Text

Facility Operating License DPR-20, Appendix a (Technical Specifications)
	ML070110053
Person / Time
Site:	Palisades
Issue date:	01/10/2007
From:	; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
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PALISADES PLANT FACILITY OPERATING LICENSE DPR-20 APPENDIX A TECHNICAL SPECIFICATIONS As Amended through Amendment No. 223

FACILITY OPERATING LICENSE and TECHNICAL SPECIFICATIONS 1 LIST OF EFFECTIVE PAGES DESCRIPTION PAGES AMENDMENT NUMBER FACILITY OPERATING LICENSE Page 1 201 Page 2 201 Page 3 222 Page 4 206 Page 4a 206 Page 5 11/10/04 APPENDIX A - TECHNICAL SPECIFICATIONS COVERSHEET Title Page 222 TABLE OF CONTENTS Pagei 205 Page ii 221 Page iii 189 Section 1.0 Page 1.1-1 205 Pages 1.1 1.1-3 189 Page 1.1-4 223 Page 1. 1-5 216 Page 1. 1-6 205 Page 1. 1-7 189 Pages 1.2-1 - 1.2-3 189 Pages 1.3-1 - 1.3-12 189 Pages 1.4-1 - 1.4-4 189 Section 2.0 Page 2.0-1 189 Section 3.0 Pages 3.0 3.0-2 219 Page 3.0-3 210 Page 3.0-4 219 Section 3.1 Page 3.1.1-1 189 Pages 3.1.2-1 - 3.1.2-2 189 Page 3.1.3-1 189 Pages 3.1.4-1 - 3.1.4-3 189 Page 3.1.5-1 189 Pages 3.1.6-1 - 3.1.6-2 189 Pages 3.1.7-1 - 3.1.7-2 189 Section 3.2 Pages 3.2.1 3.2.1-4 189 Page 3.2.2-1 205 Page 3.2.3-1 205 Page 3.2.4-1 189 Amendment No. 223

FACILITY OPERATING LICENSE and TECHNICAL SPECIFICATIONS 2 LIST OF EFFECTIVE PAGES DESCRIPTION PAGES AMENDMENT NUMBER APPENDIX A - TECHNICAL SPECIFICATIONS (continued)

Section 3.3 Page 3.3.1-1 189 Page 3.3.1-2 219 Pages 3.3.1 3.3.1-5 189 Page 3.3.1-6 216 Page 3.3.1-7 189 Page 3.3.1-8 214 Pages 3.3.2 3.3.2-2 189 Page 3.3.3-1 219 Pages 3.3.3 3.3.3-5 189 Pages 3.3.4 3.3.4-3 189 Pages 3.3.5 3.3.5-2 189 Pages 3.3.6 3.3.6-2 189 Pages 3.3.7 3.3.7-2 221 Page 3.3.7-3 189 Page 3.3.7-4 221 Page 3.3.8-1 219 Pages 3.3.8 3.3.8-3 189 Pages 3.3.9 3.3.9-2 189 Page 3.3.10-1 189 Section 3.4 Pages 3.4.1-1 -3.4.1-2 217 Page 3.4.2-1 189 Pages 3.4.3 3.4.3-3 189 Page 3.4.3-4 218 Page 3.4.4-1 189 Pages 3.4.5 3.4.5-2 189 Pages 3.4.6 3.4.6-3 189 Pages 3.4.7 3.4.7-3 189 Pages 3.4.8 3.4.8-3 189 Pages 3.4.9 3.4.9-3 189 Pages 3.4.10 3.4.10-2 189 Page 3.4.11-1 219 Pages 3.4.11 3.4.11-3 189 Page 3.4.12-1 219 Pages 3.4.12 3.4.12-4 189 Pages 3.4.13 3.4.13-2 223 Pages 3.4.14 3.4.14-4 189 Page 3.4.15-1 219 Pages 3.4.15 3.4.15-3 189 Page 3.4.16-1 219 Pages 3.4.16 3.4.16-3 189 Pages 3.4.17 3.4.17-2 223 Section 3.5 Page 3.5.1-1 191 Page 3.5.1-2 189 Page 3.5.2-1 198 Pages 3.5.2 3.5.2-3 189 Page 3.5.3-1 189 Pages 3.5.4 3.5.4-2 189 Page 3.5.5-1 189 Amendment No. 223

FACILITY OPERATING LICENSE and TECHNICAL SPECIFICATIONS 3 LIST OF EFFECTIVE PAGES DESCRIPTION PAGES AMENDMENT NUMBER APPENDIX A - TECHNICAL SPECIFICATIONS (continued)

Section 3.6 Page 3.6.1-1 194 Pages 3.6.2 3.6.2-3 189 Page 3.6.2-4 194 Pages 3.6.3 3.6.3-5 189 Page 3.6.4-1 189 Page 3.6.5-1 189 Page 3.6.6-1 199 Page 3.6.6-2 189 Page 3.6.6-3 211 Section 3.7 Pages 3.7.1 3.7.1-2 189 Pages 3.7.2 3.7.2-2 189 Pages 3.7.3 3.7.3-2 189 Page 3.7.4-1 219 Page 3.7.4-2 189 Page 3.7.5-1 219 Page 3.7.5-2 200 Page 3.7.5-3 190 Pages 3.7.6 3.7.6-2 189 Page 3.7.7-1 199 Page 3.7.7-2 189 Page 3.7.8-1 199 Page 3.7.8-2 189 Page 3.7.9-1 202 Pages 3.7.10 3.7.10-3 197 Pages 3.7.11-1 -3.7.11-3 189 Pages 3.7.12 3.7.12-2 189 Page 3.7.13-1 189 Page 3.7.14-1 189 Page 3.7.15-1 207 Pages 3.7.16 3.7.16-2 207 Page 3.7.17-1 189 Section 3.8 Page 3.8.1-1 219 Pages 3.8.1 3.8.1-8 189 Pages 3.8.2 3.8.2-3 189 Pages 3.8.3 3.8.3-3 189 Pages 3.8.4 3.8.4-4 189 Pages 3.8.5 3.8.5-2 189 Pages 3.8.6 3.8.6-3 189 Page 3.8.7-1 189 Pages 3.8.8 3.8.8-2 189 Pages 3.8.9 3.8.9-2 189 Pages 3.8.10 3.8.10-2 189 Amendment No. 223

FACILITY OPERATING LICENSE and TECHNICAL SPECIFICATIONS 4 LIST OF EFFECTIVE PAGES DESCRIPTION PAGES AMENDMENT NUMBER APPENDIX A - TECHNICAL SPECIFICATIONS (continued)

Section 3.9 Page 3.9.1-1 189 Pages 3.9.2-1 - 3.9.2-2 189 Pages 3.9.3-1 - 3.9.3-2 189 Pages 3.9.4-1 -3.9.4-2 189 Pages 3.9.5-1 - 3.9.5-2 189 Page 3.9.6-1 189 Section 4.0 Pages 4.0 4.0-4 207 Section 5.0 Pages 5.0 5.0-2 189 Page 5.0-3 196 Page 5.0-4 212 Page 5.0-5 213 Page 5.0.6 196 Page 5.0.7 213 Pages 5.0.8- 5.0-9 196 Pages 5.0-10 189 Page 5.0 5.0-16 223 Page 5.0 5.0-18 189 Page 5.0-19 204 Page 5.0-20 189 Pages 5.0 5.0-23 194 Page 5.0-24 220 Page 5.0-25 220 Page 5.0-26 209 Page 5.0-27 222 Page 5.0-28 223 Pages 5.0 5.0-32 196 APPENDIX B - ENVIRONMENTAL PROTECTION PLAN Title Page 176 Table of Contents 63 (January 22, 1981)

Page 1-1 63 (January 22, 1981)

Pages 2-1 2 63 (January 22, 1981)

Pages 3-1 3 63 (January 22, 1981)

Pages 4-1 5 63 (January 22, 1981)

Pages 5-1 4 63 (January 22, 1981)

Amendment No. 223

TABLE OF CONTENTS TECHNICAL SPECIFICATIONS 1.0 USE AND APPLICATION 1.1 Definitions 1.2 Logical Connectors 1.3 Completion Times 1.4 Frequency 2.0 SAFETY LIMITS (SLs) 2.1.1 Reactor Core SLs 2.1.2 Primary Coolant System (PCS) Pressure SL 2.2 SL Violations 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) 3.1.2 Reactivity Balance 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.4 Control Rod Alignment 3.1.5 Shutdown and Part-Length Rod Group Insertion Limits 3.1.6 Regulating Rod Group Position Limits 3.1.7 Special Test Exceptions (STE) 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Linear Heat Rate (LHR) 3.2.2 TOTAL RADIAL PEAKING FACTOR (FRT) 3.2.3 QUADRANT POWER TILT (Tq) 3.2.4 AXIAL SHAPE INDEX (ASI) 3.3 INSTRUMENTATION 3.3.1 Reactor Protective System (RPS) Instrumentation 3.3.2 Reactor Protective System (RPS) Logic and Trip Initiation 3.3.3 Engineered Safety Features (ESF) Instrumentation 3.3.4 Engineered Safety Features (ESF) Logic and Manual Initiation 3.3.5 Diesel Generator (DG) - Undervoltage Start (UV Start) 3.3.6 Refueling Containment High Radiation (CHR) Instrumentation 3.3.7 Post Accident Monitoring (PAM) Instrumentation 3.3.8 Alternate Shutdown System 3.3.9 Neutron Flux Monitoring Channels 3.3.10 Engineered Safeguards Room Ventilation (ESRV) Instrumentation Palisades Nuclear Plant Amendment No. 4-89, 205

TABLE OF CONTENTS TECHNICAL SPECIFICATIONS 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.1 PCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.4.2 PCS Minimum Temperature for Criticality 3.4.3 PCS Pressure and Temperature (P/T) Limits 3.4.4. PCS Loops - MODES 1 and 2 3.4.5 PCS Loops - MODE 3 3.4.6 PCS Loops - MODE 4 3.4.7 PCS Loops - MODE 5, Loops Filled 3.4.8 PCS Loops - MODE 5, Loops Not Filled 3.4.9 Pressurizer 3.4.10 Pressurizer Safety Valves 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) 3.4.12 Low Temperature Overpressure Protection (LTOP) System 3.4.13 PCS Operational LEAKAGE 3.4.14 PCS Pressure Isolation Valve (PIV) Leakage 3.4.15 PCS Leakage Detection Instrumentation 3.4.16 PCS Specific Activity 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Safety Injection Tanks (SITs)

.3.5.2 ECCS - Operating 3.5.3 ECCS - Shutdown 3.5.4 Safety Injection Refueling Water Tank (SIRWT) 3.5.5 Trisodium Phosphate (TSP) 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment 3.6.2 Containment Air Locks 3.6.3 Containment Isolation Valves 3.6.4 Containment Pressure 3.6.5 Containment Air Temperature 3.6.6 Containment Cooling Systems 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) 3.7.2 Main Steam Isolation Valves (MSIVs) 3.7.3 Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves 3.7.4 Atmospheric Dump Valves (ADVs) 3.7.5 Auxiliary Feedwater (AFW) System 3.7.6 Condensate Storage and Supply 3.7.7 Component Cooling Water (CCW) System 3.7.8 Service Water System (SWS) 3.7.9 Ultimate Heat Sink (UHS) 3.7.10 Control Room Ventilation (CRV) Filtration 3.7.11 Control Room Ventilation (CRV) Cooling 3.7.12 Fuel Handling Area Ventilation System 3.7.13 Engineered Safeguards Room Ventilation (ESRV) Dampers 3.7.14 Spent Fuel Pool (SFP) Water Level 3.7.15 Spent Fuel Pool (SFP) Boron Concentration 3.7.16 Spent Fuel Assembly Storage 3.7.17 Secondary Specific Activity Palisades Nuclear Plant ii Amendment No. 1-89, 221

TABLE OF CONTENTS TECHNICAL SPECIFICATIONS 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating 3.8.2 AC Sources - Shutdown 3.8.3 Diesel Fuel, Lube Oil, and Starting Air 3.8.4 DC Sources - Operating 3.8.5 DC Sources - Shutdown 3.8.6 Battery Cell Parameters 3.8.7 Inverters - Operating 3.8.8 Inverters - Shutdown 3.8.9 Distribution Systems - Operating 3.8.10 Distribution Systems - Shutdown 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration 3.9.2 Nuclear Instrumentation 3.9.3 Containment Penetrations 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation - High Water Level 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation - Low Water Level 3.9.6 Refueling Cavity Water Level 4.0 DESIGN FEATURES 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.2 Organization 5.3 Plant Staff Qualifications 5.4 Procedures 5.5 Programs and Manuals 5.6 Reporting Requirements 5.7 High Radiation Area Palisades Nuclear Plant iii Amendment No. 189

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

NOTE -------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

AVERAGE DISINTEGRATION E shall be the average (weighted in proportion to the ENERGY- E concentration of each radionuclide in the primary coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

AXIAL OFFSET (AO) AO shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core (determined using the incore monitoring system).

AXIAL SHAPE INDEX (ASI) ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core (determined using the excore monitoring system).

Palisades Nuclear Plant 1.1 -1 Amendment No. 4-88, 205

Definitions 1.1 1.1 Definitions CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.

Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

Whenever a RTD or thermocouple sensing element is replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing element.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a. Analog and bistable channels - the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, of all devices in the channel required for channel OPERABILITY; Palisades Nuclear Plant 1.1 -2 Amendment No. 189

Definitions 1.1 1.1 Definitions CHANNEL FUNCTIONAL TEST b. Digital channels - the use of diagnostic programs to test (continued) digital hardware and the injection of simulated process data into the channel to verify OPERABILITY, of all devices in the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, Overlapping, or total channel steps so that the entire channel is tested.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or control rods within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the plant specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites."

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except Primary Coolant Pump seal water leakoff), that is captured and conducted to collection systems or a sump or collecting tank; Palisades Nuclear Plant 1.1 -3 Amendment No. 189

Definitions 1.1 1.1 Definitions LEAKAGE a. Identified LEAKAGE (continued)

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known not to interfere with the operation of leakage detection systems and not to be pressure boundary LEAKAGE; and

3. Primary Coolant System (PCS) LEAKAGE through a Steam Generator to the Secondary System (primary to secondary LEAKAGE).

b. Unidentified LEAKAGE All LEAKAGE (except Primary Coolant Pump seal leakoff) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an PCS component body;,

pipe wall, or vessel wall.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average primary coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

Palisades Nuclear Plant 1.1-4 Amendment No. 4-49, 223

Definitions 1.1 1.1 Definitions PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Chapter 13, Initial Tests and Operation, of the FSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

QUADRANT POWER TILT Tq shall be the maximum positive ratio of the power (Tq) generated in any quadrant minus the average quadrant power, to the average quadrant power.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) primary coolant of 2565.4 MWt.

REFUELING BORON REFUELING BORON CONCENTRATION shall be a Primary CONCENTRATION Coolant System boron concentration of >_1720 ppm and sufficient to assure the reactor is subcritical by _>5% Ap with all control rods withdrawn.

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All full length control rods (shutdown and regulating) are fully inserted except for the single rod of highest reactivity worth, which is assumed to be fully withdrawn.

However, with all full length control rods verified fully inserted by two independent means, it is not necessary to account for a stuck rod in the SDM calculation. With any full length control rods not capable of being fully inserted, the reactivity worth of these rods must be accounted for in the determination of SDM; and

b. There is no change in part length rod position.

Palisades Nuclear Plant 1.1 -5 Amendment No. 4-89, 216

Definitions 1.1 1.1 Definitions STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the primary coolant.

TOTAL RADIAL FRT shall be the maximum ratio of the individual PEAKING FACTOR fuel pin power to the core average pin power integrated over (FRT ) the total core height, including tilt.

Palisades Nuclear Plant 1.1 -6 Amendment No. 4498, 205

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES

% RATED AVERAGE PRIMARY MODE TITLE REACTIVITY THERMAL COOLANT CONDITION POWER(a) TEMPERATURE (keff) (OF) 1 Power Operation > 0.99 >5 NA 2 Startup Ž0.99 *5 NA 3 Hot Standby < 0.99 NA _>300 4 Hot Shutdown(b) < 0.99 NA 300 > Tave > 200 5 Cold Shutdown(b) < 0.99 NA _<200 6 Refueling(c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

Palisades Nuclear Plant 1.1-7 Amendment No. 189

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the" logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

Palisades Nuclear Plant 1.2-1 Amendment No. 189

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify...

AND A.2 Restore...

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

Palisades Nuclear Plant 1.2-2 Amendment No. 185c)

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip...

OR A.2.1 Verify...

AND A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 Align....

This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Palisades Nuclear Plant 1.2-3 Amendment No. 189

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the plant. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the plant is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the plant is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Action.s for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

Palisades Nuclear Plant 1.3-1 Amendment No. 189

Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent train, subsystem, component, or variable (continued) expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery. . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended.

Palisades Nuclear Plant 1.3-2 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Palisades Nuclear Plant 1.3-3 Amendment No. 189

Completion Times 1:3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B.

Palisades Nuclear Plant 1.3-4 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for > 7 days.

Palisades Nuclear Plant 1.3-5 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore Function X 7 days Function X train to OPERABLE train status. AND inoperable.

10 days from discovery of failure to meet the LCO B. One B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y train to OPERABLE train status. AND inoperable.

10 days from discovery of failure to meet the LCO C. One C.1 Restore Function X 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Function X train to OPERABLE train status.

inoperable.

OR AND C.2 Restore Function Y One train to OPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Function Y' status.

train inoperable.

Palisades Nuclear Plant 1.3-6 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock." In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.

Palisades Nuclear Plant 1.3-7 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (including the extension) expires while one or more valves are still inoperable, Condition B is entered.

Palisades Nuclear Plant 1.3-8 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

ACTIONS

--NOTE-------------------------------

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE inoperable, status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

Palisades Nuclear Plant 1.3-9 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLE EXAMPLE 1.3-6 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform SR 3.x.x.x. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to

50% RTP.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated Completion Time not met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2),

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

Palisades Nuclear Plant 1.3-10 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem isolated.

inoperable. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered.

Palisades Nuclear Plant 1.3-11 Amendment No. 189

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

Palisades Nuclear Plant 1.3-12 Amendment No. 189

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3.

Palisades Nuclear Plant 1.4-1 Amendment No. 189

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the plant is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the plant is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the plant is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

Palisades Nuclear Plant 1.4-2 Amendment No. 189

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

Ž25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to _>25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the extension allowed by SR 3.0.2. "Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to

< 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

Palisades Nuclear Plant 1.4-3 Amendment No. 189

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE ----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

_>25% RTP.

Perform channel adjustment. 7 days As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches _>25% RTP to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency." The interval continues, whether or not the plant operation is

< 25% RTP between performances. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power Ž>25% RTP.

