Text

Palisades - Final Safety Analysis Report Update, Revision 32, Chapter 1 - Introduction and General Description on Plant - Tables
	ML16120A327
Person / Time
Site:	Palisades
Issue date:	04/18/2016
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
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FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-1 Revision 28 Page 1 of 3 CHRONOLOGICAL LICENSING EVENTS Date Docket 50-255 CPOL Application FSAR Operating License Other June 2, 1966 CP Co Files CPOL Application PSAR Included With Application

March 14, 1967 AEC Issues CPPR-25

November 1, 1968 CP Co Files Amendment 9 to CPOL Application FSAR, Rev 0, Included Initial Operating License Application for Operation at 2,200 MWt Core October 9, 1970

CP Co File Construction Stage Environmental Report March 24, 1971

NRC Issues IDPR-20 (1 MW)

August 18, 1971

CP Co Files ER Supplement (Special Report 4) November 20, 1971

Amendment 1 - Authorization for 20% Power (440 MW)

March 10, 1972

Amendment 2 - Authorization for 60% power (1,320 MW)

June 1972

NRC Issues Final Environmental Statement July 1972

CP Co Files Operating Stage ER September 1, 1972 NRC Issues OL DPR-20

Amendment 3 - Authorized 60% Power October 16, 1972

Amendment 4 - Authorized 100% Power (Limited to 60% Power)

March 23, 1973

Authorization for 100% Power (Limited to 85% Power)

January 22, 1974 CP Co Files Amendment 28 to CPOL Full Revision to FSAR (Denoted as Amendment 28) CP Co Application for Full-Term Operating License at 2,638 MWt

Core FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-1 Revision 28 Page 2 of 3 CHRONOLOGICAL LICENSING EVENTS Date Docket 50-255 CPOL Application FSAR Operating License Other December 12, 1974

NPDES Permit Granted by Michigan DNR August 2, 1976

Modified NPDES Permit Granted August 12, 1977

CP Co Requests the OL Limit Be Increased to 2,530 MWt Core Power November 1, 1977

NRC Issues Amendment 31 to DPR-20 Granting Power Operation up to 2,530 MWt February 1978

NRC Initiated Systematic Evaluation Program (SEP)

October 1978

NRC Issues Final Addendum to the Final Environmental Statement October 1982

SEP Integrated Plant Safety Assessment Final Report (NUREG 0820) issued November, 1983

Supplement 1 to SEP Integrated Plant Safety Assessment Report issued. June 28, 1984 Revision 0, Initial FSAR Update Pursuant to 10 CFR 50.71(e)

October 22, 1990

NRC issues Environmental Assessment in support of POL to FTOL conversion November 21, 1991

NRC issues SER (NUREG 1424) in support of POL to FTOL conversion February 21, 1991

FTOL issued by NRC

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-1 Revision 28 Page 3 of 3 CHRONOLOGICAL LICENSING EVENTS November 30, 1999

NRC approved conversion to Improved Technical Specifications Amendment 189 based on NUREG 1432, Standard Technical Specifications.

October 24, 2000

Improved Technical Specifications implemented.

December 14, 2000

Construction period recaptured with change of License expiration date to March 24, 2011.

Amendment 192 June 23, 2004 NRC issued Amendment 216 to Palisades Operating License to authorize operation of the facility at steady state reactor core power levels up to 2565.4 Megawatts thermal [FC-977].

January 17, 2007 On January 17, 2007, the Renewed Facility Operating License was issued by the NRC, extending the license expiration date to March 24, 2031.

