TECHNICAL SPECIFICATIONS
 
* TABLE OF CONTENTS - APPENDIX A
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A
--- SEC!fION -                        -- --- --DESCRIPTION- - - ---- -- -  - -- --PA.GE NO- - ---- .
--- SEC!fION -                        -- --- --DESCRIPTION- - - ---- -- -  - -- --PA.GE NO- - ---- .
6.0                    ADMINISTRATIVE CONTROLS (Continued) 6.5                  REVIEW AND AUDIT                                          6-5 6 .5 .1          Plant Review Committee (PRC)                              6-5 6.* 5.2          Nuclear Safety Board (NSB)                                6-6a 6.6                                  (Deleted)                                6-10 6.7                  SAFETY LIMIT VIOLATION                                    6-10 6.8                  PROCEDURES                                                6-10 6.9                  REPORTING REQUIREMENTS                                    6-11 6.9.l            Routine Reports                                          6-11 6.9.2            Reportable Events                                        6-12 6.9.3            Other Reporting Requirements                              6-18 6.9.3.1      Routine Reports                                          6-18 6.9.3.1.A  Radioactive Effluent Releases                            6-18 6.9.3.1.B  Annual Radiological Environmental Operating Report        6-24 6.9.3.2      Nonroutine Reports                                        6-25b Table 6.9-1 Environmental Radiological Monitoring Program Summary    6-25c 6.9.3.3      Special Reports                                          6-26 6.10                RECORD RETENTION                                          6-26 6.11                RADIATION PROTECTION PROGRAM                              6-28 6.12                HIGH RADIATION AREA                                      6-28 6.13                FIRE PROTECTION INSPECTION                                6-33 6.14                ENVIRONMENTAL QUALIFICATION                              6-33 6.15                SYSTEMS INTEGRITY                                        6-33 6.16                IODINE MONITORING                                        6-33 6.18                OFFSITE DOSE CALCULATION MANUAL (ODCM)                    6-35 6.19                PROCESS CONTROL PROGRAM (PCP)                            6-35 6.20                MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS                      6.;..36 6.21                SEALED SOURCE CONTAMINATION                              6-37    1 vii Proposed PAL TC
6.0                    ADMINISTRATIVE CONTROLS (Continued) 6.5                  REVIEW AND AUDIT                                          6-5 6 .5 .1          Plant Review Committee (PRC)                              6-5 6.* 5.2          Nuclear Safety Board (NSB)                                6-6a 6.6                                  (Deleted)                                6-10 6.7                  SAFETY LIMIT VIOLATION                                    6-10 6.8                  PROCEDURES                                                6-10 6.9                  REPORTING REQUIREMENTS                                    6-11 6.9.l            Routine Reports                                          6-11 6.9.2            Reportable Events                                        6-12 6.9.3            Other Reporting Requirements                              6-18 6.9.3.1      Routine Reports                                          6-18 6.9.3.1.A  Radioactive Effluent Releases                            6-18 6.9.3.1.B  Annual Radiological Environmental Operating Report        6-24 6.9.3.2      Nonroutine Reports                                        6-25b Table 6.9-1 Environmental Radiological Monitoring Program Summary    6-25c 6.9.3.3      Special Reports                                          6-26 6.10                RECORD RETENTION                                          6-26 6.11                RADIATION PROTECTION PROGRAM                              6-28 6.12                HIGH RADIATION AREA                                      6-28 6.13                FIRE PROTECTION INSPECTION                                6-33 6.14                ENVIRONMENTAL QUALIFICATION                              6-33 6.15                SYSTEMS INTEGRITY                                        6-33 6.16                IODINE MONITORING                                        6-33 6.18                OFFSITE DOSE CALCULATION MANUAL (ODCM)                    6-35 6.19                PROCESS CONTROL PROGRAM (PCP)                            6-35 6.20                MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS                      6.;..36 6.21                SEALED SOURCE CONTAMINATION                              6-37    1 vii Proposed PAL TC