Once the plant reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Palisades Nuclear Plant 1.4-4 Amendment No. 189

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2, the Departure from Nucleate Boiling Ratio (DNBR) shall be maintained at or above the following DNB correlation safety limits:

Correlation Safety Limit XNB 1.17 ANFP 1.154 HTP 1.141 2.1.1.2 In MODES 1 and 2, the peak Linear Heat Rate (LHR) (adjusted for fuel rod dynamics) shall be maintained at _<21.0 kW/ft.

2.1.2 Primary Coolant System (PCS) Pressure SL In MODES 1, 2, 3, 4, 5, and 6, the PCS pressure shall be maintained at

< 2750 psia.

2.2 SL Violations 2.2.1 If SL 2.1.1.1 or SL 2.1.1.2 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4, 5, or 6, restore compliance within 5 minutes.

Palisades Nuclear Plant 2.0-1 Amendment No. 189

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the plant shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the plant, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 4 within 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months ; and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .'

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications; or Palisades Nuclear Plant 3.0-1 Amendment No. 48&g. 219

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 (continued)

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the plant.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Special Test Exception (STE) LCOs in each applicable LCO section allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with STE LCOs is optional. When an STE LCO is desired to be met but is not met, the ACTIONS of the STE LCO shall be met. When an STE LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

Palisades Nuclear Plant 3.0-2 Amendment No. 1-89, 219

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.

Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per..

basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

Palisades Nuclear Plant 3.0-3 Amendment No. 41-8, 210

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an

.LOshall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the plant.

Palisades Nuclear Plant 3.0-4 Amendment No. 448, 219

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be within the limits specified in the COLR.

APPLICABILITY: MODE 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to 15 minutes restore SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Palisades Nuclear Plant 3.1.1 -1 Amendment No. 189

Reactivity Balance 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Balance LCO 3.1.2 The core reactivity balance shall be within +/- 1 % Ap of predicted values.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity balance not A.1 Re-evaluate core design 7 days within limit, and safety analysis and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 7 days operating restrictions and SRs.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Palisades Nuclear Plant 3.1.2-1 Amendment No. 189

Reactivity Balance 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ------------------- NOTE---------------

The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 Effective Full Power Days (EFPD) after each fuel loading.

Verify overall core reactivity balance is within Prior to entering

+/- 1% Ap of predicted values. MODE 1 after each fuel loading AND Only required after initial 60 EFPD 31 EFPD Palisades Nuclear Plant 3.1.2-2 Amendment No. 189

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained less positive than 0.5 E-4 Ap/ 0 F at < 2%

RATED THERMAL POWER (RTP).

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within limits. A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is less positive than 0.5 E-4 Ap/°F at Prior to exceeding

2% RTP. 2% RTP after each fuel loading Palisades Nuclear Plant 3.1.3-1 Amendment No. 189

Control Rod Alignment 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Alignment LCO 3.1.4 All control rods, including their position indication channels, shall be OPERABLE and aligned to within 8 inches of all other rods in their respective group, and the control rod position deviation alarm shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel of rod position A.1 Perform SR 3.1.4.1 Once within indication inoperable for (rod position 15 minutes following one or more control rods. verification), any rod motion in that group B. Rod position deviation B.1 Perform SR 3.1.4.1 Once within alarm inoperable. (rod position 15 minutes of verification), movement of any control rod C. One control rod misaligned C.1 Perform SR 3.2.2.1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by > 8 inches. (peaking factor verification).

OR C.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to < 75% RTP.

D. One full-length control rod D.1 Restore control rod to Prior to entering immovable, but trippable. OPERABLE status. MODE 2 following next MODE 3 entry Palisades Nuclear Plant 3.1.4-1 Amendment No. 189

Control Rod Alignment 3.1.4 ACTIONS E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

OR One or more control rods inoperable for reasons other than Condition D.

OR Two or more control rods misaligned by > 8 inches.

OR Both rod position indication channels inoperable for one or more control rods.

Palisades Nuclear Plant 3.1.4-2 Amendment No. 189

Control Rod Alignment 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1..4.1 Verify the position of each control rod to be within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 8 inches of all other control rods in its group.

SR 3.1.4.2 Perform a CHANNEL CHECK of the control rod 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position indication channels.

SR 3.1.4.3 Verify control rod freedom of movement by moving 92 days each individual full-length control rod that is not fully inserted into the reactor core > 6 inches in either direction.

SR 3.1.4.4 Verify the rod position deviation alarm is 18 months OPERABLE.

SR 3.1.4.5 Perform a CHANNEL CALIBRATION of the control 18 months rod position indication channels.

SR 3.1.4.6 Verify each full-length control rod drop time is Prior to reactor

_ 2.5 seconds. criticality, after each reinstallation of the reactor head Palisades Nuclear Plant 3.1.4-3 Amendment No. 189

Shutdown and Part-Length Rod Group Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown and Part-Length -Control Rod Group Insertion Limits LCO 3.1.5 All shutdown and part-length rod groups shall be withdrawn to

>128 inches.

APPLICABILITY: MODE 1, MODE 2 with any regulating rod withdrawn above 5 inches.

-NOTE--------------------------------------------

This LCO is not applicable while performing SR 3.1.4.3 (rod exercise test).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown or A.1 Declare affected control Immediately part-length rods not within rod(s) inoperable and limit. enter the applicable Conditions and Required Actions of LCO 3.1.4.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown and part-length rod group is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months withdrawn _>128 inches.

Palisades Nuclear Plant 3.1.5-1 Amendment No. 189

Regulating Rod Group Position Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Regulating Rod Group Position Limits LCO 3.1.6 The Power Dependent Insertion Limit (PDIL) alarm circuit and the Control Rod Out Of Sequence (CROOS) alarm circuit shall be OPERABLE, and the regulating rod groups shall be limited to the withdrawal sequence, overlap, and insertion limits specified in the COLR.

APPLICABILITY: MODES 1 and 2.

--- - --NOTE-----------------------

This LCO is not applicable while performing SR 3.1.4.3 (rod exercise test).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Regulating rod groups A.1 Restore regulating rod 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inserted beyondthe groups to within limits.

insertion limit.

OR A.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to less than or equal to the fraction of RTP allowed by the regulating rod group position and insertion limits specified in the COLR.

Palisades Nuclear Plant 3.1.6-1 Amendment No. 189

Regulating Rod Group Position Limits 3.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Regulating rod groups not B.1 Restore regulating rod 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months within sequence or overlap, groups to within limits, appropriate sequence and overlap limits.

C. PDIL or CROOS alarm C.1 Perform SR 3.1.6.1 Once within circuit inoperable. (group position 15 minutes following verification), any rod motion D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify each regulating rod group is within its 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months withdrawal sequence, overlap, and insertion limits.

SR 3.1.6.2 Verify PDIL alarm circuit is OPERABLE. 31 days SR 3.1.6.3 Verify CROOS alarm circuit is OPERABLE. 31 days Palisades Nuclear Plant 3.1.6-2 Amendment No. 189

Special Test Exceptions (STE) 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Special Test Exceptions (STE)

LCO 3.1.7 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.4, "Control Rod Alignment";

LCO 3.1.5, "Shutdown and Part-Length RodGroup Insertion Limits";

LCO 3.1.6, "Regulating Rod Group Position Limits"; and LCO 3.4.2, "PCS Minimum Temperature for Criticality" may be suspended, provided:

a. THERMAL POWER is *<2% RTP;

b. __1% shutdown reactivity, based on predicted control rod worth, is available for trip insertion; and C. Tave is Ž_500°F.

APPLICABILITY: MODE 2 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. THERMAL POWER not A.1 Reduce THERMAL 15 minutes within limit. POWER to within limit.

B. Shutdown reactivity not B.1 Initiate boration to 15 minutes within limit, restore shutdown reactivity to within limit.

C. Ta.e not within limit. C.1 Restore Tave to within 15 minutes limit.

Palisades Nuclear Plant 3.1.7-1 Amendment No. 189

Special Test Exceptions (STE) 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Suspend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion TESTS.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify THERMAL POWER is *2% RTP. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.1.7.2 5000 F.

Verify Tave is _Ž 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.1.7.3 Verify _ 1% shutdown reactivity is available for trip 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months insertion.

Palisades Nuclear Plant 3.1.7-2 Amendment No. 189

LHR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Linear Heat Rate (LHR)

LCO 3.2.1 LHR shall be within the limits specified in the COLR, and the Incore Alarm System or Excore Monitoring System shall be OPERABLE to monitor LH R.

APPLICABILITY: MODE 1 with THERMAL POWER > 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LHR, as determined by the A.1 Restore LHR to within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months automatic Incore Alarm limits.

System, not within limits specified in the COLR, as indicated by four or more coincident incore channels.

OR LHR, as determined by the Excore Monitoring System, not within limits specified in the COLR.

OR LHR, as determined by manual incore detector readings, not within limits specified in the COLR.

Palisades Nuclear Plant 3.2.1-1 Amendment No. 189

LHR 3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Incore Alarm and Excore B.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Monitoring Systems POWER to __85% RTP.

inoperable for monitoring LHR. AND B.2 Verify LHR is within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits using manual incore readings. AND Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thereafter C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to *25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 ---------------------- NOTE --------------

Only required to be met when the Incore Alarm System is being used to monitor LHR.

Verify LHR is within the limits specified in the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months COLR.

Palisades Nuclear Plant 3.2.1-2 Amendment No. 189

LHR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY i

SR 3.2.1.2 ------------------- NOTE---------------

Only required to be met when the Incore Alarm System is being used to monitor LHR.

Adjust incore alarm setpoints based on a Prior to operation measured power distribution. > 50% RTP after each fuel loading AND 31 EFPD thereafter SR 3.2.1.3 -------------------- NOTE--------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify measured ASI has been within 0.05 of Prior to each initial target ASI for last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . use of Excore Monitoring System to monitor LHR SR 3.2.1.4 ---------------------- NOTE--------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify THERMAL POWER is less than the APL. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Palisades Nuclear Plant 3.2.1-3 Amendment No. 189

LHR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.5 ---------------------- NOTE--------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify measured ASI is within 0.05 of target ASI. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.2.1.6 ---------------------- NOTE --------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify Tq *0.03. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Palisades Nuclear Plant 3.2.1-4 Amendment No. 189

Radial Peaking 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 TOTAL RADIAL PEAKING FACTOR (FRT)

LCO 3.2.2 FRT shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER > 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FRT not within limits A.1 Restore FRT to within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months specified in the COLR. limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify FRT is within limits specified in the COLR. Prior to operation

> 50% RTP after each fuel loading AND 31 EFPD thereafter Palisades Nuclear Plant 3.2.2-1 Amendment No. 41-8, 205

Tq 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 QUADRANT POWER TILT (Tq)

LCO 3.2.3 Tq shall be < 0.05.

APPLICABILITY: MODE 1 with THERMAL POWER > 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tq > 0.05. A.1 Verify FRT is within the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits of LCO 3.2.2, "TOTAL RADIAL AND PEAKING FACTOR Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , thereafter B. Tq> 0.10. B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 50% RTP.

C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 25% RTP.

Time not met.

OR Tq > 0.15.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify Tq is < 0.05. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.2.3-1 Amendment No. 4-88, 205

ASI 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 AXIAL SHAPE INDEX (ASI)

LCO 3.2.4 The ASI shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER > 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ASI not within limits A.1 Restore ASI to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months specified in COLR. limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 Verify ASI is within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.2.4-1 Amendment No. 189

RPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Protective System (RPS) Instrumentation LCO 3.3.1 Four RPS trip units, associated instrument channels, and associated Zero Power Mode (ZPM) Bypass removal channels for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

NOTE ----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE -------------- A.1 Place affected trip unit in 7 days Not applicable to High trip.

Startup Rate, Loss of Load, or ZPM Bypass Removal Functions.

One or more Functions with one RPS trip unit or associated instrument channel inoperable.

B. One High Startup Rate trip B.1 Restore trip unit and Prior to entering unit or associated associated instrument MODE 2 from instrument channel channel to OPERABLE MODE 3 inoperable, status.

Palisades Nuclear Plant 3.3.1-1 Amendment No. 189

RPS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One Loss of Load trip unit C.1 Restore trip unit and Prior to increasing or associated instrument associated instrument THERMAL POWER channel inoperable, channel to OPERABLE to > 17% RTP status. following entry into MODE 3 D. One or more ZPM Bypass D.1 Remove the affected Immediately Removal channels ZPM Bypasses.

inoperable.

OR D.2 Declare affected trip Immediately units inoperable.

E. --------- NOTE -------------- E.1 Place one trip unit in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Not applicable to ZPM Bypass Removal AND Function.

----------------- NOTE -------------------

Not applicable to High Startup One or more Functions Rate or Loss of Load Functions.

with two RPS trip units or associated instrument channels inoperable. E.2 Restore one trip unit and 7 days associated instrument channel to OPERABLE status.

F. Two power range F.1 Restrict THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months channels inoperable. POWER to _ 70% RTP.

Palisades Nuclear Plant 3.3.1-2 Amendment No. 4-89, 219

RPS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR G.2.1 Verify no more than one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months full-length control rod is Control room ambient air capable of being temperature > 90 0 F. withdrawn.

OR G.2.2 Verify PCS boron 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS

NOTE ----------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SR shall be performed for each Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform a CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2 Verify control room temperature is < 90 0 F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.3.1-3 Amendment No. 189

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.3 ------------------- NOTE---------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is > 15% RTP.

Perform calibration (heat balance only) and adjust 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the power range excore and AT power channels to agree with calorimetric calculation if the absolute difference is > 1.5%.

SR 3.3.1.4 --------------------- NOTE---------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is >25% RTP.

Calibrate the power range excore channels using 31 days the incore detectors.

SR 3.3.1.5 Perform a CHANNEL FUNCTIONAL TEST and 92 days verify the Thermal Margin Monitor Constants.

SR 3.3.1.6 Perform a calibration check of the power range 92 days excore channels with a test signal.

SR 3.3.1.7 Perform a CHANNEL FUNCTIONAL TEST of High Once within 7 days Startup Rate and Loss of Load Functions. prior to each reactor startup Palisades Nuclear Plant 3.3.1-4 Amendment No. 189

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.8 --------------------- NOTE-- -------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform a CHANNEL CALIBRATION. 18 months Palisades Nuclear Plant 3.3.1-5 Amendment No. 189

RPS Instrumentation 3.3.1.

Table 3.3.1-1 (page 1 of 2)

Reactor Protective System Instrumentation APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION MODES REQUIREMENTS VALUE

1. Variable High Power Trip 1,2 (a) (a) (a) SR 3.3.1.1 < 15% RTP above SR 3.3.1.2 current THERMAL SR 3.3.1.3 POWER with a SR 3.3.1.4 minimum of < 30%

SR 3.3.1.5 RTP and a SR 3.3.1.6 maximum of SR 3.3.1.8 *_109.4% RTP

2. High Startup Rate Trip(b) 1,2 SR 3.3.1.1 NA SR 3.3.1.7 SR 3.3.1.8

3. Low Primary Coolant 1,2 (a) (a) (a)

System Flow Trip(c) SR 3.3.1.1 > 95%

SR 3.3.1.5 SR 3.3.1.8

4. Low Steam Generator A Level Trip SR 3.3.1.1 > 25.9% narrow SR 3.3.1.5 range SR 3.3.1.8

5. LowSteam Generator B Level Trip 1,2,3(a)4(a)5(a) SR 3.3.1.1 > 25.9% narrow SR 3.3.1.5 range SR 3.3.1.8

6. Low Steam Generator A 1,,(a),4(a),5(a)

Pressure Trip(c) SR 3.3.1.1 > 500 psia SR 3.3.1.5 SR 3.3.1.8

7. Low Steam Generator B 1,,(a),4(a),5(a)

Pressure Trip(c) 1,, 4 5 SR 3.3.1.1 > 500 psia SR 3.3.1.5 SR 3.3.1.8

8. High Pressurizer 1,,(a),4(a),5(a)

Pressure Trip SR 3.3.1.1 < 2255 psia SR 3.3.1.5 SR 3.3.1.8 (a) With more than one full-length control rod capable of being withdrawn and PCS boron concentration less than REFUELING BORON CONCENTRATION.

(b) Trip may be bypassed when Wide Range Power is < 1 E-4% RTP or when THERMAL POWER is > 13% RTP.

(c) Trips may be bypassed when Wide Range Power is < 1 E-4% RTP. Bypass shall be automatically removed when Wide Range Power is > 1 E-4% RTP.

Palisades Nuclear Plant 3.3.1-6 Amendment No. 4-89, 2-08, 216

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 2)

Reactor Protective System Instrumentation APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION MODES REQUIREMENTS VALUE

9. Thermal Margin/

1,2,3(a)4(a)5(a) SR 3.3.1.1 Table 3.3.1-2 Low Pressure Trip(c)

SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.8

10. Loss of Load Trip 1 (d) SR 3.3.1.7 NA SR 3.3.1.8

11. Containment High 1 (a), (a) (a) SR 3.3.1.5 Pressure Trip < 3.70 psig SR 3.3.1.8

12. Zero Power Mode Bypass Automatic Removal 1,2, 3(a) 4 (a) 5 (a) SR 3.3.1.8 NA (a) With more than one full-length control rod capable of being withdrawn and PCS boron concentration less than REFUELING BORON CONCENTRATION.

(c) Trips may be bypassed when Wide Range Power is < 1E-4% RTP. Bypass shall be automatically removed when Wide Range Power is > 1E-4% RTP.

(d) When THERMAL POWER is > 17% RTP.

Palisades Nuclear Plant 3.3.1-7 Amendment No. 189

RPS Instrumentation 3.3.1 Table 3.3.1-2 (page 1 of 1)

Thermal Margin/Low Pressure Trip Function Allowable Value The Allowable Value for the Thermal Margin/Low Pressure Trip, Ptrip, is the higher of two values, Pmin and Pvar, both in psia:

Pmin 1750 Pvar 2012(QA)(QR1) + 17.0(Tin) - 9559 Where:

QA = - 0.720(ASI) + 1.028; when - 0.628_ ASI < - 0.100 QA = - 0.333(ASI) + 1.067; when - 0.100

ASI < + 0.200 QA = + 0.375(ASI) + 0.925; when + 0.200 < ASI < + 0.565 ASI = Measured ASI when Q > 0.0625 ASI = 0.0 when Q < 0.0625 QR 1 = 0.412(Q) + 0.588; when Q5*1.0 QR 1 = Q; when Q > 1.0 Q = THERMAL POWER/RATED THERMAL POWER Tin = Maximum primary coolant inlet temperature, in OF ASI, Tin, and Q are the existing values as measured by the associated instrument channel.

Palisades Nuclear Plant 3.3.1-8 Amendment No. 44-9, 214

RPS Logic and Trip Initiation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Reactor Protective System (RPS) Logic and Trip Initiation LCO 3.3.2 Six channels of RPS Matrix Logic, four channels of RPS Trip Initiation Logic, and two channels of RPS Manual Trip shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5, with more than one full-length control rod capable of being withdrawn and Primary Coolant System (PCS) boron concentration less than REFUELING BORON CONCENTRATION.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Matrix Logic channel A.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

B. One channel of Trip B.1 De-energize the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Initiation Logic inoperable, clutch power supplies.