April 11, 2007 On April 11, 2007, the NRC issued Amendment 224 to the Palisades Renewed Facility Operating License to reflect the transfer of ownership to Entergy Nuclear Palisades, LLC, and operating authority Entergy Nuclear Operations, Inc.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 1 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Plant Net Electrical Power Output @ 2,200 MWt 700 MWe Net Electrical Power Output @ 2,565.4 MWt 750 MWe Maximum Expected Gross Electrical Output

@ 2,650 MWt 845 MWe

Nuclear Steam Supply System Core Thermal Output 2,200 MWt Initial, 2,638 MWt Ultimate, 2,565.4 MWt Presently Operating Pressure 2,100 psia Initial Rating, 2,250 psia for Ultimate Rating, 2060 present nominal rating Design Pressure 2,500 psia Primary Coolant Inlet Temperature 545°F Initial Rating, 537°F Presently Primary Coolant Outlet Temperature 591°F Initial Rating, 583°F Presently Pipe Size: Outlet (ID) 42" (Wall Thickness) 4" Inlet (ID) 30" (Wall Thickness) 3" Flow per Loop 62.5 x 10 6 lb/h original 72.3 x 10 6 lb/h present nominal

Number of Loops 2

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 2 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Number of Pumps 4 Type Vertical, Centrifugal, Mechanical Seals Design Flow/Pump 83,000 gpm Design Head 260'

Core Total Heat Output 2,565.4 MWt Heat Generated in Fuel 97.4%

Design Thermal Overpower 15%

DNB Ratio at Nominal Conditions 2.00 Core Power Density 69.3 kW/Liter original 79.8 kW/Liter presently Number of Fuel Bundles 204 Number of Fuel Rods/Bundle Initial Core Loading (A, B, C1 + Typical Reload Fuel) 212 Number of Fuel Rods/Bundle 216 typical Fuel Rod Pitch 0.550" Fuel Clad Material Zircaloy-4 or M5 Number of Full-Length Control Rods 41 Number of Part-Length Control Rods 4 Control Rod Pitch 16.97" Absorber Material Silver-Indium-Cadmium Control Rod Drive Type Rack and Pinion Equivalent Core Diameter 136.7" FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 3 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Reactor Vessel Inside Diameter 172" Overall Length 40'-3/4" Wall Thickness Without Clad 8-1/2" Wall Material SA-302 Cladding Thickness 3/16" Cladding Material SS-308/309 Design Temperature 650°F Design Pressure 2,500 psia NDT Temperature (Initial) 40°F (This value does not apply to the vessel head. The vessel

head RT-ndt is 72°F, Reference 14.)

Total Weight 426 Tons

Steam Generators Number of Units 2 Type Vertical "U" Tube Outside Diameter 20'-10" Length 59'-2" Number of Tubes 8,219 Initial Design Tube OD 3/4" Tube Material Inconel Shell Material SA-302B and SA-516, Gr 70

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 4 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Primary Side Tube Side Design Pressure 2,500 psia Tube Side Design Temperature 650°F Tube Side Operating Pressure 2,060 psia Coolant Inlet Temperature (nominal) 582.7°F Coolant Outlet Temperature (nominal) 537.3°F Bottom Head Clad Material SS-304 Secondary Side Shell Side Design Pressure 1,000 psia Shell Side Design Temperature 550°F Operating Pressure (Steam Generator Outlet at Plant Rating of 2,565.4 MWt Core) 760-770 psia presently Operating Temperature 512°F Quality 99.8%

Feedwater Inlet Temperature 440.7°F Steam Flow/Steam Generator (10 6 lb/h) 5.649

Turbine Cycle Turbine Design Tandem-Compound, 1 HP, 2 LP Turbines Exhaust Pressure 1.8 inHg Makeup 0.25%

Steam Atmospheric Dump (Rated Steam Flow) 35%

Steam Bypass to Condenser (Rated Steam Flow) 5%

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 5 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Feedwater Heater Stages 6 Condensate Pumps - Number 2 - Half Capacity Design Flow 9,250 gpm Design Head 1,000' Feedwater Pumps - Number 2 - Half Capacity Design Flow 13,500 gpm Design Head 1,920' Condenser Circulating Pumps - Number 2 - Half Capacity Design Flow 205,000 gpm/Pump Design Head 90'