*
  . ,.
Table 3.17.4    (Cont'd)
Table 3.17.4    (Cont'd)
____ *Jg) ___
____ *Jg) ___

Latest revision as of 13:21, 3 February 2020

Proposed Tech Specs Increasing Quantity of Cs-137 Sealed Source for Calibr of high-range Radiation Detection Instruments & Adding Leak Test Requirements,Per Rev 2 to NUREG-0212 (Section 3/4.7.10)
ML18052A472
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/20/1986
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18052A471 List:
References
RTR-NUREG-0212, RTR-NUREG-212 NUDOCS 8606260315
Download: ML18052A472 (11)
v • d • e


Text

-- - - -ATTACHMENr -*-** .. --* - -- -- -

Consumers Power *company Palisades Plant Docket 50-255 PROPOSED PAGES PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST ALLOWABLE QUANTITY.OF SOURCE MATERI~L June 20, 1986 10 Pages TSP0686-0097-NL04

  • -- -* - UNITED* STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555 CONSUMERS POWER COMPANY (Palisades Plant)

DOCKET NO 50-255 PROVISIONAL OPERATING LICENSE License No DPR-20 Provisional Operating License No DPR-20, issued to the licensee for operation of the facility, on September 1, 1972, is hereby amended in its entirety to read as follows:

1. Provisional Operating License No DPR-20 applies to the Palisades Plant, a pressurized, light water moderated and cooled reactor, and electric generating equipment (the facility). The facility is located in Covert Township on*the Consumers Power site in Van Buren County, Michigan, and is described in the "Final Safety Analysis Report", as supplemented and amende*d.
2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Power Company (the licensee):

A. Pursuant to Section 104b of the Atomic Energy Act of 1954, as amended (the Act), and 10 CFR Part50, "Licensing of Production and Utilization Facilities~, to po~sess, use and operate the facility as a utilization facility at the designated location; B. Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material", to receive, possess and use 15,000 kilograms of Uranium-235 and 96 grams of encapsulated plutonium-beryllium in connection with operation of the facility; C. Pursuant to the Act. and 10 CFR Part 30, "Rules of General Applicability of Licensing of Byproduct Material", to receive, possess and use in connection with operation of the facility 1500 curies of Polonium~210 as two.sealed sources not to exceed 750 curies each, 1000 curies of Cesium~137 as multiple sealed calibration sources and up to 50~ millicuries per nuclide of any byproduct material with Atomic Numbers 3 to 83, inclusive, without restriction to chemical and physical form to a total of 10 curies; TSP0686-0097-NL04