C. One channel of Manual C.1 Restore channel to Prior to entering Trip inoperable. OPERABLE status. MODE 2 from MODE 3 D. Two channels of Trip D.1 De-energize the affected Immediately Initiation Logic affecting clutch power supplies.

the same trip leg inoperable.

Palisades Nuclear Plant 3.3.2-1 Amendment No. 189

RPS Logic and Trip Initiation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR E.2.1 Verify no more than one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months One or more Functions full-length control rod is with two or more Manual capable of being withdrawn.

Trip, Matrix Logic or Trip Initiation Logic channels OR inoperable for reasons other than Condition D.

E.2.2 Verify PCS boron 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform a CHANNEL FUNCTIONAL TEST on 92 days each RPS Matrix Logic channel and each RPS Trip Initiation Logic channel.

SR 3.3.2.2 Perform a CHANNEL FUNCTIONAL TEST on Once within 7 days each RPS Manual Trip channel. prior to each reactor startup Palisades Nuclear Plant 3.3.2-2 Amendment No. 189

ESF Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Engineered Safety Features (ESF) Instrumentation LCO 3.3.3 Four ESF bistables and associated instrument channels for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: As specified in Table 3.3.3-1.

ACTIONS

NOTE -------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------- NOTE --------------- A.1 Place affected bistable 7 days Not applicable to RAS. in trip.

One or more Functions with one ESF bistable or associated instrument channel inoperable.

B. ---------- NOTE ---------- B.1 Place one bistable in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Not applicable to RAS. trip.

AND One or more Functions with two ESF bistables or B.2 Restore one bistable 7 days associated instrument and associated channels inoperable. -instrument channel to OPERABLE status.

Palisades Nuclear Plant 3.3.3-1 Amendment No. 4-88-, 219

ESF Instrumentation 3.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One RAS bistable or C.1 Bypass affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated instrument bistable.

channel inoperable.

AND C.2 Restore bistable and 7 days associated instrument channel to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met for Functions 1, 2, 3, AND 4, or 7.

D.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met for Functions 5 or 6. AND E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Palisades Nuclear Plant 3.3.3-2 Amendment No. 189

ESF Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

NOTE ----------------------------------------------------------

Refer to Table 3.3.3-1 to determine which SR shall be performed for each Function.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform a CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.3.2 Perform a CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.3.3 Perform a CHANNEL CALIBRATION. 18 months Palisades Nuclear Plant 3.3.3-3 Amendment No. 189

ESF Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 2)

Engineered Safety Features Instrumentation APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION MODES REQUIREMENTS VALUE

1. Safety Injection Signal (SIS)

a. Pressurizer Low Pressure 1,2,3 SR 3.3.3.1 > 1593 psia SR 3.3.3.2 SR 3.3.3.3

2. Steam Generator Low Pressure Signal (SGLP)

a. Steam Generator A Low 1, 2 (a),3 (a) SR 3.3.3.1 > 500 psia Pressure SR 3.3.3.2 SR 3.3.3.3

b. Steam Generator B Low 1, 2 (a), 3 (a) SR 3.3.3.1 > 500 psia Pressure SR 3.3.3.2 SR 3.3.3.3

3. Recirculation Actuation Signal (RAS)

a. SIRWT Low Level 1,2,3 SR 3.3.3.3 21 inches and

<27 inches abovetank bottom

4. Auxiliary Feedwater Actuation Signal (AFAS)

a. Steam Generator A Low 1,2,3 SR 3.3.3.1 > 25.9%

Level SR 3.3.3.2 narrow range SR 3.3.3.3

b. Steam Generator B Low 1,2,3 SR 3.3.3.1 Ž 25.9%

Level SR 3.3.3.2 narrow range SR 3.3.3.3 (a) Not required to be OPERABLE when all Main Steam Isolation Valves (MSIVs) are closed and deactivated, and all Main Feedwater Regulating Valves (MFRVs) and MFRV bypass valves are either closed and deactivated, or isolated by closed manual valves.

Palisades Nuclear Plant 3.3.3-4 Amendment No. 189

ESF Instrumentation 3.3.3 Table 3.3.3-1 (page 2 of 2)

Engineered Safety Features Instrumentation APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION MODES REQUIREMENTS VALUE

5. Containment High Pressure (CHP)

a. Containment High Pressure

- Left Train 1,2,3,4 SR 3.3.3.2 > 3.7 psig SR 3.3.3.3 and

< 4.3 psig

b. Containment High Pressure

- Right Train 1,2,3,4 SR 3.3.3.2 > 3.7 psig SR 3.3.3.3 and

!54.3 psig

6. Containment High Radiation Signal (CHR)

a. Containment High Radiation 1,2,3,4 SR 3.3.3.1 <-20 R/hour SR 3.3.3.2 SR 3.3.3.3

7. Automatic Bypass Removals

a. Pressurizer Low Pressure 1,2,3 SR 3.3.3.3 < 1700 psia Bypass

b. Steam Generator A Low 1, 2 (a), 3 (a) SR 3.3.3.3 < 565 psia Pressure Bypass

c. Steam Generator B Low SR 3.3.3.3 < 565 psia 1, 2 (a),3 (a)

Pressure Bypass (a) Not required to be OPERABLE when all Main Steam Isolation Valves (MSIVs) are closed and deactivated, and all Main Feedwater Regulating Valves (MFRVs) and MFRV bypass valves are either closed and deactivated, or isolated by closed manual valves.

Palisades Nuclear Plant 3.3.3-5 Amendment No. 189

ESF Logic and Manual Initiation 3.3.4 3.3 INSTRUMENTATION 3.3.4 Engineered Safety Features (ESF) Logic and Manual Initiation LCO 3.3.4 Two ESF Manual Initiation and two ESF Actuation Logic channels and associated bypass removal channels shall be OPERABLE for each ESF Function specified in Table 3.3.4-1.

APPLICABILITY: According to Table 3.3.4-1.

ACTIONS

NOTE-------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months one Manual Initiation, Bypass OPERABLE status.

Removal, or Actuation Logic channel inoperable.

B. One or more Functions with B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months two Manual Initiation, Bypass Removal, or Actuation Logic AND channels inoperable for Functions 1, 2, 3, or 4. B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months OR Required Action and associated Completion Time of Condition A not met for Functions 1, 2, 3, or 4.

Palisades Nuclear Plant 3.3.4-1 Amendment No. 189

ESF Logic and Manual Initiation 3.3.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions with C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months two Manual Initiation, or Actuation Logic channels AND inoperable for Functions 5 or 6. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Required Action and associated Completion Time of Condition A not met for Functions 5 or 6.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform functional test of each SIS actuation 92 days channel normal and standby power functions.

SR 3.3.4.2 Perform a CHANNEL FUNCTIONAL TEST of each 92 days AFAS actuation logic channel.

SR 3.3.4.3 Perform a CHANNEL FUNCTIONAL TEST. 18 months Palisades Nuclear Plant 3.3.4-2 Amendment No. 189

ESF Logic and Manual Initiation 3.3.4 Table 3.3.4-1 (page 1 of 1)

Engineered Safety Features Actuation Logic and Manual Initiation APPLICABLE FUNCTION MODES

1. Safety Injection Signal (SIS)(a) .1,2,3

2. Steam Generator Low Pressure Signal 1,2 (d), 3 (d)

(SG LP)(b)(c)

3. Recirculation Actuation Signal (RAS) 1,2,3

4. Auxiliary Feedwater Actuation Signal (AFAS) 1,2,3

5. Containment High Pressure Signal (CHP)(c) 1,2,3,4

6. Containment High Radiation Signal (CHR) 1,2,3,4 (a) SIS actuation by Pressurizer Low Pressure may be manually bypassed when pressurizer pressure is < 1700 psia. The bypass shall be automatically removed whenever pressurizer pressure is > 1700 psia.

(b) SGLP actuation may be manually bypassed when SG pressure is < 565 psia. The bypass shall be automatically removed whenever steam generator pressure is

> 565 psia.

(c) Manual Initiation may be achieved by individual component controls.

(d) Not required to be OPERABLE when all Main Steam Isolation Valves (MSIVs) are closed and deactivated, and all Main Feedwater Regulating Valves (MFRVs) and MFRV bypass valves are either closed and deactivated, or isolated by closed manual valves.

Palisades Nuclear Plant 3.3.4-3 Amendment No. 189

DG - UV Start 3.3.5 3.3 INSTRUMENTATION 3.3.5 Diesel Generator (DG) - Undervoltage Start (UV Start)

LCO 3.3.5 Three channels of Loss of Voltage Function and three channels of Degraded Voltage Function auto-initiation instrumentation and associated logic channels for each DG shall be OPERABLE.

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter applicable Immediately with one channel per DG Conditions and inoperable. Required Actions for the associated DG made inoperable by DG - UV Start instrumentation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform a CHANNEL FUNCTIONAL TEST on 18 months each DG-UV start logic channel.

Palisades Nuclear Plant 3.3.5-1 Amendment No. 189

DG - UV Start 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1-SR 3.3.5.2 Perform CHANNEL CALIBRATION on each Loss 18 months of Voltage and Degraded Voltage channel with setpoints as follows:

a. Degraded Voltage Function Ž 2187 V and

< 2264 V Time delay: > 0.5 secondsand

< 0.8 seconds; and

b. Loss of Voltage Function > 1780 V and

< 1940 V Time delay: > 5.45 seconds and 5 8.15 seconds at 1400 V.

Palisades Nuclear Plant 3.3.5-2 Amendment No. 189

Refueling CHR Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Refueling Containment High Radiation (CHR) Instrumentation LCO 3.3.6 Two Refueling CHR Automatic Actuation Function channels and two CHR Manual Actuation Function channels shall be OPERABLE.

APPLICABILITY: During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.I" Place the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with one channel channel in trip.

inoperable.

OR A.2.1 Suspend CORE 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ALTERATIONS.

AND A.2.2 Suspend movement of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months irradiated fuel assemblies within containment.

B. One or more Functions B.1 Suspend CORE Immediately with two channels ALTERATIONS.

inoperable.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

Palisades Nuclear Plant 3.3.6-1 Amendment No. 189

Refueling CHR Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform a CHANNEL CHECK of each refueling 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months CHR monitor channel.

SR 3.3.6.2 Perform a CHANNEL FUNCTIONAL TEST of each 31 days refueling CHR monitor channel.

SR 3.3.6.3 Perform a CHANNEL FUNCTIONAL TEST of each 18 months CHR Manual Initiation channel.

SR 3.3.6.4 Perform a CHANNEL CALIBRATION of each 18 months refueling CHR monitor channel.

Palisades Nuclear Plant 3.3.6-2 Amendment No. 189

PAM Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.7 The PAM instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

-NOTES

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required 30 days

ýwith one required channel channel to OPERABLE inoperable, status.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.

met.

C. One or more C.1 Restore one channel to 7 days Functions with two OPERABLE status.

required channels inoperable.

Palisades Nuclear Plant 3.3.7-1 Amendment No. 4-99, 24-9, 221

PAM Instrumentation 3.3.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (Not Used)

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C not Table 3.3.7-1 for the met. channel.

F. As required by Required F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action E.1 and referenced in Table 3.3.7-1. AND F.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months G. As required by Required G.1 Initiate action in Immediately Action E.1 and referenced accordance with in Table 3.3.7-1. Specification 5.6.6.

Palisades Nuclear Plant 3.3.7-2 Amendment No. 4-89, 221

PAM Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS

NOTE ------------------------------------------------------------

These SRs apply to each PAM instrumentation Function in Table 3.3.7-1.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.7.2 ------------------ NOTE ----------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Palisades Nuclear Plant 3.3.7-3 Amendment No. 189

PAM Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION E.1

1. Primary Coolant System Hot Leg Temperature (wide range) 2 F

2. Primary Coolant System Cold Leg 2 F Temperature (wide range)

3. Wide Range Neutron Flux 2

4. Containment Floor Water Level 2 (wide range)

5. Subcooled Margin Monitor 2

6. Pressurizer Level (wide range), 2

7. (Deleted)

8. Condensate Storage Tank Level 2

9. Primary Coolant System Pressure 2 (wide range)

10. Containment Pressure (wide range) 2

11. Steam Generator A Water Level 2 (wide range)

12. Steam Generator B Water Level 2 (wide range)

13. Steam Generator A Pressure 2

14. Steam Generator B Pressure 2

15. Containment Isolation Valve Position 1 per valve(a) 16, Core Exit Temperature - Quadrant 1 4

17. Core Exit Temperature - Quadrant 2 4

18. Core Exit Temperature - Quadrant 3 4

19. Core Exit Temperature - Quadrant 4 4

20. Reactor Vessel Water Level 2

21. Containment Area Radiation 2 (high range)

(a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valvesecured.

Palisades Nuclear Plant 3.3.7-4 Amendment No. 4-89, 221

Alternate Shutdown System 3.3.8 3.3 INSTRUMENTATION 3.3.8 Alternate Shutdown System LCO 3.3.8 The Alternate Shutdown System Functions in Table 3.3.8-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

7 ..--------------------NOTE-------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable. Functions to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Palisades Nuclear Plant 3.3.8-1 Amendment No. 4-8w, 219

Alternate Shutdown System 3.3.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL FUNCTIONAL TEST of the Once within 7 days Source Range Neutron Flux Function. prior to each reactor startup SR 3.3.8.2 Verify each required control circuit and transfer 18 months switch is capable of performing the intended function.

SR 3.3.8.3 --------------------- NOTES --------------

1. Not required for Functions 16, 17, and 18.

2. Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each 18 months required instrumentation channel.

Palisades Nuclear Plant 3.3.8-2 Amendment No. 189

Alternate Shutdown System 3.3.8 Table 3.3.8-1 (page 1 of 1)

Alternate Shutdown System Instrumentation and Controls FUNCTION, INSTRUMENT REQUIRED OR CONTROL PARAMATER CHANNELS

1. Source Range Neutron Flux 1

2. Pressurizer Pressure 1

3. Pressurizer Level 1

4. Primary Coolant System (PCS) #1 Hot Leg Temperature 1

5. PCS #2 Hot Leg Temperature 1

6. PCS #1 Cold Leg Temperature 1

7. PCS #2 Cold Leg Temperature 1

8. Steam Generator (SG) A Pressure 1

9. SG B Pressure 1

10. SG A Wide Range Level 1

11. SG B Wide Range Level 1

12. Safety Injection Refueling Water (SIRW) Tank Level 1

13. Auxiliary Feedwater (AFW) Flow Indication to SG A 1

14. AFW Flow Indication to SG B 1

15. AFW Low Suction Pressure Alarm (P-8B) 1

16. AFW Pump P-8B Steam Supply Valve Control 1

17. AFW Flow Control to SG A 1

18. AFW Flow Control to SG B 1 Palisades Nuclear Plant 3.3.8-3 Amendment No. 189

Neutron Flux Monitoring Channels 3.3.9 3.3 INSTRUMENTATION 3.3.9 Neutron Flux Monitoring Channels LCO 3.3.9 Two channels of neutron flux monitoring instrumentation shall be OPERABLE.

APPLICABILITY: MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend all operations Immediately channel(s) inoperable, involving positive reactivity additions.

AND A.2 Perform SDM 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months verification in accordance with AND SR 3.1.1.1.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

thereafter Palisades Nuclear Plant 3.3.9-1 Amendment No. 189

Neutron Flux Monitoring Channels 3.3.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.9.2 --------------------- NOTE----------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Palisades Nuclear Plant 3.3.9-2 Amendment No. 189

ESRV Instrumentation 3.3.10 3.3 INSTRUMENTATION 3.3.10 Engineered Safeguards Room Ventilation (ESRV) Instrumentation LCO 3.3.10 Two channels of ESRV Instrumentation shall be OPERABLE.

APPLICABILITY: MODES 1,2, 3, and 4.

ACTIONS

NOTE -------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Initiate action to isolate Immediately inoperable, the associated ESRV System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform a CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.10.3 Perform a CHANNEL CALIBRATION. 18 months Verify high radiation setpoint on each ESRV Instrumentation radiation monitoring channel is 5 2.2E+5 cpm.

Palisades Nuclear Plant 3.3.10-1 Amendment No. 189

PCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 PRIMARY COOLANT SYSTEM (PCs) 3.4.1 PCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 PCS DNB parameters for pressurizer pressure, cold leg temperature, and PCS total flow rate shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer pressure, PCS A.1 Restore parameter(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months cold leg temperature, or within limit.

PCS total flow rate not within limits.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Palisades Nuclear Plant 3.4.1-1 Amendment No. 489, 217

PCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure within the limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR.

SR 3.4.1.2 Verify PCS cold leg temperature within the limit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR.

SR 3.4.1.3 -- ------------------ NOTE ---------------

Not required to be performed until 31 EFPD after THERMAL POWER is Ž 90% RTP.

Verify PCS total flow rate within the limit specified 18 months in the COLR.

AND After each plugging of 10 or more steam generator tubes Palisades Nuclear Plant 3.4.1-2 Amendment No. 4-&G, 217

PCS Minimum Temperature for Criticality 3.4.2 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.2 PCS Minimum Temperature for Criticality LCO 3.4.2 Each PCS loop average temperature (Tave) shall be _>525TF.

APPLICABILITY: MODE 1 MODE 2 with Keff 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tave in one or more PCS A.1 Be in MODE 2 with Keff 30 minutes loops not within limit. < 1.0.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify PCS Tave in each loop Ž 5250 F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.4.2-1 Amendment No. 189

PCS P/T Limits 3.4.3 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.3 PCS Pressure and Temperature (P/T) Limits LCO 3.4.3 PCS pressure, PCS temperature, and PCS heatup and cooldown rates shall be maintained-within the limits of Figure 3.4.3-1 and Figure 3.4.3-2.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE -------------- A.1 Restore parameter(s) to 30 minutes Required Action A.2 shall within limits.

be completed whenever this Condition is entered. AND A.2 Determine PCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Requirements of LCO not acceptable for continued met in MODE 1, 2, 3, or 4. operation.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5 with 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PCS pressure

< 270 psia.

Palisades Nuclear Plant 3.4.3-1 Amendment No. 189

PCS P/T Limits 3.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. --------- NOTE 1---------C Initiate action to restore Immediately Required Action C.2 shall parameter(s) to within be completed whenever limits.

this Condition is entered.

AND Requirements of LCO not C.2 Determine PCS is Prior to entering met any time in other than acceptable for continued MODE 4 MODE 1, 2, 3, or 4. operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 ---------------------- NOTE--------------

Only required to be performed during PCS heatup and cooldown operations.

Verify PCS pressure, PCS temperature, and PCS 30 minutes heatup and cooldown rates are within the limits of Figure 3.4.3-1 and Figure 3.4.3-2.

Palisades Nuclear Plant 3.4.3-2 Amendment No. 189

PCS P/T Limits 3.4.3 2250 i

2000 4 0 F/Hr

-- M- 20 F/Hr 1750 -A- 40 F/Hr 0~

60 F/Hr 1500 -x-- 80 F/Hr /

U) 100 F/Hr U) 0, 1L CL

1. 1250 I a,

N

.4 1.