Generator Design Rating 955 MVA Power Factor 0.85 Terminal Voltage 22,000

NSSS Auxiliary Systems

1. Chemical and Volume Control System Normal Letdown Flow Rate 40 gpm Maximum Letdown Flow Rate 133 gpm Charging Pumps - Number 2 - Fixed Capacity 1 - Variable Capacity Design Flow 40 gpm Design Head 6,375'

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 6 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Metering Pumps - Number 1 Design Flow Range 0 to 35 gpm Maximum Outlet Pressure 120 psig Regenerative Heat Exchanger - Number 1 - Full Capacity Design Heat Transfer 6.6 x 10 6 Btu/h Letdown Heat Exchanger - Number 1 - Full Capacity Design Heat Transfer 19.1 x 10 6 Btu/h Demineralizers - Number 2 - Purification 1 - Deborating Nominal Rating 40 gpm Maximum Flow 160 gpm Resin Type H-OH Resin Volume 32 ft 3 Filter - Number 2 Type Cartridge Design Rating 120 gpm Filter Size 2 Microns

2. Safety Injection System Safety Injection Tanks - Number 4 Volume - Total 2,000 ft 3 Borated Water 1,000 ft 3 Nitrogen @ 200 psia 1,000 ft 3 Design Pressure 250 psia

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 7 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Design Temperature 200°F High-Pressure Pumps - Number 2 - Full Capacity Rating, Each 300 gpm Head 2,500' Low-Pressure Pumps - Number 2 - Full Capacity Rating, Each 3,000 gpm Head 350'

3. Containment Air Cooling System Air Coolers - Number 4 (3-safety related)

Rating, Each Safety Related Cooler (Btu/h) @ 283°F, 55 psig 87.2 x 10 6 (DBA) Cooling Water Flow, Each Set per FSAR Sect 9.1.2.3 (DBA)

Airflow 30,000 ft 3/min (DBA)

Rating (Safety Related Cooler) 1.98 x 10 6 Btu/h (Normal)* (Non-safety Related Cooler) 1.98 x 10 6 Btu/h (Normal)*

Cooling Water Flow, Each 500 gpm (Normal)

Airflow 60,000 ft 3/min (Normal)

Cooler performance based on 115°F EAT & 81.5°F EWT

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 8 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

4. Containment Spray System Spray Pumps - Number 3 - Half Capacity Rating, Each 1,340 gpm Head 450' Heat Exchangers (Shutdown Cooling Heat Exchangers) 2 Rating, Each (Btu/h) 83.5 x 10 6 @ 283°F

5. Deleted

6. SIRW Tank Fluid Volume 285,000 Gallons Boron Concentration 1720-2500 ppm

7. Shutdown Cooling System Auxiliary Feedwater Pumps - Number 3 - Full Capacity Turbine Driven - Number 1 Rating 415 gpm Head 2,730' Motor Driven - Number 2 Approximate Rating (Pump P8A) 415 gpm (Pump P8C) 330 gpm At Approximate Head (Pump P8A) 2,730' (Pump P8C) 2,260'

Pumps - Use Low-Pressure Safety Injection Pumps

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 9 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Heat Exchangers - Number 2 - Half Capacity Rating, Each 80.0 x 10 6 Btu/h 8. Component Cooling System Component Cooling Pumps - Number 3 - Half Capacity Rating, Each 6,000 gpm Head 164' Heat Exchangers - Number 2 Rating, Each 50.5 x 10 6 Btu/h (Normal)

Rating, Each 85.0 x 10 6 Btu/h (Post-DBA)

9. Spent Fuel Cooling System Spent Fuel Pool Capacity 4 Cores Volume of Empty SFP Cavity 21,885 ft 3 Fuel Assemblies 892 Pumps - Number 2 - Half Capacity Rating, Each 1,700 gpm Head 64' Heat Exchanger - Number 2 Combined Rating 23 x 10 6 Btu/h Filter - Number 1 Type Cartridge Rating 150 gpm Size 25 Microns

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 10 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Demineralizer - Number 1 Resin Type H-OH Bed Size 68 ft 3 Nominal Flow 150 gpm