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A

- - - -- ---- -- - - SECTION- -- ------- -- -- - - - DESCRIPTION-- - -- - - - - -- PA.GE Nff - - -----

~~~~~~~~~~....;;...;;;--'-~~~~~~~~~

1.0 DEFINITIONS 1-1 1.1 REACTOR OPERATING CONDITIONS 1-1 1.2 PROTECTIVE SYSTEMS 1-3 1.3 INSTRUMENTATION SURVEILLANCE 1-3 1.4 MISCELLANEOUS DEFINITIONS 1-4 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 SAFETY LIMITS - REACTOR CORE 2-1 2.2 SAFETY LIMITS - PRIMARY COOLANT SYSTEM PRESSURE 2-3 2.3 LIMITING SAFETY SYSTEM SETTINGS - REACTOR PROTECTIVE SYSTEM 2-4 Table 2.3.1 Reactor Protective System Trip Setting Limits 2-5 Figure 2-1 Reactor Core Safety Limits 2 Pump Operation 2-11 Figure 2-2 Reactor Core Safety Limits 3 Pump Operation 2-12 Figure 2-3 Reactor Core Safety Limits 4 Pump Operation 2-13 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1 3.1 PRIMARY COOLANT SYSTEM 3...;1b 3 .1.1 Operable Components 3-lb Figure 3-0 Reactor Inlet Temperature vs Operating Pressure 3-3a 3.1.2 Heatup and Cooldown Rates 3;...4 Figure 3-1 Pressure - Temperature Limits for Heatup 3-9 Figure 3-2 Pressure - Temperature Limits for Cooldown 3;...10 Figure 3-3 Pressure - Temperature Limits for Hydro Test 3-11 3.* 1.3 Minimum Conditions for Criticality

  • 3-12 3.1.4 Maximum Primary Coolant Radioactivity 3-17 3.1.5 Primary Coolant System Leak.age Limits 3-20 3.1.6 Maximum Primary Coolant Oxygen and Halogens Concentrations 3-23 3.1. 7 Primary and S~condary Safety Valves 3-25 3.1.8 Overpressure Protection Systems 3-25a 3.2 CHEMICAL AND VOLUME CONTROL SYSTEM 3-26 3.3 EMERGENCY CORE COOLING SYSTEM 3-29 3.4 CONTAINMENT COOLING 3-34 3.5 STEAM AND FEEDWATER SYSTEMS 3-38 3.6 CONTAINMENT SYSTEM 3-40 3.7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 3.9 EFFLUENT RELEASE (DELETED) 3-50 i

PAL TC

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A PAGEliO - - -- -- ---

3.0 LIMITING CONDITIONS FOR OPERATION (Continued) 3.10 CONTROL ROD AND POWER DISTRIBUTION LIMITS 3-58 3.10.l Shutdown Margin Requirements 3-58 3.10.2 Individual Rod Worth 3-58 3.10.3 Part-Length Control Rods 3-58 3.10.4 Misaligned or Inoperable Control Rod or Part-Length Rod 3-60 3.10.5 Regulating Group Insertion Limits 3-60 3.10.6 Shutdown Rod Liinits 3-61 3.10.7 Low Power Physics Testing 3-61 3.10.8 Center Control Rod Misalignment 3-61 Figure 3-6 Control Rod Insertion Limits 3-62

3. ll POWER DISTRIBUTION INSTRUMENTS 3-65 3.11.1 Incore Detectors 3-65 3.11.2 Excore Power Distribution Monitoring System 3-66a Figure 3.11-1 Axial Variation Bounding Condition 3-66d 3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-67 3.13 CONTAINMENT BUILDING AND FUEL STORAGE BUILDING CRANES 3-69 3.14 CONTROL ROOM VENTILATION 3-70 3.15 REACTOR PRIMARY SHIELD COOLING SYSTEM 3-70a 3.16 ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUMENTATION SETTINGS 3-71 Table 3.16.1 Engineered Safety Features System Initiation Instrument Setting Limits 3-75 3.17 INSTRUMENTATION AND CONTROL SYSTEMS 3-76 Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System 3-78 Table 3.17.2 Instrumentation Operating Requirements for Engineered Safety Feature Systems 3-79 Table 3.17.3 Instrument Operating Conditions for Isolation Functions