U)

U) 1000 ,/

U, L.

0-750 ,,/

(I RV Inlet Avg. Hrly.

Temperature H/U Limit T

170F 20"F/Hr.

250 Ž T > 170F 40"F/Hr.

K 350 > T > 250F 60"F/Hr.0 T Ž 350F 100"F/Hr.

.4

When shutdown coolinq isolation

-4 valves MO-3015 and MO-3016 are Zb:0 #* I + I ~-.! 4-open, PCS heatup rate shall be maintained S 40"F/Hr.

J 0 -lti i :1I l iI It It hri t Ililt [ I[Ib i rrIit tn 50 100 150 200 250 300 350 400 4530 RV Inlet Temperature, F Figure 3.4.3-1 (Page 1 of 1)

Pressure - Temperature Limits for Heatups Palisades Nuclear Plant 3.4.3-3 Amendment No. 189

PCS P/T Limits 3.4.3 2250-2000-- -

- 0 F/Hr U20 F/Hr r-4 1750 A- 40 F/Hr 0- e 60 F/Hr L )K 80 F/Hr

0 U) --- 100 F/Hr 1..

0~

0-1250 N

r1~

1000-0-

7WWI*/ .

r RV Inlet Avg. Hrly.

~nI 2 Temperature C/ Limit U-'JJv7 250 ý T T

170F

> 170F 40F/Hr.

40F/Hr.

350 > T > 250"F 60"F/Hr.

T 1_350F 100"F/Hr.

Il Lq i i 50 100 150 200 250 300 350 400 450 RV Inlet Temperature, F Additional restrictions wI hen head is on reactor vessel:

1. Maintain average c ore exit temperature:

135°F > T > 110'F for> 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

2. Following completi on of item 1, maintain average hourly cooldown (CI/D) limit of 20°F/hour based on core exit temperati ire indication.

Figure 3.4.3-2 (Page 1, of 1)

Pressure - Temperature Limits for Cooldown Palisades Nuclear Plant 3.4.3-4 Amendment No. 489, 218

PCS Loops - MODES 1 and 2 3.4.4 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.4 PCS Loops - MODES 1 and 2 LCO 3.4.4 Two PCS loops shall be OPERABLE and in operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO not A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each PCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.4.4-1 Amendment No. 189

PCS Loops - MODE 3 3.4.5 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.5 PCS Loops - MODE 3 LCO 3.4.5 Two PCS loops shall be OPERABLE and one PCS loop shall be in operation.

-- ---------------------------NOTES ----------------------

1. All primary coolant pumps may not be in operation for _<1 hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. No operations are permitted that would cause reduction of the PCS boron concentration; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. Forced circulation (starting the first primary coolant pump) shall not be initiated unless one of the following conditions is met:

a. PCS cold leg temperature (To) is > 4301F;

b. Steam Generator (SG) secondary temperature is equal to or less than the reactor inlet temperature (To);

c. SG secondary temperature is < 100°F above T,, and shutdown cooling is isolated from the PCS, and PCS heatup/cooldown rate is _<10°F/hour; or

d. SG secondary temperature is < 1000 F above To, and shutdown cooling is isolated from the PCS, and pressurizer level is < 57%.

APPLICABILITY: MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required PCS loop A.1 Restore required PCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, loop to OPERABLE status.

Palisades Nuclear Plant 3.4.5-1 Amendment No. 189

PCS Loops - MODE 3 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition A not met.

C. No PCS loop OPERABLE. C.1 Suspend all operations Immediately involving a reduction of OR PCS boron concentration.

No PCS loop in operation.

AND C.2 Initiate action to restore Immediately one PCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required PCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify secondary side water level in each steam 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months generator > -84%.

SR 3.4.5.3 Verify correct breaker alignment and indicated 7 days power available to the required primary coolant pump that is not in operation.

Palisades Nuclear Plant 3.4.5-2 Amendment No. 189

PCS Loops - MODE 4 3.4.6 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.6 PCS Loops - MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of PCS loops and Shutdown Cooling (SDC) trains shall be OPERABLE, and either:

a. One PCS loop shall be in operation; or

b. One SDC train shall be in operation with > 2810 gpm flow through the reactor core.

NOTES ------------------------

1. All Primary Coolant Pumps (PCPs) and SDC pumps may not be in operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. No operations are permitted that would cause reduction of the PCS boron concentration; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. Forced circulation (starting the first PCP) shall not be initiated unless one of the following conditions is met:

a. Steam Generator (SG) secondary temperature is equal to or less than the reactor inlet temperature (To),

b. SG secondary temperature is < 100°F above Tc, and shutdown cooling is isolated from the PCS, and PCS heatup/cooldown rate is < 100 F/hour,

c. SG secondary temperature is < 1001F above To, and shutdown cooling is isolated from the PCS, and pressurizer level is < 57%.

3. Primary coolant pumps P-50A and P-50B shall not be operated simultaneously.

APPLICABILITY: MODE 4.

Palisades Nuclear Plant 3.4.6-1 Amendment No. 189

PCS Loops - MODE 4 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One PCS loop inoperable. A.1 Initiate action to restore a Immediately second PCS loop or one AND SDC train to OPERABLE status.

Two SDC trains inoperable.

B. One SDC train inoperable. B.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND Two PCS loops inoperable.

C. No PCS loops or SDC trains C.1 Suspend all operations Immediately OPERABLE. involving reduction of PCS boron concentration.

OR AND No PCS loop in operation with SDC flow through the C.2.1 Initiate action to restore Immediately reactor core not within one PCS loop to limits. OPERABLE status and operation.

OR C.2.2 Initiate action to restore Immediately one SDC train to OPERABLE status and operation with > 2810 gpm flow through the reactor core.

Palisades Nuclear Plant 3.4.6-2 Amendment No. 189

PCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one SDC train is in operation with > 2810 gpm 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months flow through the reactor core, or one PCS loop is in operation.

SR 3.4.6.2 Verify secondary side water level in required SG(s) is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> -84%.

SR 3.4.6.3 Verify correct breaker alignment and indicated power 7 days available to the required pump that is not in, operation.

Palisades Nuclear Plant 3.4.6-3 Amendment No. 189

PCS Loops - MODE 5, Loops Filled 3.4.7 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.7 PCS Loops - MODE 5, Loops Filled LCO 3.4.7 One Shutdown Cooling (SDC) train shall be OPERABLE and in operation.

with _>2810 gpm flow through the reactor core, and either:

a. One additional SDC train shall be OPERABLE; or

b. The secondary side water level of each Steam Generator (SG) shall be > -84%.

----------------------NOTES ------------------------

1. The SDC pump of the train in operation may not be in operation for

< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause reduction of the PCS boron concentration; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. Both SDC trains may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing or maintenance provided:

a. One SDC train is providing the required flow through the reactor core;

b. Core outlet temperature is maintained at least 10°F below saturation temperature; and

c. Each SG secondary side water level is >_-84%.

3. Forced circulation (starting the first primary coolant pump) shall not be initiated unless one of the following conditions is met:

a. SG secondary temperature is equal to or less than the reactor inlet temperature (To);

b. SG secondary temperature is < 100°F above To, and shutdown cooling is isolated from the PCS, and PCS heatup/cooldown rate is < 100 F/hour; or

c. SG secondary temperature is < 100OF above To, and shutdown cooling is isolated from the PCS, and pressurizer level is _<57%.

4. Primary coolant pumps P-50A and P-50B shall not be operated simultaneously.

5. All SDC trains may not be in operation during planned heatup to MODE 4 when at least one PCS loop is in operation.

APPLICABILITY: MODE 5 with PCS loops filled.

Palisades Nuclear Plant 3.4.7-1 Amendment No. 189

PCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SDC train inoperable. A.1 Initiate action to restore a Immediately second SDC train to AND OPERABLE status.

Any SG with secondary side OR water level not within limit.

A.2 Initiate action to restore Immediately SG secondary side water levels to within limits.

B. Two SDC trains inoperable. B.1 Suspend all operations Immediately involving reduction in OR PCS boron concentration.

SDC flow through the AND reactor core not within limits. B.2 Initiate action to restore Immediately one SDC train to OPERABLE status and operation with _>2810 gpm flow through the reactor core.

Palisades Nuclear Plant .3.4.7-2 Amendment No. 189

PCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one SDC train is in operation with Ž>2810 gpm 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months flow through the reactor core.

SR 3.4.7.2 Verify required SG secondary side water level is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

_-84%.

SR 3.4.7.3 Verify correct breaker alignment and indicated power 7 days available to the required SDC pump that is not in operation.

Palisades Nuclear Plant 3.4.7-3 Amendment No. 189

PCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.8 PCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two Shutdown Cooling (SDC) trains shall be OPERABLE, and either:

a. One SDC train in operation with > 2810 gpm flow through the reactor core; or

b. One SDC train in operation with _ 650 gpm flow through the reactor core with two of the three charging pumps incapable of reducing the boron concentration in the PCS below the minimum value necessary to maintain the required SHUTDOWN MARGIN.

NOTES

1. All SDC pumps may not be in operation for _ 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided:

a. No operations are permitted that would cause a reduction of the PCS boron concentration;

b. Core outlet temperature is maintained > 10°F below saturation temperature; and

c. No draining operations to further reduce the PCS water volume are permitted.

2. One SDC train may be inoperable for _<2 hours for surveillance testing provided the other SDC train is OPERABLE and in operation.

APPLICABILITY: MODE 5 with PCS loops not filled.

Palisades Nuclear Plant 3.4.8-1 Amendment No. 189

PCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SDC train inoperable. A.1 Initiate action to restore Immediately SDC train to OPERABLE status.

B. Two SDC trains B.1 Suspend all operations Immediately inoperable, involving reduction of PCS boron OR concentration.

SDC flow through the AND reactor core not within limits. B.2 Initiate action to restore Immediately one SDC train to OPERABLE status and operation with SDC flow through the reactor core within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 ---------------------- NOTE --------------

Only required to be met when complying with LCO 3.4.8.a.

Verify one SDC train is in operation with 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Ž2810 gpm flow through the reactor core.

Palisades Nuclear Plant 3.4.8-2 Amendment No. 189

PCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE FREQUENCY SR 3.4.8.2 --------------------- NOTE --------------

Only required to be met when complying with LCO 3.4.8.b.

Verify one SDC train is in operation with _>650 gpm 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months flow through the reactor core.

SR 3.4.8.3 ---------------------- NOTE -------------

Only required to be met when complying with LCO 3.4.8.b.

Verify two of three charging pumps are incapable 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of reducing the boron concentration in the PCS below the minimum value necessary to maintain the required SHUTDOWN MARGIN.

SR 3.4.8.4 Verify correct breaker alignment and indicated 7 days power available to the SDC pump that is not in operation.

Palisades Nuclear Plant 3.4.8-3 Amendment No. 189

Pressurizer 3.4.9 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level < 62.8%;

NOTE -------------------------------------------

The pressurizer water level limit does not apply in MODE 3 until after a bubble has been established in the pressurizer and the pressurizer water level has been lowered to within its normal operating band.

b. _ 375 kW of pressurizer heater capacity available from electrical bus 1 D, and

c. _ 375 kW of pressurizer heater capacity available from electrical bus 1 E with the capability of being powered from an emergency power supply.

APPLICABILITY: MODES 1, 2, and 3.,

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level not A.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit, reactor tripped.

AND A.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Palisades Nuclear Plant 3.4.9-1 Amendment No. 189

Pressurizer 3.4.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. < 375 kW pressurizer B.i Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months heater capacity available pressurizer heaters to from electrical bus 1 D, or OPERABLE status.

electrical bus 1 E, OR Required pressurizer heater capacity from electrical bus 1 E not capable of being powered from an emergency power supply.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B not AND met.

C;2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 ---------------------- NOTE --------------

Not required to be met until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after establishing a bubble in the pressurizer and the pressurizer water level has been lowered to within its normal operating band.

Verify pressurizer water level is < 62.8%. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.4.9-2 Amendment No. 189

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify the capacity of pressurizer heaters from 18 months electrical bus 1 D, and electrical bus 1 E is

_ 375 kW.

SR 3.4.9.3 Verify the required pressurizer heater capacity 18 months from electrical bus 1 E is capable of being powered from an emergency power supply.

Palisades Nuclear Plant 3.4.9-3 Amendment No. 189

Pressurizer Safety Valves 3.4.10 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings as specified in Table 3.4.10-1.

APPLICABILITY: MODES 1 and 2, MODE 3 with all PCS cold leg temperatures >_4301F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Reduce any PCS cold 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months leg temperature Two or more pressurizer

<430 0 F.

safety valves inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE In accordance with in accordance with the Inservice Testing Program. the Inservice Testing Following testing, lift settings shall be within +/- 1% Program of required setpoint.

Palisades Nuclear Plant 3.4.10-1 Amendment No. 189

Pressurizer Safety Valves 3.4.10 Table 3.4.10-1 (page 1 of 1)

Pressurizer Safety Valve Lift Settings VALVE NUMBER LIFT SETTING (psia + 3%)

RV-1 039 2580 RV-1040 2540 RV-1 041 2500 Palisades Nuclear Plant 3.4.10-2 Amendment No. 189

Pressurizer PORVs 3.4.11 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with all PCS cold leg temperatures _ 4300 F.

ACTIONS

NOTE-- -------------------------------

Separate Condition entry is allowed for each PORV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One PORV inoperable. A.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valve.

AND A.2 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. One block valve B.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, in manual control.

AND B.2 Restore block valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

Palisades Nuclear Plant 3.4.11-1 Amendment No. 4-8-, 219

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Two PORVs inoperable. C.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valves.

AND C.2 Restore at least one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months PORV to OPERABLE status.

D. Two block valves D.1 Place associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. PORVs in manual control.

AND D.2 Restore at least one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months block valve to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Palisades Nuclear Plant 3.4.1 1-2 Amendment No. 189

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Perform a complete cycle of each block valve. Once prior to entering MODE 4 from MODE 5 if not performed within previous 92 days SR 3.4.11.2 Perform a complete cycle of each PORV with PCS 18 months average temperature > 2000 F.

Palisades Nuclear Plant 3.4.11-3 Amendment No. 189

LTOP System 3.4.12 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with:

a. Both High Pressure Safety Injection (HPSI) pumps incapable of injecting into the PCS, and NOTES ----------------------

1. LCO 3.4.12.a is only required when any PCS cold leg temperature is < 3000 F.

2. LCO 3.4.12.a does not prohibit the use of the HPSI pumps for emergency addition of makeup to the PCS.

b. One of the following pressure relief capabilities:

1. Two Power Operated Relief Valves (PORVs) with lift settings as specified in Figure 3.4.12-1; or

2. The PCS depressurized and a PCS vent capable of relieving _>167 gpm at a pressure of 315 psia.

APPLICABILITY: MODE 3 when any PCS cold leg temperature is < 430 0 F, MODES 4 and 5, MODE 6 when the reactor vessel head is on.

ACTIONS

NOTE -----------------------------

LCO 3.0.4.b is not applicable to PORVs when entering MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two HPSI pumps A.1 Initiate action to verify Immediately capable of injecting into no HPSI pump is the PCS. capable of injecting into the PCS.

Palisades Nuclear Plant 3.4.12-1 Amendment No. 4--9, 219

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One required PORV B.1 Restore required PORV 7 days inoperable and pressurizer to OPERABLE status.

water level < 57%.

C. One required PORV C.1 Restore required PORV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable and pressurizer to OPERABLE status.

water level > 57%.

D. Two required PORVs D.1 Depressurize PCS and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable, establish PCS vent capable of relieving OR >- 167 gpm at a PCS pressure of 315 psia.

Required Action and associated Completion Time not met.

OR LTOP System inoperable for any reason other than Condition A, B, or C.

Palisades Nuclear Plant 3.4.12-2 Amendment No. 189

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 --------------------- NOTE -------------

Only required to be met when complying with LCO 3.4.12.a.

Verify both HPSI pumps are incapable of injecting 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months into the PCS.

SR 3.4.12.2 Verify required PCS vent, capable of relieving 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for

_ 167 gpm at a PCS pressure of 315 psia, is open. unlocked open vent valve(s)

AND 31 days for locked open vent valve(s)

SR 3.4.12.3 Verify PORV block valve is open for each required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months PORV.

SR 3.4.12.4 --------------------- NOTE -------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing any PCS cold leg temperature to

< 4301F.

Perform CHANNEL FUNCTIONAL TEST on each 31 days required PORV, excluding actuation.

SR 3.4.12.5 Perform CHANNEL CALIBRATION on each 18 months required PORV actuation channel.

Palisades Nuclear Plant 3.4.12-3 Amendment No. 189

LTOP System 3.4.12 2250--

2000 1750 a;.

L 1500 0

L CL.

L 1 "*** '

4)

//

N

-I L

CL 1000 750 500 250 0

I I I 50 100 150 200 250 300 350 400 450 RV Inlet Temperature, F Figure 3.4.12-1 (Page 1 of 1)

LTOP Setpoint Limit Palisades Nuclear Plant 3.4.12-4 Amendment No. 189

PCS Operational LEAKAGE 3.4.13 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.13 PCS Operational LEAKAGE LCO 3.4.13 PCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. PCS operational A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits within limits.

for reasons other than pressure boundary LEAKAGE or primary to secondary leakage.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Pressure boundary LEAKAGE exists.

OR Primary to secondary LEAKAGE not within limit.

Palisades Nuclear Plant 3.4.13-1 Amendment No. 4-89, 223

PCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------------------- NOTES ------------- ----------- NOTE--------

1. Not required to be performed in MODE 3 or 4 Only required to be until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation. performed during steady state

2. Not applicable to primary to secondary operation LEAKAGE.

Verify PCS operational LEAKAGE is within limits 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by performance of PCS water inventory balance.

SR 3.4.13.2 --------------------- NOTE -------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is <150 72 Hours SG.

gallons per day through any one Palisades Nuclear Plant 3.4.13-2 Amendment No. 4-89, 223

PCS PIV Leakage 3.4.14 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.14 PCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each PCS PIV shall be within limits and both Shutdown Cooling (SDC) suction valve interlocks shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3, MODE 4, except during the SDC mode of operation, or transition to or from, the SDC mode of operation.

ACTIONS

NOTES ------------------------------

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an

.inoperable PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths -------------- NOTE ---------

with leakage from one or Each valve used to satisfy more PCS PIVs not within Required Action A.1 must have limit, been verified to meet SR 3.4.14.1 and be on the PCS pressure boundary or the high pressure portion of the system.

(continued)

Palisades Nuclear Plant 3.4.14-1 Amendment No. 189

PCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND A.2 Restore PCS PIV 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. One or both SDC suction C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valve interlocks penetration by use of inoperable. one closed deactivated valve.

Palisades Nuclear Plant 3.4.14-2 Amendment No. 189

PCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 --------------------- NOTES --------------

1. Only required tobe performed in MODES 1 and 2.

2. Leakage rates _< 5.0 gpm are unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible leakage rate of 5.0 gpm by 50%

or greater.