10. Shield Cooling System Pumps - Number 2 - Full Capacity Rating, Each 180 gpm Head 79' Heat Exchanger - Number 1 - Full Capacity Rating 2 x 10 5 Btu/h Sets of Cooling Coils - Number 2 - Full Capacity

Conventional Plant Auxiliary Systems

1. Service Water System Service Water Pumps - Number 3 - Half Capacity Rating 8,000 gpm Head 140'

2. Compressed Air System Compressors - Number 3 Rating 288 scfm Discharge Pressure 100 psig

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 11 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

3. High-Pressure Air Systems Compressors - Number 3 Rating, Each 22.3 scfm Discharge Pressure 325 psig

Containment Type Reinforced Concrete, Prestressed, Post-Tensioned Diameter 116'-0" ID (Inside)

Height 190'-6" (Inside)

Liner - Material A442 Plate Thickness 1/4" Design Pressure 55 psig Design Temperature 283°F Free Volume 1.64 x 10 6 ft 3 Leak Rate 0.1%/Day

Electrical Equipment Main Transformer - Rating 875 MVA Voltage 345 kV Diesel Generators - Number 2 - Full Capacity Rating 3,000 kVA Fuel Oil Capacity 1 Week Following a DBA

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 31 Page 12 of 12 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Station Battery - Number 2 Type Lead Calcium Number of Cells 59 Rating 125 V, 1,800 Ah Chargers - Number 4 Inverters - Number 4 AC/DC Voltage 120/125 Rating 6 kVA

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-6 Revision 32 Page 1 of 1 ESTIMATED USE ON MARCH 24, 2031 RPV Material Material Heat # Cu (%) Initial USE (ft-lbs) 1/4t Neutron Fluence (10 19 n/cm 2) USE (ft-lbs)2-112A/C*

W5214 0.213 118 1.275 64.9 3-112A/C*

W5214 0.213 118 1.275 64.9 34B009 0.192 111 1.275 56.6 9-112* 27204 0.203 84 2.024 49.6 D-3803-1* C-1279 0.24 102 2.024 65.3 D-3803-2* A-0313 0.24 87 2.024 53.1 D-3803-3* C-1279 0.24 91 2.024 58.2 D-3804-1* C-1308A 0.19 72 2.024 48.2 D-3804-2* C-1308B 0.19 76 2.024 50.9 D-3804-3* B-5294 0.12 73 2.024 54.8 D-3802-1**

C-1279 0.21 75 0.0902 62.3 D-3802-2**

C-1308 0.19 73 0.0902 61.3 D-3802-3**

C-1281 0.25 62.2*** 0.0902 50.1 D-3802-3**

C-1281 0.25 59**** 0.0902 47.5 1-112A/B/C**

W5214 0.213 118 0.0573 82.6 8-112** 34B009 0.192 111 0.0902 72.2

Traditional beltline materials (Reference 106)

- Extended beltline mate rials (Reference 104) *** CVGraph Method **** 95% Shear Method FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-7 Revision 32 Page 1 of 1 RTMAX-X Values for Reactor Vessel at 42.1 Effective Full Power Years Lower and Intermediate Shell Region (Twall 9.5 inches)

(1) Upper Shell Region (10.5 inches < Twall 11.5 inches)

(1) Reactor Vessel 10 CFR 50.61a Screening Criteria Reactor Vessel 10 CFR 50.61a Screening Criteria Axial Weld - RT MAX-AW (°F) 237.0 269 135.2 222 Plate - RT MAX-PL (°F) 199.4 356 149.8 293 Axial Weld and Plate -

RT MAX-AW + RT MAX-PL (°F) 436.4 538 285.0 445 Circumferential Weld -

RT MAX-CW (°F) 247.6 312 149.8 269 Note: (1) T WALL is the reactor vessel thickness including the cladding.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-8Revision 30Page 1 of 1