  • 3-80 Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions 3-81 3d8 SECONDARY WATER MONITORING REQUIREMENTS 3-82 Table 3.18.1 Secondary Water Monitoring Control Parameters 3-83 3.19 IODINE REMOVAL SYSTEM 3-84 3.20 SHOCK SUPPRESSORS (SNUBBERS) 3-88 Table 3.20.1 Safety-Related Hydraulic Shock Suppressors (Snubbers) 3-89 3.21 Table 3.20.2 Safety-Related Mechanical Shock Suppressors (Snubbers)

MOVEMENT OF SHIELDED CASK IN FUEL HANDLING AREAS 3-91 3-92 1

3.22 FIRE PROTECTION SYSTEM 3-96 3.22.1 Fire Detection Instrumentation 3-96 Table 3.22.1 Fire Detection Instrumentation - Minimum Instruments Operable 3-97 ii Propose~

PAL TC

  • PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A DESCRIPTION PAGE NO ----~- - ---

3.0 LIMITING CONDITIONS FOR OPERATION (Continued) 3.22.2 Fire Suppression Water System 3-98 3.22.3 Fire Sprinkler System 3-100 3.22.4 Fire Hose Stations 3-101 3.22.5 Penetration Fire Barriers 3-102 3.23 POWER DISTRIBUTION LIMITS 3-103 3.23.1 Linear Heat Rate (LHR) 3-103 Table 3.23.1 Linear Heat Rate Limits 3-107 Table 3.23.2 Radial Peaking Factor Limits, F 3-107 Fig. 3.23-1 Allowable LHR as a Function of ~eak Power Location 3-108 Fig. 3.23-2 Allowable LHR as a Function of Burnup 3-109 Fig. 3.23-3 Allowable LHR as a Function of Active Fuel Height for Interior Fuel Rods 3-110 3.23.2 Radial Peaking Factors 3-111 3.23.3 Quadrant Power Tilt - Tq 3-112 3.24 RADIOLOGICAL EFFLUENT RELEASES 3-114 3.24.1 Radioactive Liquid Effluent Monitoring Instrumentation ~-114 Table 3.24-1 Radioactive Liquid Effluent Monitoring Instrumentation ... 3-115 Bases for 3.24.1 3-128 3.24.2 Radioactive Gaseous Effluent Monitoring Instrumentation 3-117 Table 3.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation 3-118 Bases for 3.24.2 .* 3-128 3.24.3 Liquid Effluents Concentration 3-120 Bases for 3.24.3 3-129 I 3.24.4 Liquid Effluent Dose 3-121 Bases for 3.24.4 3-129 I 3.24.5 Gaseous Effluents Dose 3-122 Bases for 3.24.5 3-130 3.24.5.1 Dose Rate 3-122 Bases for 3.24.5.1 3-130 3.24.5.2 Noble Gases 3-123 Bases for 3.24.5.2 3-131 3.24.5.2 Dose ~ Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form 3...:124 Bases for 3.24.5.2 3-131 3.24.6 Gaseous Waste Treatment System 3-125 Basesfor 3.24.6 3-132 3.24.7 Solid Radioactive Waste 3-126 Bases for 3.24.7 3-132 3.24.8 Total Dose 3-127 Bases for 3.24.8 3-133 iii Proposed PAL TC

PALISADES PLANT TECHNICAL SPECIFICATIONS

. TJiaLE OF *CONTENTS - .APPENDIX A

... --. SECTION - ------ --*--- DESCRIPTION- PAGE NO 4.0 SURVEILLANCE REQUIREMENTS 4-1 4 .1 INSTRUMENTATION AND CONTROL 4-1 Table 4.1.1 Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System 4-3 Table 4.1. 2 Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls 4-6 Table 4.1.3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls 4-10 4.2 EQUIPMENT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Frequencies for Sampling Tests 4-14 Table 4.2.2 Minimum Frequencies for Equipment Tests 4-15 Table 4.2.3 HEPA Filter and Charcoal Adsorber Systems 4-15c 4.3 SYSTEMS SURVEILLANCE 4-16 Table 4.3.1 Primary Coolant System Pressure Isolation Valves 4'.""19 Table 4.3.2 Miscellaneous Surveillance Items 4-23 4.4 PRIMARY COOLANT SYSTEM INTEGRITY TESTING 4-24 4.5 CONTAINMENT TESTS 4-25 4.5.1 Integrated Leakage Rate Tests 4-25 4.5.2 Local Leak Detection Tests 4-27 4.5.3 Recirculation Heat Removal Systems 4-28 4.5.4 Surveillance for Prestressing System 4~29 4.5.5 End Anchorage Concrete Surveillance 4-30 4.5.6 Liner Plate Surveillance 4-31 4.5.7 Penetrations Surveillance 4-32 4.5.8 Dome Delamination Surveillance 4-32a 4.6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4-39.