3. Minimum test differential pressure shall not be less than 150 psid.

Verify leakage from each PCS PIV is equivalent to 18 months

_ 5 gpm at a PCS pressure of 2060 psia.

AND Once prior to entering MODE 2 whenever the plant has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months SR 3.4.14.2 Verify each SDC suction valve interlock prevents its 18 months associated valve from being opened with a simulated or actual PCS pressure signal __280 psia.

Palisades Nuclear Plant 3.4.14-3 Amendment No. 189

PCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.3 ---------------

NOTE---------------

Only required to be performed in MODES 1 and 2.

Prior to entering Verify each of the four Low Pressure Safety MODE 2 after each Injection (LPSI) check valves are closed. use of the LPSI check valves for SDC Palisades Nuclear Plant 3.4.14-4 Amendment No. 189

PCS Leakage Detection Instrumentation 3.4.15 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.15 PCS Leakage Detection Instrumentation LCO 3.4.15 Three of the following PCS leakage detection instrumentation channels shall be OPERABLE:

a'. One containment sump level indicating channel;

b. One containment atmosphere gaseous activity monitoring channel;

c. One containment air coolercondensate level switch channel;

d. One containment atmosphere humidity monitoring channel.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two r~quired leak A.1 Perform SR 3.4.13.1 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months detection instrument (PCS water inventory channels inoperable, balance).

AND A.2 Restore inoperable 30 days channel(s) to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Palisades Nuclear Plant 3.4.15-1 Amendment No. 1-89, 219

PCS Leakage Detection Instrumentation 3.4.15 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. All required channels C.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment sump level indicator.

SR 3.4.15.2 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere gaseous activity monitor.

SR 3.4.15.3 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere humidity monitor.

SR 3.4.15.4 Perform CHANNEL FUNCTIONAL TEST of the 18 months required containment air cooler condensate level switch.

SR 3.4,15.5 Perform CHANNEL CALIBRATION of the required 18 months containment sump level indicator.

Palisades Nuclear Plant 3.4.15-2 Amendment No. 189

PCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.6 Perform CHANNEL CALIBRATION of the required 18 months containment atmosphere gaseous activity monitor.

SR 3.4.15.7 Perform CHANNEL CALIBRATION of the required 18 months containment atmosphere humidity monitor.

Palisades Nuclear Plant 3.4.15-3 Amendment No. 189

PCS Specific Activity 3.4.16 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.16 PCS Specific Activity LCO 3.4.16 The specific activity of the primary coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with PCS average temperature (Tave) - 5000 F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 ----------- NOTE ----------

> 1.0 pCi/gm. LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131

< 40 ,uCi/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

Palisades Nuclear Plant 3.4.16-1 Amendment No. 41-8, 219

PCS Specific Activity 3.4.16 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tave < 500 0 F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131

__40 /Ci/gm.

OR Gross specific activity of the primary coolant not within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify primary coolant gross specific activity 7 days

< 10O/ ,uCi/gm.

Palisades Nuclear Plant 3.4.16-2 Amendment No. 189

PCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.2 NOTE --------------

Only required to be performed in MODE 1.

14 days Verify primary coolant DOSE EQUIVALENT 1-131 specific activity < 1.0 /uCi/gm. AND Once between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after THERMAL POWER change of

> 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period SR 3.4.16.3 -NOTE Not required to be performed until 31 days after a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for _>48 hours.

Determine E from a sample taken in MODE 1 after 184 days a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Palisades Nuclear Plant 3.4.16-3 Amendment No. 189

SG Tube Integrity 3.4.17 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG Tube Integrity shall be maintained.

AND All SG tubes satisfying the tube repair criteria shall be plugged in accordance with the Steam Generator Program.

APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS

NOTE ----------------------------------------------------------

Separate Condition entry is allowed for each SG tul CONDITION REQUIRED ACTION COMPLETION TIME A.1 Verify tube integrity of the 7 days A. One or more SG tubes affected tube(s) is satisfying the tube repair maintained until the next criteria and not plugged in refueling outage or SG accordance with the Steam tube inspection.

Generator Program.

AND A.2 Plug the affected tube(s) in Prior to entering accordance with the Steam MODE 4 following the Generator Program. next refueling outage or SG tube inspection B. Required Action and B.1 Be in MODE 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met. AND OR B.2 Be in Mode 5 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SG tube integrity not maintained.

Palisades Nuclear Plant 3.4.17-1 Amendment No. 488, 223

SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the In accordance with Steam Generator Program. the Steam Generator Program.

SR 3.4.17.2 Verify that each. inspected SG tube that satisfies Prior to entering the tube repair criteria is plugged in accordance MODE 4 following a with the Steam Generator Program. SG tube inspection.

Palisades Nuclear Plant 3.4.17-2 Amendment No. 9,223

SITs 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Safety Injection Tanks (SITs)

LCO 3.5.1 Four SITs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SIT inoperable due to A.1 Restore SIT to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months boron concentration not OPERABLE status.

within limits.

OR One SIT inoperable due to the inability to verify level or pressure.

B. One SIT inoperable for B.1 Restore SIT to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B not met.

D. Two or more SITs D.1 Enter LCO 3.0.3. Immediately inoperable.

Palisades Nuclear Plant 3.5.1-1 Amendment No. 4-8, 191

SITs 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each SIT isolation valve is fully open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.1.2 Verify borated water volume in each SIT is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Ž1040 ft3 and*< 1176 ft3 .

SR 3.5.1.3 Verify nitrogen cover pressure in each SIT is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

_ 200 psig.

SR 3.5.1.4 Verify boron concentration in each SIT is 31 days

Ž1720 ppm and_< 2500 ppm.

SR 3.5.1.5 Verify power is removed from each SIT isolation 31 days valve operator.

Palisades Nuclear Plant 3.5.1-2 Amendment No. 189

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with Primary Coolant System (PCS) temperature _> 325°F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One LPSI subsystem A.1 Restore LPSI 7 days inoperable, subsystem to OPERABLE status.

B. One or more ECCS trains B.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable for reasons OPERABLE status.

other than Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C.2 Reduce PCS 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature to < 325 0 F.

D. Less than 100% of the D.1 Enter LCO 3.0.3. Immediately required ECCS flow available.

Palisades Nuclear Plant 3.5.2-1 Amendment No. 4-89, 4-94-, 198

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves and hand switches are 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in the open position.

Valve/Hand Switch Number Function CV-3027 SIRWT Recirc Valve HS-3027A Hand Switch For CV-3027 HS-3027B Hand Switch For CV-3027 CV-3056 SIRWT Recirc Valve HS-3056A Hand Switch For CV-3056 HS-3056B Hand Switch For CV-3056 SR 3.5.2.2 Verify each ECCS manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.3 Verify CV-3006, "SDC Flow Control Valve," is 31 days open and its air supply is isolated.

SR 3.5.2.4 Verify each ECCS pump's developed head at the In accordance with test flow point is greater than or equal to the the Inservice Testing required developed head. Program SR 3.5.2.5 Verify each ECCS automatic valve that is not 18 months locked, sealed, or otherwise secured in position, in the flow path actuates to the correct position on an actual or simulated actuation signal.

Palisades Nuclear Plant 3.5.2-2 Amendment No. 189

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 18 months SR 3.5.2.6 Verify each ECCS pump starts automatically on an actual or simulated actuation signal.

SR 3.5.2.7 Verify each LPSI pump stops on an actual or 18 months simulated actuation signal.

SR 3.5.2.8 Verify, for each ECCS throttle valve listed below, 18 months each position stop is in the correct position.

Valve Number Function MO-3008 LPSI to Cold leg 1A MO-301 0 LPSI to Cold leg 1 B MO-3012 LPSI to Cold leg 2A MO-3014 LPSI to Cold leg 2B MO-3082 HPSI to Hot leg 1 MO-3083 HPSI to Hot leg 1 SR 3.5.2.9 Verify, by visual inspection, each ECCS train 18 months containment sump suction inlet is not restricted by debris and the suction inlet screens show no evidence of structural distress or abnormal corrosion.

Palisades Nuclear Plant 3.5.2-3 Amendment No. 189

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One Low Pressure Safety Injection (LPSI) train shall be OPERABLE.

NOTE ----------------------------------------------

A LPSI train may be considered OPERABLE during alignment and operation for shutdown cooling if capable of being manually realigned to the ECCS mode of operation.

APPLICABILITY: MODE 3 with Primary Coolant System (PCS) temperature < 3251F, MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required LPSI train A.1 Initiate action to restore Immediately inoperable, one LPSI train to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs of Specification 3.5.2, "ECCS - In accordance with Operating," are applicable: applicable SRs SR 3.5.2.2 SR 3.5.2.9 SR 3.5.2.4 Palisades Nuclear Plant 3.5.3-1 Amendment No. 189

SIRWT 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Safety Injection Refueling Water Tank (SIRWT)

LCO 3.5.4 The SIRWT shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SIRWT boron A.1 Restore SIRWT to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not within OPERABLE status.

limits.

OR SIRWT borated water temperature not within limits.

B. SIRWT inoperable for B.1 Restore SIRWT to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Palisades Nuclear Plant 3.5.4-1 Amendment No. 189

SIRWT 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify SIRWT borated water temperature is > 40°F 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and < 1O0°F.

SR 3.5.4.2 ---------------------- NOTE --------------

Only required to be met in MODES 1, 2, and 3.

Verify SIRWT borated water volume is 7 days

> 250,000 gallons.

SR 3.5.4.3 ---------------------- NOTE --------------

Only required to be met in MODE 4.

Verify SIRWT borated water volume is 7 days

_ 200,000 gallons.

SR 3.5.4.4 Verify SIRWT boron concentration is >_1720 ppm 31 days and < 2500 ppm.

Palisades Nuclear Plant 3.5.4-2 Amendment No. 189

TSP 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Trisodium Phosphate (TSP)

LCO 3.5.5 The TSP baskets shall contain > 8,300 lbs and < 11,000 Ibsof active TSP.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. TSP not within limits. A.1 Restore TSP to within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1 Verify the TSP baskets contain _ 8,300 lbs and 18 months

<11,000 lbs of TSP.

SR 3.5.5.2 Verify that a sample from the TSP baskets provides 18 months adequate pH adjustment of borated water.

Palisades Nuclear Plant 3.5.5-1 Amendment No. 189

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance with rate testing, except for containment air lock testing, the Containment in accordance with the Containment Leak Rate Leak Rate Testing Testing Program. Program SR 3.6.1.2- Verify containment structural integrity in In accordance with accordance with the Containment Structural the Containment Integrity Surveillance Program. Structural Integrity Surveillance Program Palisades Nuclear Plant 3.6.1-1 Amendment No. 4-8W, 194

Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 Two containment air locks shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES ------------------------------

1. Entry and exit is permissible through a "locked" air lock door to perform repairs on the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment ----------- NOTES-"

air locks with one 1. Required Actions A.1, A.2, containment air lock door and A.3 are not applicable if inoperable, both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls if both air locks are inoperable.

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND (continued)

Palisades Nuclear Plant 3.6.2-1 Amendment No. 189

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed in the affected air lock.

AND NOTE.---------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

A.3 Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.

B. One or more containment ----------- NOTES--------

air locks with containment 1. Required Actions B.1, B.2, air lock interlock and B.3 are not applicable if mechanism inoperable, both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND (continued)

Palisades Nuclear Plant 3.6.2-2 Amendment No. 189

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Lock an OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed in the affected air lock.

AND NOTE.---------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

B.3 Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock.

C. One or more containment C.1 Initiate action to Immediately air locks inoperable for evaluate overall reasons other than containment leakage Condition A or B. rate per LCO 3.6.1.

AND C.2 Verify a door is closed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Palisades Nuclear Plant 3.6.2-3 Amendment No. 189

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

I.

SR 3.6.2.1 ------------------ NOTES--------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria- applicable to SR 3.6.1.1.

In accordance with Perform required air lock leakage rate testing in the Containment Leak accordance with the Containment Leak Rate Rate Testing Program Testing Program.

SR 3.6.2.2 Verify only one door in the air lock can be opened 24 months at a time.

Palisades Nuclear Plant 3.6.2-4 Amendment No. 4-89, 194

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES -----------------------------

1. Penetration flow paths, except for 8 inch purge exhaust valves and 12 inch air room supply valves penetration flow paths, may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for system(s) made inoperable by containment isolation valves.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE --------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path by penetration flow paths with use of at least one two containment isolation closed and de-activated valves. automatic valve, closed manual valve, blind flange, or check valve One or more penetration with flow through the flow paths with one valve secured.

containment isolation valve

.inoperable (except for AND purge exhaust valve or air room supply valve not locked closed).

(continued)

ACTIONS Palisades Nuclear Plant 3.6.3-1 Amendment No. 189

Containment Isolation Valves 3.6.3 CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) NOTE ----------------

Isolation devices in high radiation areas may be verified by use of administrative means.

A.2 Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B. --------- NOTE --------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths with use of at least one two containment isolation closed and de-activated valves. automatic valve, closed manual valve, or blind flange.

One or more penetration flow paths with two containment isolation valves inoperable (except for purge exhaust valve or air room supply valve not locked closed).

Palisades Nuclear Plant 3.6.3-2 Amendment No. 189

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. --------- NOTE penetration flow path by Only applicable to use of at least one penetration flow paths with closed and de-activated only one containment automatic valve, closed isolation valve and a manual valve, or blind closed system. flange.

AND One or more penetration flow paths with one ------------- NOTE -----------------

containment isolation valve Isolation devices in high radiation inoperable, areas may be verified by use of administrative means.

C.2 Verify the affected Once per 31 days penetration flow path is isolated.

D. One or more purge D.1 Lock closed the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exhaust or air room supply valves.

valves not locked closed.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Palisades Nuclear Plant 3.6.3-3 Amendment No. 189

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 8 inch purge valve and 12 inch air 31 days room supply valve is locked closed.

SR 3.6.3.2 --------------------- NOTE --------------

Valves and blind flanges in high radiation areas may be verified, by use of administrative means.

Verify each manual containment isolation valve 31 days and blind flange that is located outside containment and not locked, sealed, or otherwise secured in position, and is required to be closed during accident conditions, is closed, except for containment isolation valves that are open under administrative controls.

SR 3.6.3.3 -------------------- NOTE ---------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each manual containment isolation valve Prior to entering and blind flange that is located inside containment MODE 4 from and not locked, sealed, or otherwise secured in MODE 5 if not position, and required to be closed during accident performed within the conditions, is closed, except for containment previous 92 days isolation valves that are open under administrative controls.

Palisades Nuclear Plant 3.6.3-4 Amendment No. 189

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.4 Verify the isolation time of each automatic power In accordance with, operated containment isolation valve is within the Inservice Testing limits. Program SR 3.6.3.5 Verify each containment 8 inch purge exhaust and 184 days 12 inch air room supply valve is closed by performance of a leakage rate test.

SR 3.6.3.6 Verify each automatic containment isolation valve 18 months that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

Palisades Nuclear Plant 3.6.3-5 Amendment No. 189

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be<* 1.0 psig in MODES 1 and 2 and

_<1.5 psig in MODES 3 and 4.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure not A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within limit. pressure to within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limit. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.6.4-1 Amendment No. 189

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be < 140 0 F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air A.1 Restore containment 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air temperature limit. to within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limit.

Palisades Nuclear Plant 3.6.5-1 Amendment No. 189

Containment Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Cooling Systems LCO 3.6.6 Two containment cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months cooling trains inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months C. Less than 100% of the C.1 Enter LCO 3.0.3. Immediately required post accident containment cooling capability available.

Palisades Nuclear Plant 3.6.6-1 Amendment No. 88, 199

Containment Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.6.2 Operate each Containment Air Cooler Fan Unit for 31 days

_ 15 minutes.

SR 3.6.6.3 Verify the containment spray piping is full of water 31 days to the 735 ft elevation in the containment spray header.

SR 3.6.6.4 Verify total service water flow rate, when aligned 18 months for accident conditions, is > 4800 gpm to Containment Air Coolers VHX-1, VHX-2, and VHX-3.

SR 3.6.6.5 Verify each containment spray pump's developed In accordance with head at the flow test point is greater than or equal the Inservice Testing to the required developed head. Program SR 3.6.6.6 Verify each automatic containment spray valve in 18 months the flow path that is not locked, sealed, or otherwise secured in position, actuates to its correct position on an actual or simulated actuation signal.

Palisades Nuclear Plant 3.6.6-2 Amendment No. 189

Containment Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.7 Verify each containment spray pump starts 18 months automatically on an actual or sirhulated actuation signal.

SR 3.6.6.8 Verify each containment cooling fan starts 18 months automatically on an actual or simulated actuation signal.

SR 3.6.6.9 Verify each spray nozzle is unobstructed. Following maintenance which could result in nozzle blockage Palisades Nuclear Plant 3.6.6-3 Amendment No. 1-89, 211

LCO 3.6.7 AND BASES DELETED: REFER TO AMENDMENT 221 DATED 1/11/05

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 Twenty-three MSSVs shall be OPERABLE as specified in Table 3.7.1-1.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months MSSVs inoperable. MSSVs to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each required MSSV lift setting is within the In accordance with limits of Table 3.7.1-1 in accordance with the the Inservice Testing Inservice Testing Program. Following testing, lift Program settings shall be within +/- 1%.

Palisades Nuclear Plant 3.7.1-1 Amendment No. 189

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER LIFT SETTING Steam Generator A Steam Generator B (psig +/- 3%)

RV-0703 RV-0701 RV-0704 RV-0702 1025 RV-0705 RV-0707 RV-0706 RV-0708 RV-0713 RV-0709 RV-0714 RV-0710 1005 RV-0715 RV-0711 RV-0716 RV-0712 RV-0717 RV-0719 RV-0718 RV-0720 985 RV-0723 RV-0721 RV-0724 RV-0722 Palisades Nuclear Plant 3.7.1-2 Amendment No. 189

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Two MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when both MSIVs are closed and de-activated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months MODE 1. OPERABLE status.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A not met.

C. --------- NOTE ------------- C.1 Close MSIV. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Separate Condition entry is allowed for each MSIV. AND One or more MSIVs C.2 Verify MSIV is closed. Once per 7 days inoperable in MODE 2 or 3.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Palisades Nuclear Plant 3.7.2-1 Amendment No. 189

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify closure time of each MSIV is

5 seconds on 18 months an actual or simulated actuation signal from each train under no flow conditions.

Palisades Nuclear Plant 3.7.2-2 Amendment No. 189

MFRVs and MFRV Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves LCO 3.7.3 Two MFRVs and two MFRV bypass valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 except when both MFRVs and both MFRV bypass valves are either closed and de-activated, or isolated by closed manually actuated valves.

ACTIONS

NOTE ------------------------------

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFRVs or A.1 Close or isolate 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months MFRV bypass valves inoperable MFRV(s) or inoperable. MFRV bypass valve(s).