SUMMARY

OF FATIGUE USAGE FACTORS AT NUREG/CR-6260SAMPLE LOCATIONS APPLICABLE TO PALISADESLocationMaterial 60 Year CUF F enEnvironmental CUF RPVLower Head to ShellJuncture SA-533 Grade BClass 1 0.004 2.5 0 0.009 RPV Inlet NozzleSA-302 Grade B 0.104 2.5 0 0.260 RPV Outlet Nozzle SA-508 Class 2 0.181 2.5 0 0.454Charging NozzleSB-166 Alloy 600Stainless Steel 0.306 0.006 1.49 15.35 0.456 0.092Surge Line ElbowSA-376 Type 316 0.01515.35 0.238Safety Injection Nozzle SA-516 Grade 70 0.036 1.7 6 0.06 4Shutdown Cooling LineInlet TransitionSA-516 Grade 700.0097 1.7 6 0.017Values from Reference 96, Attachment 5.4 FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 1 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 1.Each year, following the submittal of the Palisades License Renewal Application and at leastthree months before the scheduled completion of the NRC review, Entergy will submit anamendment to the application pursuant to 10 CFR 54.21 (b). This amendment will identify anychanges to the Current Licensing Basis of the facility that materially affect the contents of theLicense Renewal Application, including the FSAR supplement, that have not already been submitted. (Reference 57)

NA 2.Equivalent Margins Analysis - Entergy will submit an equivalent margins analysis, completedin accordance with 10 CFR 50 Appendix G Section IV.A.1, for NRC approval, at least threeyears before any reactor vessel beltline material upper shelf energy decreases to less than 50ft-lb. (Reference 57)Reactor Vessel IntegritySurveillance Program 3.PTS Management - At the appropriate time, prior to exceeding the PTS screening criteria,Palisades will select the optimum alternative to manage PTS in accordance with NRC regulations and make relevant submittals to obtain NRC review and approval. (Reference 57)Reactor Vessel Integrity Surveillance Program 4.Charging Line Fatigue - Entergy will evaluate the effect the increase in variable speedcharging pump out-of-service events may have on these lines (Charging Lines Inboard of the Regenerative Heat Exchanger), and will take actions necessary to ensure these lines meetlicensing basis design criteria for the extended operating period. Entergy will complete thisevaluation and will advise the NRC of the results, and of any necessary corrective actions, before the end of the current licensed operating period. (Reference 57)Fatigue Monitoring

Program 5.Fatigue Monitoring of PZR TEs - Entergy will monitor the cumulative number of pressurizertemperature element nozzle fatigue cycles within the Fatigue Monitoring Program, and maintain a special action level to ensure that appropriate actions are taken if at any time thecycle count for any design basis event since 1993 reaches the number assumed by theseanalyses. (Reference 57)Fatigue Monitoring Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 2 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 6.Update Alloy 600 Program - Entergy will revise the Alloy 600 Program to update the PWSCCcorrosion rate assessments and inspection program consistent with the latest NRCrequirements and industry commitments (e.g., EPRI Report 1010087 Materials ReliabilityProgram: Primary System Piping System Butt Weld Inspection and Evaluation Guidelines[MRP-139], (August 2005)). (Reference 57)Alloy 600 Inspection Program 7.Commitment deleted (Reference 94).

Deleted.8.Incorporate AMP & TLAA into FSAR - In a periodic FSAR update following NRC issuance ofthe renewed operating license, in accordance with 10 CFR 50.71 (e), the summarydescriptions of Aging Management Programs and Time Limited Aging Analyses, provided inAppendix A, will be incorporated into appropriate sections of the FSAR. (Reference 57)