4~6.1 Safety Injection System 4-39 4.6.2 Containment Spray System 4-39 4.6.3 Pumps . 4...;39 4.6.4 Valve* (Deleted) 4-40 4.6.5 Containment Air Cooling System 4-40 4.7 EMERGENCY POWER SYSTEM PERIODIC TESTS . 4-42 4.7.1 Diesel Generators 4-42 4.7.2 Station Batteries 4-42 4.7.3 Emergency Lighting 4-43 4.8 MAIN STEAM STOP VALVES 4-44 4.9 AUXILIARY FEEDWATER SYSTEM 4-45 _I 4.10 REACTIVITY ANOMALIES 4-46 4.11 RADIOLOGICAL ENVIRONMENTAL MONITORING 4..:.47 Table 4.11-1 Radiological Environmental Monitoring Program 4-49 Table 4.11-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 4-56 iv Proposed' PAL TC

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A

- --- ---- - - - --SECTION- - -- - - -- -- DESCRIPTION 4.0 SURVEILLANCE REQUIREMENTS (Continued)

Table 4 .11-3 Detection Capabilities for Environmental Sample Ai:J.alysis 4-57 4.11.l Bases for Monitoring Program 4-59a 4.11.3 Bases for Land Use Census 4-59a 4.11.5 Bases for Interlaboratory Comparison Program 4-59a 4.12 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT- 4-60 Fig. 4.12 A Augmented Inservice Inspection Program - Main Steam Welds 4-63 Fig. 4.12 B Augmented Inservice Inspection Program - Feedwater Line Welds 4-64 4.13 REACTOR INTERVALS VIBRATION MONITORING (DELETED) 4-65 4.14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS 4-68 Table 4.14.1 Operating Allowances 4-68d Table 4.14.2 Maximum Allowable Degradation 4-69 4.15 PRIMARY SYSTEM FLOW MEASUREMENT 4-70 4.16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (SNUBBERS) 4-71 4.17 FIRE PROTECTION SYSTEM 4-75 4.17.1 Fire Detection Instrumentation 4 4.17.2 Fire Suppression Water System 4-76 4.17.3 Fire Sprinkler System 4-78 4.17.4 Fire Hose Stations 4-79 4.17.5 Penetration r*

Fire Barriers 4-80 4.18 POWER DISTRIBUTION INSTRUMENTATION 4-81 4.18 .1 Incore Detectors 4-81 4.18.2 Excore Monitoring System 4-82 4.19 POWER DISTRIBUTION LIMITS 4-83 4.19.l Linear Heat Rate 4-83 4.19.2 Radial Peaking Factors 4-84 4.20 (Intentionally Left Blank) 4-85 4.21 (Intentionally Left Blank) 4-86 4.22 (Intentionally Left Blank) 4-87 4.23 (Intentionally Left Blank) 4-88 (Intentionally Left Blank) 4-89 4.24 RADIOLOGICAL EFFLUENT RELEASES 4-90 4.24.1 Radiological Liquid Effluent Monitoring Instrumentation 4-90 4.24.2 Radiological Gaseous Effluent Monitoring Instrumentation 4-90 4.24.3 Liquid Effluent Concentration 4-90 4.24.4 Liquid Effluent Dose 4-90 4.24.5 Gaseous Effluent Dose 4-90 v

Proposed.

PAL TC

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A

--SECTION *DESCRIPTION * - --PAGE NO 4.0 SURVEILLANCE REQUIREMENTS (Continued) 4.24.6 Gaseous Waste System 4-91 4.24.7 Solid Radioactive Waste 4-91 4.24.8 Total Dose 4-91 Table 4 .24-1. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 4-92 Table 4.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 4-93 Table 4.24-3 Radioactive Liquid Waste Sampling and Analysis Program 4-95 Table 4.24-5 Radioactive Gaseous Waste Sampling and Analysis Program 4-97 5.0 DESIGN FEATURES 5-1 5.1 SITE 5-1 5.2 CONTAINMENT DESIGN FEATURES 5-1 5.2.1. Containment Structures 5-1 5.2.2 Penetrations 5-2 5.2.3 Containment Structure Cooling Systems 5-2 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5;-2 5.3.l Primary Coolant System 5-2 5.3.2 Reactor Core and Control 5-3 5.3.3 Emergency Core Cooling System 5-3 5.4 FUEL STORAGE 5-3 5.4.1 New Fuel Storage 5-3 5.4.2 Spent Fuel Storage 5-4 Figure 5-1 Site Environment TLD Stations 5-5 6.0 ADMiNISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-1 6.2.l Off site 6-1 6.2.2 Plant Staff 6-1 6.2.3 Nuclear Activities Plant Organization (NAPO) 6-la 6.3 PLANT STAFF QUALIFICATION 6-lb 6.4 TRAINING 6-1~