AND A.2 Verify inoperable Once per 7 days MFRV(s) or MFRV bypass valve(s) is closed or isolated.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Palisades Nuclear Plant 3.7.3-1 Amendment No. 189

MFRVs and MFRV Bypass Valves 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each MFRV and MFRV 18 months bypass valve is < 22 seconds on a actual or simulated actuation signal.

Palisades Nuclear Plant 3.7.3-2 Amendment No. 189

ADVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Dump Valves (ADVs)

LCO 3.7.4 One ADV per steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is being relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ADV A.1 Restore ADV to 7 days inoperable. OPERABLE status.

B. Two required ADVs B.1 Restore one ADV to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable. OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4 without 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months reliance upon steam generator for heat removal.

Palisades Nuclear Plant 3.7.4-1 Amendment No. 1-89, 219

ADVs 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ADV. 18 months Palisades Nuclear Plant 3.7.4-2 Amendment No. 189

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Two AFW trains shall be OPERABLE.

- NOTES -- ----------------------

1. Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

2. The steam driven pump is only required to be OPERABLE prior to making the reactor critical.

3. Two AFW pumps may be placed in manual for testing, for a period of up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

NOTE- ------------------------------

LCO 3.0.4.b is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AFW A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trains inoperable in OPERABLE status.

MODE 1, 2, or 3.

Palisades Nuclear Plant 3.7.5-1 Amendment No. 4-89, 1-90, 2-00, 219

AFW System 3.7.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months OR Less than 100% of the required AFW flow available to either steam generator.

OR Less than two AFW pumps OPERABLE in MODE 1,2, OR 3.

C. Less than 100% of the ------------ NOTE ---------

required AFW flow LCO 3.0.3 and all other LCO available, to both steam Required Actions requiring MODE generators. changes or power reductions are suspended until at least 100% of the required AFW flow is available.

C.1 Initiate action to restore Immediately, one AFW train to OPERABLE status.

Palisades Nuclear Plant 3.7.5-2 Amendment No. 4-89, 1-90, 200

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each required AFW manual, power 31 days operated, and automatic valve in each water flow path and in the steam supply flow path to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 ------------------ NOTE -----------------

Not required to be met for the turbine driven AFW pump in MODE 3 below 800 psig in the steam

,generators.

Verify the developed head of each required AFW In accordance with pump at the flow test point is greater than or equal the Inservice Testing to the required developed head. Program SR 3.7.5.3 -------------------- NOTE ---------------

Only required to be met in MODES 1, 2 or 3 when AFW is not in operation.

Verify each AFW automatic valve that is not 18 months locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.4 --------------------- NOTE---------------

Only required to be met in MODES 1, 2, and 3.

Verify each required AFW pump starts 18 months automatically on an actual or simulated actuation signal.

Palisades Nuclear Plant 3.7.5-3 Amendment No. 4-89, 190

Condensate Storage and Supply 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage and Supply LCO 3.7.6 The combined useable volume of the Condensate Storage Tank (CST) and Primary Makeup Storage Tank (T-81) shall be >_100,000 gallons.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Condensate volume not A.1 Verify OPERABILITY of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months within limit, backup water supplies.

AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Restore condensate 7 days volume to within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4 without 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months reliance on steam generator for heat removal.

Palisades Nuclear Plant 3.7.6-1 Amendment No. 189

Condensate Storage and Supply 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify condensate useable volume is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 100,000 gallons.

Palisades Nuclear Plant 3.7.6-2 Amendment No. 189

CCW System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CCW trains A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Less than 100% of the C.1 Enter LCO 3.0.3. Immediately required post accident CCW cooling capability available.

Palisades Nuclear Plant 3.7.7-1 Amendment No. 1-89, 199

CCW System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

+

SR 3.7.7.1 -------------------

NOTE ----------------------------

Isolation of CCW flow to individual components does not render the CCW System inoperable.

Verify each CCW manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.2 --------------------- NOTE---------------

Only required to be met in MODES 1, 2, and 3.

Verify each CCW automatic valve in the flow path 18 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.7.3 --------------------- NOTE---------------

Only required to be met in MODES 1, 2, and 3.

Verify each CCW pump starts automatically on an 18 months actual or simulated actuation signal in the "with standby power available" mode.

Palisades Nuclear Plant 3.7.7-2 Amendment No. 189

SWS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water System (SWS)

LCO 3.7.8 Two SWS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SWS trains A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Less than 100% of the C.1 Enter LCO 3.0.3. Immediately required post accident SWS cooling capability available.

Palisades Nuclear Plant 3.7.8-1 Amendment No. 1-89, 199

SWS 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 ------------------- NOTE---------------

Isolation of SWS flow to individual components does not render SWS inoperable.

Verify each SWS manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the.correct position.

SR 3.7.8.2 -------------------- NOTE----------------

Only required to be met in MODES 1, 2, and 3.

Verify each SWS automatic valve in the flow path 18 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.8.3 --------------------- NOTE ---------------

Only required to be met in MODES 1, 2, and 3.

Verify each SWS pump starts automatically on an 18 months actual or simulated actuation signal in the "with standby power available" mode.

Palisades Nuclear Plant 3.7.8-2 Amendment No. 189

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS inoperable. A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is > 568.25 ft above 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mean sea level.

SR 3.7.9.2 Verify water temperature of UHS is < 85 0 F. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Palisades Nuclear Plant 3.7.9-1 Amendment No. 8, 202

CRV Filtration 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Ventilation (CRV) Filtration LCO 3.7.10 Two CRV Filtration trains shall be OPERABLE.

-NOTE The control room boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, During CORE ALTERATIONS, During movement of irradiated fuel assemblies, During movement of a fuel cask in or over the Spent Fuel Pool (SFP).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRV Filtration train A.1 Restore CRV Filtration 7 days inoperable, train to OPERABLE status.

B. Two CRV Filtration B.1 Initiate preplanned Immediately trains inoperable due compensatory measures.

to inoperable control room boundary in AND MODE 1,2, 3, or 4.

B.2 Restore control room 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months boundary to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Palisades Nuclear Plant 3.7.10-1 Amendment No. 4-8, 197

CRV Filtration 3.7.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 -Place OPERABLE CRV Immediately associated Completion Filtration train in Time of Condition A not emergency mode.

met during CORE ALTERATIONS, during OR movement of irradiated fuel assemblies, or D.2.1 Suspend CORE Immediately during movement of a ALTERATIONS.

fuel cask in or over the SFP. AND D.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND D.2.3 Suspend movement of a Immediately fuel cask in or over the SFP.

E. Two CRV Filtration E.1 Suspend CORE Immediately trains inoperable during ALTERATIONS.

CORE ALTERATIONS, during movement of AND irradiated fuel assemblies, or during E.2 Suspend movement of Immediately movement of a fuel cask irradiated fuel assemblies.

in or over the SFP.

AND E.3 Suspend movement of a Immediately fuel cask in or over the SFP.

Palisades Nuclear Plant 3.7.10-2 Amendment No. 1-89, 197

CRV Filtration 3.7.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Two CRV.Filtration F.1 Enter LCO 3.0.3. Immediately trains inoperable in MODE 1,2, 3, or 4 for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRV Filtration train for 31 days

> 10 continuous hours with associated heater (VHX-26A or VHX-26B) operating.

SR 3.7.10.2 Perform required CRV Filtration filter testing in In accordance with accordance with Ventilation Filter Testing the Ventilation Filter Program. Testing Program SR 3.7.10.3 -------------------- NOTE---------------

Only required to be met in MODES 1, 2, 3, and 4, and during movement of irradiated fuel assemblies in containment.

Verify each CRV Filtration train actuates on an 18 months actual or simulated actuation signal.

SR 3.7.10.4 Verify one CRV Filtration train can maintain a 18 months positive pressure of ->0.125 inches water gauge, relative to the adjacent area during the emergency mode of operation, at an emergency ventilation flow rate of > 3040 cfm and < 3520 cfm.

Palisades Nuclear Plant 3.7.10-3 Amendment No. 44-9, 197

CRV Cooling 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Ventilation (CRV) Cooling LCO 3.7.11 Two CRV Cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, During CORE ALTERATIONS, During movement of irradiated fuel assemblies, During movement of a fuel cask in or over the Spent Fuel Pool (SFP).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRV Cooling train A.1 Restore CRV Cooling 30 days inoperable, train to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Palisades Nuclear Plant 3.7.11-1 Amendment No. 189

CRV Cooling 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Place OPERABLE CRV Immediately associated Completion Cooling train in Time of Condition A not operation.

met during CORE ALTERATIONS, during OR movement of irradiated fuel assemblies, or C.2.1 Suspend CORE Immediately movement of a fuel cask in ALTERATIONS.

or over the SFP.

AND C.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND C.2.3 Suspend movement of a Immediately fuel cask in or over the SFP.

D. Two CRV Cooling trains D.1. Suspend CORE Immediately inoperable during CORE ALTERATIONS.

ALTERATIONS, during movement of irradiated AND fuel assemblies, or movement of a fuel cask in D.2 Suspend movement of Immediately or over the SFP. irradiated fuel assemblies.

AND D.3 Suspend movement of a Immediately fuel cask in or over the SFP.

Palisades Nuclear Plant 3.7.1 1-2 Amendment No. 189

CRV Cooling 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two CRV Cooling trains E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CRV Cooling train has the capability to 18 months remove the assumed heat load.

Palisades Nuclear Plant 3.7.1 1-3 Amendment No. 189

Fuel Handling Area Ventilation System 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Fuel Handling Area Ventilation System LCO 3.7.12 The Fuel Handling Area Ventilation System shall be OPERABLE with one fuel handling area exhaust fan aligned to the emergency filter bank and in operation.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel handling building when irradiated fuel assemblies with < 30 days decay time are in the fuel handling building, During movement of a fuel cask in or over the SFP when irradiated fuel assemblies with < 90 days decay time are in the fuel handling building, During CORE ALTERATIONS when irradiated fuel assemblies with

< 30 days decay time are in the containment with the equipment hatch open, During movement of irradiated fuel assemblies in the containment when irradiated fuel assemblies with < 30 days decay time are in the

.containment with the equipment hatch open.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel Handling Area A.1 Suspend movement of Immediately Ventilation System not fuel assemblies.

aligned or in operation.

AND OR Fuel Handling Area A.2 Suspend CORE ALTERATIONS. Immediately System Ventilation inoperable. AND A.3 Suspend movement of a Immediately fuel cask in or over the SFP.

Palisades Nuclear Plant 3.7.12-1 Amendment No. 189

Fuel Handling Area Ventilation System 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Perform required Fuel Handling Area Ventilation In accordance with System filter testing in accordance with the the Ventilation Filter Ventilation Filter Testing Program. Testing Program SR 3.7.12.2 Verify the flow rate of the Fuel Handling Area 18 months Ventilation System, when aligned to the emergency filter bank, is _>5840 cfm and

< 8760 cfm.

Palisades Nuclear Plant 3.7.12-2 Amendment No. 189

ESRV Dampers 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Engineered Safeguards Room Ventilation (ESRV) Dampers LCO 3.7.13 Two ESRV Damper trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more ESRV A.1 Initiate action to isolate Immediately Damper trains inoperable, associated ESRV Damper train(s).

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify each ESRV Damper train closes on an 31 days actual or simulated actuation signal.

Palisades Nuclear Plant 3.7.13-1 Amendment No. 189

SFP Water Level 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool (SFP) Water Level LCO 3.7.14 The SFP water level shall be 2! 647 ft elevation.

NOTE ------------------------------------------

SFP level may be below the 647 ft elevation to support fuel cask movement, if the displacement of water by the fuel cask when submerged in the SFP, would raise SFP level to > 647 ft elevation.

APPLICABILITY: During movement of irradiated fuel assemblies in the SFP, During movement of a fuel cask in or over the SFP.

ACTIONS

NOTE -------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. SFP water level not within A.1 Suspend movement of Immediately limit, irradiated fuel assemblies in SFP.

AND A.2 Suspend movement of Immediately fuel cask in or over the SFP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the SFP water level is Ž647 ft elevation. 7 days Palisades Nuclear Plant 3.7.14-1 Amendment No. 189

SFP Boron Concentration 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool (SFP) Boron Concentration LCO 3.7.15 The SFP boron concentration shall be Ž_ 1720 ppm.

APPLICABILITY: When fuel assemblies are stored in the Spent Fuel Pool.

ACTIONS NOTE ------------------------

NOT--------------------- ......------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. SFP boron concentration A.1 Suspend movement of Immediately not within limit. fuel assemblies in the SFP.

AND A.2 Initiate action to restore Immediately SFP boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the SFP boron concentration is within limit. 7 days Palisades Nuclear Plant 3.7.15-1 Amendment No. 4-89, 207

Spent Fuel Assembly Storage 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Spent Fuel Assembly Storage LCO 3.7.16 The combination of initial enrichment, burnup, and decay time of each fuel assembly stored in Region II shall be within the requirements of Table 3.7.16-1.

APPLICABILITY: Whenever any fuel assembly is stored in Region II of either the spent fuel pool or the north tilt pit.

ACTIONS

NOTE ------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Initiate action to move Immediately not met. the noncomplying fuel assembly from Region II.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify by administrative means the combination of Prior to storing the initial enrichment, burnup, and decay time of the fuel assembly in fuel assembly is in accordance with Region II Table 3.7.16-1.

Palisades Nuclear Plant 3.7.16-1 Amendment No. 1-8 4, 207

Spent Fuel Assembly Storage 3.7.16 TABLE 3.7.16-1 (page 1 of 1)

Spent Fuel Minimum Burnup and Decay Requirements for Storage in Region II of the Spent Fuel Pool and North Tilt Pit Initial Burnup Burnup Burnup Burnup Burnup Enrichment (GWD/MTU) (GWD/MTU) (GWD/MTU) (GWD/MTU) (GWD/MTU)

(Wt%) No Decay 1 Year Decay 3 Year Decay 5 Year Decay 8 Year Decay

1.14 0 0 0 0 0

> 1.14 3.477 3.477 3.477 3.477 3.477 1.20 3.477 3.477 3.477 3.477 3.477 1.40 7.951 7.844 7.464 7.178 6.857 1.60 11.615 11.354 10.768 10.319 9.847 1.80 14.936 14.535 13.767 13.187 12.570 2.00 18.021 17.502 16.561 15.875 15.117 2.20 21.002 20.417 19.313 18.499 17.611 2.40 23.900 23.201 21.953 21.034 20.050 2.60 26.680 25.905 24.497 23.487 22.378 2.80 29.388 28.528 27.006 25.879 24.678 3.00 32.044 31.114 29.457 28.243 26.942 3.20 34.468 33.457 31.698 30.397 29.008 3.40 36.848 35.783 33.920 32.544 31.079 3.60 39.152 38.026 36.059 34.615 33.077 3.80 41.419 40.226 38.163 36.650 35.049 4.00 43.661 42.422 40.257 38.673 37.007 4.20 45.987 44.684 42.415 40.778 39.028 4.40 48.322 46.950 44.588 42.877 41.041 4.60 50.580 49.158 46.690 44.911 43.003 (a) Linear interpolation between two consecutive points will yield acceptable results.

(b) Comparison of nominal assembly average burnup numbers to these in the table is acceptable if measurement uncertainty is _<10%.

Palisades Nuclear Plant 3.7.16-2 Amendment No. 4-89, 207

Secondary Specific Activity 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Secondary Specific Activity LCO 3.7.17 The specific activity of the secondary coolant shall be <50.10 pCi/gm DOSE EQUIVALENT 1-131.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not within A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify the specific activity of the secondary coolant is 31 days within limit.

Palisades Nuclear Plant 3.7.17-1 Amendment No. 189

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1 E AC Electrical Power Distribution System; and

b. Two Diesel Generators (DGs) each capable of supplying one train of the onsite Class 1 E AC Electrical Power Distribution System.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTE -----------------------------

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. (offsite source check) for OPERABLE offsite AND circuit.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND thereafter A.2 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 10 days from discovery of failure to meet LCO Palisades Nuclear Plant 3.8.1-1 Amendment No. 484, 219

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One DG inoperable. B.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (offsite source check) for the OPERABLE AND offsite circuit(s).

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s) supported by discovery of the inoperable DG Condition B inoperable when its concurrent with redundant required inoperability of feature(s) is inoperable. redundant required feature(s)

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (start test) for OPERABLE DG.

AND B.4 Restore DG to 7 days OPERABLE status.

AND 10 days from discovery of failure to meet LCO Palisades Nuclear Plant 3.8.1-2 Amendment No. 189

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Two offsite circuits C.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable, feature(s) inoperable discovery of when its redundant Condition C required feature(s) is concurrent with inoperable. inoperability of redundant required feature(s)

AND C.2 Restore one offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status.

D. One offsite circuit NOTE ------------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND "Distribution Systems -

Operating," when Condition D is One DG inoperable, entered with no AC power source to any train.

D.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR D.2 Restore DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

E. Two DGs inoperable. E.1 Restore one DG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OPERABLE status.

Palisades Nuclear Plant 3.8.1-3 Amendment No. 189

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A, B, C, AND D, or E not met.

F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Three or more AC sources G.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and voltage for 7 days.

each offsite circuit.

SR 3.8.1.2 Verify each DG starts from standby conditions and 31 days achieves:

a. In < 10 seconds, ready-to-load status; and

b. Steady state voltage > 2280 V and < 2520 V, and frequency > 59.5 Hz and < 61.2 Hz.

Palisades Nuclear Plant 3.8.1 -4 Amendment No. 189

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.3 --------------------- NOTES --------------

1. Momentary transients outside the load range do not invalidate this test.

2. This Surveillance shall be conducted on only one DG at a time.

3. This Surveillance shall be preceded by and immediately follow without-shutdown a successful performance of SR 3.8.1.2.

Verify each DG is synchronized and loaded, and 31 days operates for > 60 minutes:

a. For > 15 minutes loaded to greater than or equal to peak accident load; and

b. For the remainder of the test at a load

- 2300 kW and < 2500 kW.

SR 3.8.1.4 Verify each day tank contains > 2500 gallons of 31 days fuel oil.

SR 3.8.1.5 Verify each DG rejects a load greater than or equal 18 months to its associated single largest post-accident load, and:

a. Following load rejection, the frequency is

< 68 Hz;

b. Within 3 seconds following load rejection; the voltage is > 2280 V and < 2640 V; and

c. Within 3 seconds following load rejection, the frequency is > 59.5 Hz and < 61.5 Hz.

Palisades Nuclear Plant 3.8.1-5 Amendment No. 189

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify each DG, operating at a power factor < 0.9, 18 months does not trip, and voltage is maintained < 4000 V during and following a load rejection of > 2300 kW and < 2500 kW.

SR 3.8.1.7 ------------------- NOTE---------------

This'Surveillance shall not be performed in MODE 1,2, 3, or 4.