NA 9.Expand Quality Program to NSR SSC - The Quality Program implementation procedures willbe expanded to apply the elements of corrective action, confirmation process, andadministrative controls to both safety related and non-safety related systems, structures, andcomponents that are subject to aging management review for license renewal. (Reference 57)Quality 10.Update Bolting Program Standards - Review and revise ASME ISI Master Plan, proceduresthat implement credited License Renewal Programs, and plant maintenance procedures toreflect and reference the applicable guidance provided in NUREG-1339 and EPRI TR-104213for safety and non-safety related bolting. These revisions should also include instructions forselection of bolting material and use of lubricants and sealants, in accordance with theguidelines of EPRI NP-5769 and the additional recommendations of NUREG-1339 to prevent or mitigate degradation and failure of safety-related bolting. (Reference 57)Bolting Integrity Program 11.Define Insp Reqts High Strength Bolts - Evaluate the high strength bolting used forcomponent supports for susceptibility to cracking as described in NUREG-1801,Section XI.M.18, "Parameters Monitored/Inspected," and implement appropriate inspectionrequirements to provide adequate age-management for these bolts (Reference 57).Bolting Integrity Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 3 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 12.Define Boric Acid Insp Walkdown Criteria- Revise applicable plant procedures to includecriteria for observing susceptible SSC, within the scope of license renewal, for boric acidleakage and degradation, during system walkdown inspections. (Reference 57)Boric Acid Corrosion Program 13.Boric Acid Insp Criteria - Revise applicable plant procedure(s) to include explicit acceptancecriteria for boric acid inspections. (Reference 57)Boric Acid Corrosion

Program 14.Boric Acid Insp of Struct & NonASME - Revise applicable plant procedures to includeinspection of structural steel and non-ASME component supports for evidence of boric acidresidue and boric acid wastage/corrosion on a periodic frequency. (Reference 57)Boric Acid Corrosion Program 15.Implement Buried Services Monitoring Program - A Buried Services Corrosion MonitoringProgram will be developed and implemented. Features of the program will includedevelopment and implementation of procedures for inspection of selected buried SSCs forcorrosion, pitting and MIC. The periodicity of these inspections will be based on opportunitiesfor inspection such as scheduled excavation and maintenance work. (Reference 57)Buried ServicesCorrosion Monitoring Program 16.Periodic Clean Inspect FO StorageTank - Develop and implement procedures for periodicdraining and cleaning of diesel fuel oil storage tanks, Emergency Diesel Generator day tanks,and Diesel Fire Pump Day Tanks. These procedures shall include steps to perform a visualinspection of interior tank surfaces for signs of degradation or corrosion, with acceptancecriteria, corrective actions, and documentation of inspection results. (Reference 57)Diesel Fuel Monitoringand Storage Program 17.Periodic Drain Water from Fuel Oil Tanks - Develop and implement procedures for periodicdraining of water accumulated in the bottom of the fuel oil storage tanks and fuel oil day tanks for the Diesel Generators and Diesel Fire Pumps. (Reference 57)Diesel Fuel Monitoring and Storage Program 18.Fuel Oil Tank Bottom Thickness Measurements - Develop and implement procedures forperiodic ultrasonic measurement of thickness of the bottom of Fuel Oil Storage Tanks,Emergency Diesel Generator Day Tanks, and Diesel Fire Pump Day Tanks. (Reference 57)Diesel Fuel Monitoringand Storage Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 4 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 19.Structural Monitoring Program for Fire Barriers - The Structures Monitoring Program shallbe revised to include specific inspection criteria and documentation requirements for verifyingthat walls, ceilings and floors that serve as Fire Protection Program fire barriers are verified tobe free from aging related degradation that would impact the fire barrier's intended function.(Reference 57)Structures Monitoring Program 20.Fire Door Inspection - Plant procedures shall be revised to more specifically address agingrelated degradation and expectations for documentation of fire door condition. (Reference 57)Fire Protection Program 21.Fire Door Clearance Inspections - Develop and implement procedures to perform visualinspections for fire door clearances. (Reference 57)Fire Protection Program 22.Diesel Fire Pump Fuel Line Inspection - Revise diesel-driven fire pump performance testprocedures to more specifically address requirement to inspect and monitor fuel oil supply linefor aging related degradation, and to document inspection results.Fire Protection Program 23.Inspect Below Grade Fire Piping - Develop and implement procedures for inspection ofbelow grade fire protection system piping. Inspections shall be implemented under the BuriedServices Corrosion Monitoring Program. In addition, results of wall thickness inspections ofabove grade fire protection system piping shall be extrapolated to evaluate the wall thicknesscondition of below grade fire protection system piping. Procedures shall include acceptancecriteria, and criteria for further corrective actions if acceptance criteria are not met. (Reference