- Figure 6.2-1 Consumers Power-Company Offite Organization 6-2 Figure 6.2-2 Consumers Power Company Plant Organization 6-3 Table 6.2-1 Minimum Shift Crew Composition 6-4 vi Proposed PAL TC

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A

--- SEC!fION - -- --- --DESCRIPTION- - - ---- -- - - -- --PA.GE NO- - ---- .

6.0 ADMINISTRATIVE CONTROLS (Continued) 6.5 REVIEW AND AUDIT 6-5 6 .5 .1 Plant Review Committee (PRC) 6-5 6.* 5.2 Nuclear Safety Board (NSB) 6-6a 6.6 (Deleted) 6-10 6.7 SAFETY LIMIT VIOLATION 6-10 6.8 PROCEDURES 6-10 6.9 REPORTING REQUIREMENTS 6-11 6.9.l Routine Reports 6-11 6.9.2 Reportable Events 6-12 6.9.3 Other Reporting Requirements 6-18 6.9.3.1 Routine Reports 6-18 6.9.3.1.A Radioactive Effluent Releases 6-18 6.9.3.1.B Annual Radiological Environmental Operating Report 6-24 6.9.3.2 Nonroutine Reports 6-25b Table 6.9-1 Environmental Radiological Monitoring Program Summary 6-25c 6.9.3.3 Special Reports 6-26 6.10 RECORD RETENTION 6-26 6.11 RADIATION PROTECTION PROGRAM 6-28 6.12 HIGH RADIATION AREA 6-28 6.13 FIRE PROTECTION INSPECTION 6-33 6.14 ENVIRONMENTAL QUALIFICATION 6-33 6.15 SYSTEMS INTEGRITY 6-33 6.16 IODINE MONITORING 6-33 6.18 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-35 6.19 PROCESS CONTROL PROGRAM (PCP) 6-35 6.20 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.;..36 6.21 SEALED SOURCE CONTAMINATION 6-37 1 vii Proposed PAL TC

Table 3.17.4 (Cont'd)

____ *Jg) ___

  • Calculate-the .Quadrant Power--Tilt using*the*-excore readings at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the excore detectors deviation alarms are inoperable. I (h) With two flow rate indicators inoperable for a given control valve, the control valve shall be considered inoperable and the requirements of 3.5.2(e) apply.

3-Slb Proposed TSP0686-0097-NL04

ADMINISTRATIVE ~ONTROLS 6.21 SEALED SOURCE CONTAMINATION

--6-. 2-1 * - -Ea-ch sealed-~fource contaiiiing--radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.

6.21.2 With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:

  • _1. Decontaminate and repair the sealed source, or
2. Dispose of the sealed source in accordance with applicable regulations.

6.21.3 Each category of sealed sources as described.in 6.21.1 with a half-life greater than 30 days (excluding Hydrogen-3), and in any* other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed six months.

6. 21. 4 The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

6.21.5 The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.

6.21.6 The periodic leak test does not apply to sealed sources that are stored and not being used. These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous six months. Sealed sources which are continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

6.21.7. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.

6.21.8 A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

6-37 Proposed TSP0686-0097-NL04

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