Verify on an actual or simulated loss of offsite 18 months power signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses;

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in < 10 seconds,

2. energizes auto-connected shutdown loads through automatic load sequencer,

3. maintains steady state voltage

> 2280 V and < 2520 V,

4. maintains steady state frequency

> 59.5 Hz and < 61.2 Hz, and

5. supplies permanently connected loads for > 5 minutes.

Palisades Nuclear Plant 3.8.1-6 Amendment No. 189

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.8 ---------------

NOTE--------------

Momentary transients outside the load and power factor ranges do not invalidate this test.

18 months Verify each DG, operating at a power factor < 0.9, operates for > 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For > 100 minutes loaded > its' peak accident loading; and

b. For the remaining hours of the test loaded

> 2300 kW and < 2500 kW.

SR 3.8.1.9 ---------------

NOTE--------------

This Surveillance shall not be performed in MODE 1,2, 3, or 4.

Verify each DG:

18 months

a. Synchronizes with offsite power source while supplying its associated 2400 V bus upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

Palisades Nuclear Plant 3.8.1-7 Amendment No. 189

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.10 -------------------- NOTE ---------------

This Surveillance shall not be performed in MODE 1,2, 3, or 4.

Verify the time of each sequenced load is within 18 months

_ 0.3 seconds of design timing for each automatic load sequencer.

SR 3.8.1.11 ------------------- NOTE -----------------------------

This Surveillance shall not be performed in MODE 1,2, 3, or 4.

Verify on an actual or simulated loss of offsite 18 months power signal in conjunction with an actual or simulated safety injection signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses;

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in < 10 seconds,

2. energizes auto-connected emergency loads through its automatic load sequencer,

3. achieves steady state voltage

> 2280 V and < 2520 V,

4. achieves steady state frequency

> 59.5 Hz and < 61.2 Hz, and

5. supplies permanently connected loads for > 5 minutes.

Palisades Nuclear Plant 3.8.1-8 Amendment No. 189

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1 E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and

b. One Diesel Generator (DG) capable of supplying one train of the onsite Class 1 E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The required offsite circuit ----------- NOTE ----------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.

A.1 Declare affected Immediately required feature(s) with no offsite power available inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND (continued)

Palisades Nuclear Plant 3.8.2-1 Amendment No. 189

AC Sources - Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.2.2 Suspend movement of Immediately A. (continued) irradiated fuel assemblies.

AND A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions.

AND A.2.4 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. The required DG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies.

AND B.3 Initiate action to Immediately suspend operations involving positive reactivity additions.

AND B.4 Initiate action to restore Immediately required DG to OPERABLE status.

Palisades Nuclear Plant 3.8.2-2 Amendment No. 189

AC Sources - Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 For AC sources required to be OPERABLE, the In accordance with following SRs of Specification 3.8.1, "AC Sources - applicable SRs Operating" are applicable:

SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.4.

Palisades Nuclear Plant 3.8.2-3 Amendment No. 189

Diesel Fuel, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel, Lube Oil, and Starting Air LCO 3.8.3 For each Diesel Generator (DG):

a. The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits, and

b. Both diesel fuel oil transfer systems shall be OPERABLE.

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

NOTE-------------------------------

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel oil inventory A.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

< 23,700 gallons and inventory to within limits.

> 20,110 gallons in storage tank.

B. Stored lube oil inventory B.1 Restore stored lube oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

< 200 gallons and inventory to within limits.

> 160 gallons.

C. Fuel transfer system C.1 Restore fuel transfer 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months (P-18A) inoperable. system to OPERABLE status.

D. Fuel transfer system D.1 Restore fuel transfer 7 days (P-18B) inoperable, system to OPERABLE status.

Palisades Nuclear Plant 3.8.3-1 Amendment No. 189

Diesel Fuel, Lube Oil, and Starting Air 3.8.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Both fuel transfer systems E.1 Restore one fuel 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable, transfer system to OPERABLE status.

F. Fuel oil properties other F.1 Restore stored fuel oil 30 days than viscosity, and water properties to within and sediment, not within limits.

limits.

G. Required Action and G.1 Declare associated Immediately associated Completion DG(s) inoperable.

Time not met.

OR Stored diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, or F.

Palisades Nuclear Plant 3.8.3-2 Amendment No. 189

Diesel Fuel, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify the fuel oil storage tank contains 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> 23,700 gallons of fuel.

SR 3.8.3.2 Verify stored lube oil inventory is > 200 gallons. 31 days SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil are In accordance with tested in accordance with, and maintained within the the Fuel Oil limits of, the Fuel Oil Testing Program. Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure is 31 days

> 200 psig.

SR 3.8.3.5 Check for and remove excess accumulated water from 92 days the fuel oil storage tank.

SR 3.8.3.6 Verify the fuel oil transfer system operates to transfer 92 days fuel oil from the fuel oil storage tank to each DG day tank and engine mounted tank.

Palisades Nuclear Plant 3.8.3-3 Amendment No. 189

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Left Train and Right Train DC.electrical power sources shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required DC electrical A.1 Verify functional 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power source battery cross-connected battery charger inoperable, charger is connected supplying power to the affected DC train.

AND A.2 Restore required DC 7 days.

electrical power source battery charger to OPERABLE status.

B. One required DC electrical B.1 Verify OPERABLE 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power source battery directly connected and inoperable, functional cross-connected battery chargers are connected supplying power to the affected DC train.

AND B.2 Restore required DC 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months electrical power source battery to OPERABLE status.

Palisades Nuclear Plant 3.8.4-1 Amendment No. 189

DC Sources - Operating 3.8.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is > 125 V on float 7 days charge.

SR 3.8.4.2 Verify no visible corrosion at battery terminals and 92 days connectors.

OR Verify battery connection resistance is

< 50 pohm for inter-cell connections, < 360 pohm for inter-rack connections, and < 360,pohm for inter-tier connections.

SR 3.8.4.3 Inspect battery cells, cell plates, and racks for 12 months visual indication of physical damage or abnormal deterioration that could degrade battery performance.

Palisades Nuclear Plant 3.8.4-2 Amendment No. 189

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.4 Remove visible terminal corrosion and verify 12 months battery cell to cell and terminal connections are coated with anti-corrosion material.

SR 3.8.4.5 Verify battery connection resistance is 12 months

-<50 pohm for inter-cell connections, < 360 pohm for inter-rack connections, and < 360 pohm for inter-tier connections.

SR 3.8.4.6 Verify each required battery charger supplies 18 months

> 180 amps at > 125 V for > 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SR 3.8.4.7 --------------------- NOTES--------------

1. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7.

2. This Surveillance shall not be performed in MODE 1,2, 3, or 4.

Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required 18 months emergency loads for the design duty cycle when subjected to a battery service test.

Palisades Nuclear Plant 3.8.4-3 Amendment No. 189

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

.4-SR 3.8.4.8 --------------

NOTE---------------

This Surveillance shall not be performed in MODE 1,2, 3, or 4.

60 months Verify battery capacity is > 80% of the manufacturer's rating when subjected to a AND performance discharge test or a modified performance discharge test. 12 months when battery shows degradation or has reached 85% of the expected life with capacity < 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity

Ž 100% of manufacturer's rating Palisades Nuclear Plant 3.8.4-4 Amendment No. 189

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 DC electrical power source(s) shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown."

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required DC A.1 Declare affected Immediately electrical power sources required feature(s) inoperable, inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions.

AND (continued)

Palisades Nuclear Plant 3.8.5-1 Amendment No. 189

DC Sources - Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate action to restore Immediately required DC electrical power source(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 For DC sources required to be OPERABLE, the In accordance with following SRs are applicable: applicable SRs SR 3.8.4.1 SR 3.8.4.3 SR 3.8.4.5 SR 3.8.4.2 SR 3.8.4.4 SR 3.8.4.6.

Palisades Nuclear Plant 3.8.5-2 Amendment No. 189

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for the Left Train and Right Train batteries shall be within limits.

APPLICABILITY: When associated DC electrical power source(s) are required to be OPERABLE.

ACTIONS ACTIONS--- ---------------------- NOTE ---------------------------------------------

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries with A.1 Verify pilot cells 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one or more battery cell electrolyte level and float parameters not within voltage meet Category A or B limits. Table 3.8.6-1 Category C limits.

AND A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6-1 AND Category C limits.

Once per 7 days thereafter AND A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.

Palisades Nuclear Plant 3.8.6-1 Amendment No. 189

Battery Cell Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

OR One or more batteries with average electrolyte temperature of the representative cells

< 70'F.

OR One or more batteries with one or more battery cell parameters not within Category C limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet Table 3.8.6-1 31 days Category A limits.

SR 3.8.6.2 Verify average electrolyte temperature of 31 days representative cells is > 70 0 F.

SR 3.8.6.3 Verify battery cell parameters meet Table 3.8.6-1 92 days Category B limits.

Palisades Nuclear Plant 3.8.6-2 Amendment No. 189

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Surveillance Requirements CATEGORY A: CATEGORY B: CATEGORY C:

NORMAL LIMITS NORMAL LIMITS ALLOWABLE FOR EACH FOR EACH LIMITS FOR EACH DESIGNATED CONNECTED CONNECTED PARAMETER PILOT CELL CELL CELL Electrolyte Level > Minimum level > Minimum level Above top of plates, indication mark, and indication mark, and and not overflowing

< 1/4 inch above < 1/4 inch above maximum level maximum level indication mark(a) indication mark(a)

Float Voltage >2.13 V >2.13 V > 2.07 V Specific Gravity(b)(c) > 1.205 > 1.200 Not more than 0.020 below AND average connected cells Average of connected cells AND

Ž1.205 Average of all connected cells.

Ž1.195 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing.

(b) Corrected for electrolyte temperature and level. Level correction is not required, however, when battery charging is < 2 amps when on float charge.

(c) A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits.

Palisades Nuclear Plant 3.8.6-3 Amendment No. 189

Inverters - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 Four inverters shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One inverter inoperable. ------------- NOTE ---------

Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems -

Operating" with any Preferred AC bus de-energized.

A.1 Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and 7 days alignment to Preferred AC buses.

Palisades Nuclear Plant 3.8.7-11 Amendment No. 189

Inverters - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 Inverter(s) shall be OPERABLE to support the onsite Class 1 E Preferred AC bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-- Shutdown."

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected Immediately inverters inoperable. required feature(s) inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions.

AND A.2.4 Initiate action to restore Immediately required inverters to OPERABLE status.

Palisades Nuclear Plant 3.8.8-1 Amendment No. 189

Inverters - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and 7 days alignment to required Preferred AC buses.

Palisades. Nuclear Plant 3.8.8-2 Amendment No. 189

Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Left Train and Right Train AC, DC, and Preferred AC bus electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC electrical A.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution power distribution subsystems in one train subsystem(s) to AND inoperable. OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO B. One Preferred AC bus B.1 Restore Preferred AC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable, bus to OPERABLE status. AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO C. One or more DC electrical C.1 Restore DC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution power distribution.

subsystems in one train subsystem(s) to AND inoperable. OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO Palisades Nuclear Plant 3.8.9-1 Amendment No. 189

Distribution Systems - Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two or more inoperable E.1 Enter LCO 3.0.3. Immediately distribution subsystems that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to 7 days required AC, DC, and Preferred AC bus electrical power distribution subsystems.

Palisades Nuclear Plant 3.8.9-2 Amendment No. 189

Distribution Systems - Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portion of AC, DC, and Preferred AC bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC, A.1 Declare associated Immediately DC, or Preferred AC bus supported required electrical power distribution feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions.

AND (continued)

Palisades Nuclear Plant 3.8.10-1 Amendment No. 189

Distribution Systems - Shutdown 3.8.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate actions to restore Immediately required AC, DC, and Preferred AC bus electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling train inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to 7 days required AC, DC, and Preferred AC bus electrical power distribution subsystems.

Palisades Nuclear Plant 3.8.10-2 Amendment No. 189

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Primary Coolant System and the refueling cavity shall be maintained at the REFUELING BORON CONCENTRATION.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend CORE Immediately within limit. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is at the REFUELING 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months BORON CONCENTRATION.

Palisades Nuclear Plant 3.9.1-1 Amendment No. 189

Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range channels shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One source range channel A.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

B. Two source range B.1 Initiate action to restore Immediately channels inoperable, one source range channel to OPERABLE status.

AND B.2 Perform SR 3.9.1.1 Once per (PCS boron 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months concentration verification).

Palisades Nuclear Plant 3.9.2-1 Amendment No. 189

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.2.2 --------------------- NOTE----------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Palisades Nuclear Plant 3.9.2-2 Amendment No. 189

Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be in the following status:

a. The equipment hatch closed and held in place by four bolts;

- NOTE ------------------------------------------

The equipment hatch is only required to be closed when the Fuel Handling Area Ventilation System is not in compliance with LCO 3.7.12, "Fuel Handling Area Ventilation System."

b. One door in the personnel air lock closed;

-N O T E--- -----------------------------------------

One door in the personnel air lock is only required to be closed when the equipment hatch is closed.

c. One door in the emergency air lock closed; and

d. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2. capable of being closed by an OPERABLE Refueling Containment High Radiation Initiation signal.

APPLICABILITY: During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.

Palisades Nuclear Plant 3.9.3-1 Amendment No. 189

Containment Penetrations 3.9.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend CORE Immediately penetrations not in ALTERATIONS.

required status.

AND A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required to be met containment 7 days penetration is in the required status.

SR 3.9.3.2 --------------------- NOTE---------------

Only required to be met for unisolated containment penetrations.

Verify each required automatic isolation valve 18 months closes on an actual or simulated Refueling Containment High Radiation signal.

Palisades Nuclear Plant 3.9.3-2 Amendment No. 189

SDC and Coolant Circulation - High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation - High Water Level LCO 3.9.4 One SDC train shall be OPERABLE and in operation.

-- ---------------------------NOTES ----------------------

1. The required SDC train may not be in operation for_< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause reduction of the Primary Coolant System boron concentration.

2. The required SDC train may be made inoperable for < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period for testing or maintenance, provided one SDC train is in operation providing flow through the reactor core, and core outlet temperature is __2000 F.

APPLICABILITY: MODE 6 with the refueling cavity water level Ž_647 ft elevation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required SDC train A.1 Initiate action to restore Immediately inoperable or not in SDC train to operation. OPERABLE status and operation.

AND A.2 Suspend operations Immediately involving a reduction in primary coolant boron concentration.

AND (continued)

Palisades Nuclear Plant 3.9.4-1 Amendment No. 189

SDC and Coolant Circulation - High Water Level 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Suspend loading Immediately irradiated fuel assemblies in the core.

AND A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one SDC train is in operation and circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months primary coolant at a flow rate of _>1000 gpm.

Palisades Nuclear Plant 3.9.4-2 Amendment No. 189

SDC and Coolant Circulation - Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation - Low Water Level LCO 3.9.5 Two SDC trains shall be OPERABLE, and one SDC train shall be in operation.

APPLICABILITY: MODE 6 with the refueling cavity water level < 647 ft elevation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SDC train inoperable. A.1 Initiate action to restore Immediately SDC train to OPERABLE status.

OR A.2 Initiate action to Immediately establish the refueling cavity water level _>647 ft elevation.

Palisades Nuclear Plant 3.9.5-1 Amendment No. 189

SDC and Coolant Circulation - Low Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. No SDC train OPERABLE B.1 Suspend operations Immediately or in operation. involving a reduction in primary coolant boron concentration.

AND B.2 Initiate action to restore Immediately one SDC train to OPERABLE status and to operation.

AND B.3 Initiate action to close Immediately all containment penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one SDC train is in operation and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circulating primary coolant at a flow rate of

Ž1000 gpm.

SR 3.9.5.2 Verify correct breaker alignment and indicated 7 days power available to the required SDC pump that is not in operation.

Palisades Nuclear Plant 3.9.5-2 Amendment No. 189

Refueling Cavity Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Cavity Water Level LCO 3.9.6 The refueling cavity water level shall be maintained _>647 ft elevation.

APPLICABILITY: During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend CORE Immediately level not within limit. ALTERATIONS.

AND A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling cavity water level is _ 647 ft 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elevation.

Palisades Nuclear Plant 3.9.6-1 Amendment No. 189

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location

- The Palisades Nuclear Plant is located on property owned by Consumers Energy on the eastern shore of Lake Michigan approximately four and one-half miles south of the southern city limits of South Haven, Michigan. The minimum distance to the boundary of the exclusion area as defined in 10 CFR 100.3 shall be 677 meters.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor core shall contain 204 fuel assemblies. Each assembly shall consist of a matrix of zircaloy-4 clad fuel rods with an initial composition of depleted, natural, or slightly enriched uranium dioxide (U0 2 ) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.

Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. A core plug or plugs may be used to replace one or more fuel assemblies subject to the analysis of the resulting power distribution.

Poison may be placed in the fuel bundles for long-term reactivity control.

4.2.2 Control Rod Assemblies The reactor core shall contain 45 control rods. Four of these control rods may consist of part-length absorbers. The control material shall be silver-indium-cadmium, as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The Region I fuel storage racks (See Figure B 3.7.16-1) are designed and shall be maintained with:

a. Fuel assemblies having a maximum planar average U-235 enrichment of 4.95 weight percent; Palisades Nuclear Plant 4.0-1 Amendment No. 41-8, 207

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality (continued)

b. Keff -<0.95 if fully flooded with unborated water, which includes allowances for uncertainties as described in Section 9.11 of the FSAR.

c. A nominal 10.25 inch center to center distance between fuel assemblies with the exception of the single Type E rack which has a nominal 11.25 inch center to center distance between fuel assemblies; and

d. New or irradiated fuel assemblies.

4.3.1.2 The Region II fuel storage racks (See Figure B 3.7.16-1) are designed and shall be maintained with;

a. Fuel assemblies having maximum planar average U-235 enrichment of 4.60 weight percent;

b. Keff < 1.0 if fully flooded with unborated water, which includes allowances for uncertainties as described in Section 9.11 of the FSAR.

C. Keff < 0.95 if fully flooded with water borated to 850 ppm, which includes allowance for uncertainties as described in Section 9.11 of the FSAR.

d. A nominal 9.17 inch center to center distance between fuel assemblies; and

e. New or irradiated fuel assemblies which meet the initial enrichment, burnup, and decay time requirements of Table 3.7.16-1.

4.3.1.3 The new fuel storage racks are designed and shall be maintained with:

a. Twenty four unirradiated fuel assemblies having a maximum planar average U-235 enrichment of 4.95 weight percent, and stored in accordance with the pattern shown in Figure 4.3-1, or Thirty six unirradiated fuel assemblies having a maximum planar average U-235 enrichment of 4.05 weight percent, and stored in accordance with the pattern shown in Figure 4.3-1;

b. Keff - 0.95 when flooded with either full density or low density (optimum moderation) water including allowances for uncertainties as described in Section 9.11 of the FSAR.

Palisades Nuclear Plant 4.0-2 Amendment No. 44-8, 207

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality (continued)

c. The pitch of the new fuel storage rack lattice being > 9.375 inches and every other position in the lattice being permanently occupied by an 8" x 8" structural steel or core plugs, resulting in a nominal 13.26 inch center to center distance between fuel assemblies placed in alternating storage locations.

4.3.2 Drainage The spent fuel storage pool cooling system suction and discharge piping is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 644 ft 5 inches.

4.3.3 Capacity The spent fuel storage pool and north tilt pit are designed and shall be maintained with a storage capacity limited to no more than 892 fuel assemblies.

Palisades Nuclear Plant 4.0-3 Amendment No. 1-89, 207

Design Features 4.0 4.0 DESIGN FEATURES DOOOOOD__DO ODODODODODO@

DODOIODODOOO CENTERLINE- LEGEND PATTERN REPEATS D 8X8 STEEL BOX BEAM O ASSEMBLY STORAGE LOCATION (ENRICHMENT<= 4.95 WT% U-235)

ASSEMBLY STORAGE LOCATION (ENRICHMENT <= 4.05 WT% U-235)

Note: If any assemblies containing fuel enrichments greater than 4.05% U-235 are stored in the New Fuel Storage Rack, the center row must remain empty.

Figure 4.3-1 (page 1 of 1)

New Fuel Storage Rack Arrangement Palisades Nuclear Plant 4.0-4 .Amendment No. 207

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant superintendent shall be responsible for overall plant operation and shall delegate in writing the succession for this responsibility during his absence.

The plant superintendent or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The Shift Supervisor (SS) shall be responsible for the control room command function. During any absence of the SS from the control room while the plant is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the SS from the control room while the plant is in MODE 5 or 6 an individual with an active SRO license or Reactor'Operator (RO) license shall be designated to assume the control room command function.

Palisades Nuclear Plant 5.0-1 Amendment No. 189

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the Palisades plant.

a. Lines of authority, responsibility and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented, and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key positions, or in equivalent forms of documentation. These requirements and the plant specific equivalent of those titles referred to in these Technical Specifications shall be documented in the FSAR.

b. The plant superintendent shall be responsible for overall plant safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. A specified corporate executive shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out radiation safety and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Plant Staff

a. A non-licensed operator shall be assigned when fuel is in the reactor and an additional non-licensed operator shall be assigned when the reactor is operating in MODES 1, 2, 3, or 4.

b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the plant is in MODES 1, 2, 3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.

Palisades Nuclear Plant 5.0-2 Amendment No. 189

Organization 5,2 5.2 Organization 5.2.2 Plant Staff (continued)

c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i), and 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the requirements.

d. A radiation safety technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

e. Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g.,

licensed SROs, licensed ROs, radiation safety personnel, auxiliary operators, and key maintenance personnel).

The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.

Any deviations from the overtime guidelines shall be authorized in advance by the plant superintendent or his designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation. Routine deviation from the working hour guidelines shall not be authorized.

Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

f. The operations manager or an assistant operations manager shall hold an SRO license. The individual holding the SRO license shall be responsible for directing the activities of the licensed operators.

g. An individual shall provide advisory technical support to the plant operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the plant. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift (Published in Federal Register 50 FR 43621, October 28, 1985).

Palisades Nuclear Plant 5.0-3 Amendment No. 8, 196

Plant Staff Qualifications 5:3 5.0 ADMINISTRATIVE CONTROLS 5.3 Plant Staff Qualifications 5.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N1 8.1-1971 for comparable positions except for the education and experience eligibility requirements for operator license applicants, and changes thereto, shall be those previously reviewed and approved by the NRC, specifically those referenced in NRC Safety Evaluation dated October 24, 2003.

5.3.2 The radiation safety manager shall meet the qualifications of a Radiation Protection Manager as defined in Regulatory Guide 1.8, September 1975. For the purpose of this section, "Equivalent," as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following: (a) Formal schooling in science or engineering, or (b) operational or technical experience and training in nuclear power.

5.3.3 The individual, required by Specification 5.2.2g, assigned to provide advisory technical support to the plant operations shift crew, shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift (Published in Federal Register 50 FR 43621, October 28, 1985).

5.3.4 The plant staff who perform reviews which ensure compliance with 10 CFR 50.59 shall meet or exceed the minimum qualifications of ANS 3.1-1987, Section 4.7.1 and 4.7.2. A Senior Reactor Operator license or certification shall be considered equivalent to a bachelors degree for the purpose of this specification.

Palisades Nuclear Plant 5.0-4 Amendment No. 88, 1-96, 212

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Site Fire Protection Program implementation.

d. All programs specified in Specification 5.5.

Palisades Nuclear Plant 5.0-5 Amendment No. 44, 1-96, 213

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained:

5.5.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b. The ODCM shall also contain (1) the radioactive effluent controls and radiological environmental monitoring activities and (2) descriptions of the information that should be included in the Radiological Environmental Operating Report, and Radioactive Effluent Release Report required by Specification 5.6.2 and Specification 5.6.3.

c. Changes to ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes, and

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after approval by the plant superintendent.

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

Palisades Nuclear Plant 5.0-6 Amendment No. 8, 196

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage to the engineered safeguards rooms, from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident, to as low as practical. The systems include the Containment Spray System, the Safety Injection System, the Shutdown Cooling System, and the containment sump suction piping. This program shall include the following:

a. Provisions establishing preventive maintenance and periodic visual inspection requirements, and

b. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

c. The portion of the shutdown cooling system that is outside the containment shall be tested either by use in normal operation or hydrostatically tested at 255 psig.

d. Piping from valves CV-3029 and CV-3030 to the discharge of the safety injection pumps and containment spray pumps shall be hydrostatically tested at no less than 100 psig.

e. The maximum allowable leakage from the recirculation heat removal systems' components (which include valve stems, flanges and pump seals) shall not exceed 0.2 gallon per minute under the normal hydrostatic head from the SIRW tank.

5.5.3 Post Accident Samplinq Proqram

[deleted]

Palisades Nuclear Plant 5.0-7 Amendment No. 1-89, 4-98, %, 213

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. Tho program (1) shall be contained in the Offsite Dose Calculation Manual (ODCM), (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402.

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM,

d. Limitation on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each plant to unrestricted areas conforming to 10 CFR 50, Appendix I,

e. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: a dose rate < 500 mrem/yr to the whole body and a dose rate < 3000 mrem/yr to the skin, and

2. For iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate < 1500 mrem/yr to any organ;

f. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary conforming to 10 CFR 50, Appendix I, Palisades Nuclear Plant 5.0-8 Amendment No. 4-89, 196

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

g. Limitations on the annual and quarterly doses to a member of the public from Iodine-i131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each plant to areas beyond the site boundary conforming to 10 CFR 50, Appendix I,

h. Limitations on the annual doses or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

Palisades Nuclear Plant 5.0-9 Amendment No. 89, 196

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Containment Structural Integrity Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, toensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Containment Structural Integrity Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWE and IWL.

If, as a result of a tendon inspection, corrective retensioning of five percent (8) or more of the total number of dome tendons is necessary to restore their liftoff forces to within the limits, a dome delamination inspection shall be performed within 90 days following such corrective retensioning. The results of this inspection shall be reported to the NRC in accordance with Specification 5.6.7, "Containment Structural Integrity Surveillance Report."

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Containment Structural Integrity Surveillance Program inspection frequencies.

5.5.6 Primary Coolant Pump Flywheel Surveillance Program

a. Surveillance of the primary coolant pump flywheels shall consist of a 100% volumetric inspection of the upper flywheels each 10 years.

b. The provisions of SR 3.0.2 are not applicable to the Flywheel Testing Program.

Palisades Nuclear Plant 5.0-10 Amendment No. 189

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda (B&PV Code) as follows:

B&PV Code terminology Required interval for inservice testing for performing inservice activities testing activities Weekly < 7 days Monthly _ 31 days Quarterly or every 3 months < 92 days Semiannually or every 6 months < 184 days Every 9 months _ 276 days Yearly or annually < 366 days Biennially or every 2 years < 731 days

b. The provisions of SR 3.0.2 are applicable to the above required intervals for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the B&PV Code shall be construed to supersede the requirements of any Technical Specification.

5.5.8 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following provisions:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes.

Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE Palisades Nuclear Plant 5.0-11 Amendment No. 4-8-, 223

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program

b. Performance criteria for SG tube integrity. (continued)

1. Structural integrity performance criterion: All in-service SG tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 0.3 gpm.

3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "PCS Operational LEAKAGE."

c. Provisions for SG tube repair criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged.

d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube repair criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. An assessment of degradation shall be performed to Palisades Nuclear Plant 5.0-12 Amendment No. 4W-8, 223

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program

d. Provisions for SG tube inspections. (continued) determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations 1: Inspect 100% of the tubes in each SG during the first refueling outage following SG replacement.

2. Inspect 100% of the tubes at sequential periods of 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. No SG shall operate for more than 24 effective full power months or one refueling outage (whichever is less) without being inspected.

3. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever is less). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

d. Provisions for monitoring operational primary to secondary LEAKAGE.

Palisades Nuclear Plant 5.0-13 Amendment No. 489, 223

Programs and Manuals 5.5 5.5 Programs and Manuals This page retained for page numbering Palisades Nuclear Plant 5.0-14 Amendment No. 4-88, 223

Programs and Manuals 5.5 5.5 Programs and Manuals This page retained for page numbering Palisades Nuclear Plant 5.0-15 Amendment No. 489, 223

Programs and Manuals 5.5 5.5 Programs and Manuals This page retained for page numbering Palisades Nuclear Plant 5.0-16 Amendment No. 48&, 223

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Secondary Water Chemistry Program A program shall be established, implemented and maintained for monitoring of secondary water chemistry to inhibit steam generator tube degradation and shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables,

b. Identification of the procedures used to measure the values of the critical variables,

c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

d. Procedures for the recording and management of data,

e. Procedures defining corrective actions for all off-control point chemistry conditions, and

f. A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective actions.

5.5.10 Ventilation Filter Testing Program A program shall be established to implement the following required testing of Control Room Ventilation (CRV) and Fuel Handling Area Ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2 (RG 1.52), and in accordance with RG 1.52 and ASME N510-1989, at the system flowrates and tolerances specified below*:

a. Demonstrate for each of the ventilation systems that an inplacetest of the High Efficiency Particulate Air (HEPA) filters shows a penetration and system bypass < 0.05% for the CRV and < 1.00% for the Fuel Handling Area Ventilation System when tested in accordance with RG 1.52 and ASME N510-1989:

Ventilation System Flowrate (CFM)

V-8A or V-8B 7300 +/- 20%

V-8A and V-8B 10,000 +/- 20%

V-95 or V-96 12,500 +/- 10%

Palisades 'Nuclear Plant 5.0-17 Amendment No. 189

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (continued)

b. Demonstrate for each of the ventilation systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% for the CRV and < 1.00% for the Fuel Handling Area Ventilation System when tested in accordance with RG 1.52 and ASME N510-1989.

Ventilation System Flowrate (CFM)

V-8A and V-8B 10,000 +/- 20%

V-26A and V-26B 3200 +10% -5%

c. Demonstrate for each of the ventilation systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in RG 1.52 shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of

< 301C and equal to the relative humidity specified as follows:

Ventilation System Penetration Relative Humidity VF-66 6.00% 95%

VFC-26A and VFC-26B 0.157% 70%

d. For each of the ventilation systems, demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with RG 1.52 and ASME N510-1989:

Ventilation System Delta P (In HP0) Flowrate (CFM)

V-8A and V-8B 6.0 10,000 + 20%

VF-26A and VF-26B 8.0 3200 +10% -5%

e. Demonstrate that the heaters for the CRV system dissipates the following specified value +/- 20% when tested in accordance with ASME N510-1989:

Ventilation System Wattage VHX-26A and VHX-26B 15 kW The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Ventilation Filter Testing Program frequencies.

Should the 720-hour limitation on charcoal adsorber operation occur during a plant operation requiring the use of the charcoal adsorber - such as refueling - testing may be delayed until the completion of the plant operation or up to 1,500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months of filter operation; whichever occurs first.

Palisades Nuclear Plant 5.0-18 Amendment No. 189

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Fuel Oil Testing Program A fuel-oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling requirements, testing requirements, and acceptance criteria, based on the diesel manufacturer's specifications and applicable ASTM Standards. The program shall establish the following:

a. Acceptability of new fuel oil prior to addition to the Fuel Oil Storage Tank, and acceptability of fuel oil stored in the Fuel Oil Storage Tank, by determining that the fuel oil has the following properties within limits:

1. API gravity or an absolute specific gravity,

2. Kinematic viscosity, and

3. Water and sediment content.

b. Other properties of fuel oil stored in the Fuel Oil Storage Tank, specified by the diesel manufacturers or specified for grade 2D fuel oil in ASTM D 975, are within limits.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Fuel Oil Testing Program.

5.5.12 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

Palisades Nuclear Plant 5.0-19 Amendment No. 88, 204

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Technical Specifications (TS) Bases Control Program (continued)

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of Specification 5.5.12.b. above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).

5.5.13 Safety Functions Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss, of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or Palisades Nuclear Plant 5.0-20* Amendment No. 189

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Safety Functions Determination Program (SFDP) (continued)

c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

5.5.14 Containment Leak Rate Testing Program

a. A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines of Regulatory Guide 1.163, "Performance-Based Containment Leakage-Test Program," dated September 1995, as modified by the following exceptions:

1. Leakage rate testing is not necessary after opening the Emergency Escape Air Lock doors for post-test restoration or post-test adjustment of the air lock door seals. However, a seal contact check shall be performed instead.

Emergency Escape Airlock door opening, solely for the purpose of strongback removal and performance of the seal contact check, does not necessitate additional pressure testing.

2. Leakage rate testing at Pa is not necessary after adjustment of the Personnel Air Lock door seals. However, a between-the-seals test shall be performed at Ž10 psig instead.

3. Leakage rate testing frequency for the Containment 4 inch purge exhaust valves, the 8 inch purge exhaust valves, and the 12 inch air room supply valves may be extended up to 60 months based on component performance.

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 53 psig. The containment design pressure is 55 psig.

c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of containment air weight per day.

Palisades Nuclear Plant 5.0-21 Amendment No. 48, 194

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Containment Leak Rate Testing Pro-gram (continued)

d. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criteria is _<1.0 La. During the first plant startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests and< 0.75 La for Type A tests.

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage is _<1.0 La when tested at __Pa and combined with all penetrations and valves subjected to Type B and C tests. However, during the first unit startup following testing performed in accordance with this program, the leakage rate acceptance criteria is < 0.6 La when combined with all penetrations and valves subjected to Type B and C tests.

b) For each Personnel Air Lock door, leakage is _<0.023 La when pressurized to > 10 psig.

c) For each Emergency Escape Air Lock door, a seal contact check , consisting of a verification of continuous contact between the seals and the sealing surfaces, is acceptable.

e. "Containment OPERABILITY" is equivalent to "Containment Integrity" for the purposes of the testing requirements.

f. The provisions of SR 3.0.3 are applicable to the Containment Leak Rate Testing Program requirements.

g. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

Palisades Nuclear Plant 5.0-22 P Amendment No. 4-9, 194

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Process Control Program

a. The Process Control Program shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR 20, 10 CFR 71, Federal and State regulations, and other requirements governing the disposal of the radioactive waste.

b. Changes to the Process Control Program:

1. Shall be documented and records of reviews performed shall be retained as required by the Quality Program, CPC-2A. This documentation shall contain:

a) Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s) and b) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2. Shall become effective after approval by the plant superintendent.

Palisades Nuclear Plant 5.0-23 Amendment No. 4-99, 194

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 (Deleted) 5.6.2 Radioloqical Environmental Operating Report The Radiological Environmental Operating Report covering the operation of the plant during the previous calendar year shall be submitted before May 15 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering operation of the plant in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual and Process Control Program, and shall be in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

Nuclear Plant Palisades Nuclear Palisades Plant 5.0-24 5.0-24 Amendment No. 1-gQ, 2-1-s, 220 Amendment No. 449, 24-3, 220

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 (Deleted) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

3.1.1 Shutdown Margin 3.1.6 Regulating Rod Group Position Limits 3.2.1 Linear Heat Rate Limits 3.2.2 Radial Peaking Factor Limits 3.2.4 ASI Limits 3.4.1 DNB Limits

b. The analytical methods used to determine the core operating limits shall be those approved by the NRC, specifically those described in the latest approved revision of the following documents:

1. EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs," Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

2. ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. (Bases report not approved) (LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

3. XN-NF-82-21 (P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company.

(LCOs 3.2.1, 3.2.2, & 3.2.4)

4. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs, "Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

5. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company. (Bases document not approved)

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-25 Amendment No. 49-8, 2-1-, 220

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

6. EMF-2310 (P)(A), Revision 0, Framatome ANP, Inc., May 2001, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

7. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, & 3.2.2)

8. ANF-89-151 (P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

9. EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

Siemens Power Corporation. (LCOs 3.2.1, 3.2.2, & 3.2.4)

10. XN-NF-621(P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company. (LCOs 3.2.1, 3.2.2, & 3.2.4)

11. XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

12. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWD/MTU," Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

13. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-26 Amendment No. 4-88, 209

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

14. EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

15. EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, & 3.2.2)

16. ANF-87-150 Volume 2, "Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. [Approved for use in the Palisades design during the NRC review of license Amendment 118, November 15, 1988] (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.4.1)

17. EMF-1 961 (P)(A), Revision 0, Siemens Power Corporation, July 2000, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, &

3.4.1)

18. EMF-2328 (P)(A), Revision 0, Framatome ANP, Inc., March 2001, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based."

(LCOs 3.1.6, 3.2.1, & 3.2.2)

19. BAW-2489P, "Revised Fuel Assembly Growth Correlation for Palisades." (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC.

Palisades Nuclear Plant 5.0-27 Amendment No. 41-9, 4-95, 209, 24-7, 222

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 Post Accident Monitorinq Report When a report is required by LCO 3.3.7, "Post Accident Monitoring Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

5.6.7 Containment Structural InteQrity Surveillance Report Reports shall be submitted to the NRC covering Prestressing, Anchorage, and Dome Delamination tests within 90 days after completion of the tests.

5.6.8 Steam Generator Tube Surveillance Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.8, Steam Generator (SG) Program. The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each active degradation mechanism,

f. Total number and percentage of tubes plugged to date,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and

h. The effective plugging percentage for all plugging in each SG.

Palisades Nuclear Plant 5.0-28 Amendment No. 4-88, 223

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601 (c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP), or equivalent, that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP, or equivalent, while performing their assigned duties, provided that they are otherwise following plant radiation

-protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation.

dose rates in the area; or

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or Palisades Nuclear Plant 5.0-29 Amendment No. 48-, 196

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area, and who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

Palisades Nuclear Plant 5.0-30 Amendment No. 44-8, 196

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP, or equivalent, while performing radiation surveys in such areas, provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits dose rate ahd cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, and with the means to communicate with and control every individual in the area, or Palisades Nuclear Plant 5.0-31 Amendment No. 4-89. 196

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 Higqh Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; and who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into suchareas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

Palisades Nuclear Plant 5.0-32 Amendment No. 1-89, 196

ML070110053

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