94)Fire Protection Program/ Buried Services Program 24.Fire Hydrant Inspection & Testing - Plant procedures shall be revised to more specificallyaddress identification of aging related degradation and expectations for documentation of fire hydrant condition. Also, these revisions shall include provisions to perform flow testing for firehydrants within the scope of License Renewal that are credited for fire suppression in thePalisades current licensing basis. (Reference 57)Fire Protection Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 5 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 25.Replace or Test Sprinkler Heads - Develop and implement procedures to replace all sprinklerheads prior to the end of the 50 year service life, or for testing of a representative sample ofsprinkler heads prior to the end of the 50 year service life and at 10 year intervals thereafter, per requirements of NFPA 25, Section 5.3. (Reference 57)Fire Protection Program 26.Non-EQ Commodities Condition Monitoring - A Non-EQ Electrical Commodities ConditionMonitoring Program will be developed and implemented. Features of the program will includedevelopment and implementation of procedures to conduct periodic inspection of insulatedcables and connectors, test sensitive instrumentation circuits, test medium voltage cables,inspect manhole water levels, and inspect non-segregated phase bus and connections.(Reference 94)Non-EQ ElectricalCommodity ConditionMonitoring Program 27.One Time Inspection Program - A One Time Inspection Program will be developed andimplemented. Features of the program are as described in the Enhancement section of LRA Section B2.1.13. (Reference 57)One-Time Inspection

Program 28.Crane Inspection Requirements - Revise crane and fuel handling machine inspectionprocedures to specifically inspect for general corrosion on passive components making up the bridge, trolley, girders, etc., and to inspect rails of Bridge Cranes for wear. Revision should alsoinclude documentation of results of these inspections, acceptance criteria, and qualificationrequirements for inspectors and crane supervisors. (Reference 57)Overhead LoadHandling SystemsInspection Program 29.Reactor Vessel PT/LTOP Curves - The Reactor Vessel Integrity Surveillance Program willensure thatpressure-temperature and LTOP curves are updated to reflect the additionalneutron fluence accumulated duringthe extended operating period. (Reference 57)Reactor Vessel IntegritySurveillance Program 30.RV Surveillance Capsules - Document and establish requirement to save and store all pulledand tested reactor vessel surveillance capsules for future reconstitution use. (Reference 57)Reactor Vessel IntegritySurveillance Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 6 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 31.Surv Capsule Withdrawal Schedule - Evaluate and revise as necessary, the surveillancecapsule withdrawal and testing schedule of FSAR Table 4-20 such that at least one capsuleremains in the reactor vessel and is tested during the period of extended operation to monitor the effects of long-term exposure to neutron irradiation. (Reference 57)Reactor Vessel IntegritySurveillance Program 32.Reactor Vessel Integrity Program - Develop a program level procedure to implement andcontrol Technical Specification and FSAR activities associated with the Reactor VesselIntegrity Surveillance Program, including activities associated with surveillance capsules,pressure-temperature limit curves, LTOP setpoints, neutron embrittlement calculationmethodology, neutron fluence calculations and control, and documentation requirements. Titleof procedure should be, "Reactor Vessel Integrity Surveillance Program." (Reference 57)Reactor Vessel IntegritySurveillance Program 33.Reactor Vessel Internals Program Submittal - Entergy will participate in industry initiativesthat will generate additional data on aging mechanisms relevant to reactor vessel internals(RVI), including void swelling, and develop appropriate inspection techniques to permitdetection and characterization of features of interest. Recommendations for augmentedinspections and techniques resulting from this effort will be incorporated into the ReactorVessel Internals Program as applicable. (Reference 82)Reactor Vessel InternalsInspection Program34. Withdrawn 35.Incorporate Members in Structural Monitoring Program - Incorporate into the StructuralMonitoring Program all structural members listed in Tables 3.5.2-1 through 3.5.2-10 that willuse the Structural Monitoring Program as an AMR. (Reference 57)Structures Monitoring Program 36.Enhance System Walkdown Procedures - Enhance system walkdown procedures to morespecifically address the types of components to be inspected, and to specifically describe therelevant degradation mechanisms and effects of interest, and for use of the Corrective ActionProgram to document aging related degradation, identified during the inspections, that mayaffect the ability of the SSC to perform its intended function. (Reference 57)System Monitoring

Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 7 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 37.Fatigue Monitoring Program - A Fatigue Monitoring Program will be developed andimplemented. Features of the program will include monitoring and tracking selected cyclicloading transients (cycle counting) and their effects on critical reactor pressure boundary components and other selected components. (Reference 57)Fatigue Monitoring Program 38.Incorporate Commitments into FSAR - The final text and schedule of licensee commitmentsthat are confirmed by NRC in the final SER for the Palisades Renewed Operating License willbe incorporated into appropriate locations of the FSAR in the first regular FSAR update under10 CFR 50.71 (e) following NRC issuance of the renewed operating license. (Reference 83)

NA 39.Buried Piping Opportunistic Inspection - Visual inspections of a sample of buried carbon,low-alloy, and stainless steel components will be performed within ten years prior to entering,and within ten years after entering, the period of extended operation. Prior to the tenth year ofeach period, Entergy will perform an evaluation of available data to determine if sufficientopportunistic inspections have been performed within that period to assess the condition of thecomponents. If insufficient data exists, focused inspection(s) will be performed as needed.(Reference 84)Buried ServicesCorrosion Monitoring Program 40.HVAC Flex Joint PM Enhancement- Entergy will enhance the preventive maintenanceprogram to periodically inspect, and replace as necessary, the expansion joints/flexible connections in the portions of the Heating, Ventilation and Air Conditioning System that are in-scope for license renewal. (Reference 94)

NA 41.Industry Standard Use for Tank Inspection - Entergy will identify specific methods ofinspection for individual components as part of the System Monitoring Program implementation procedure development. Industry documents such as EPRI 1009743, EPRI GS-7086, and API575 will be used as source documents to define tank testing and inspection requirements.(Reference 85)System Monitoring Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 8 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 42.FAC Acceptance Criterion NSR Pipe Wall - Entergy will revise the governing procedure forthe Flow Accelerated Corrosion Program to include the value of 87.5% of nominal wallthickness for non safety related piping as a trigger point to initiate engineering analysis toconfirm that remaining wall thickness is acceptable to support the intended function or todetermine corrective action, as applicable. (Reference 82)Flow AcceleratedCorrosion Program 43.Neutron Blackness Test of SFP Racks - Entergy will perform a neutron absorption("blackness") test of selected cells in the NUS spent fuel racks to validate that there is nosignificant degradation of the neutron absorption capability. If degradation is identified, anevaluation of the condition will be performed under the Entergy Corrective Action Program. Ifapplicable, this evaluation will determine the need for additional testing. (References 86 and 95)NA 44.Internal Inspections of Opportunity - Palisades procedures will be enhanced to inspect anddocument the internal condition of applicable components, in-scope for license renewal, whenmaintenance provides an opportunity. Applicable components are those that have an internalenvironment of water, are constructed of materials that are potentially susceptible to internalaging degradation in a wetted environment, but are not subject to another Aging ManagementProgram (e.g., Water Chemistry, Open Cycle Cooling) that would manage the internalenvironment such that aging degradation of the internal surfaces would not be expected.

(Reference 87)Inspections ofOpportunity for InternalSurfaces of SelectedComponents FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANTTABLE 1-9Revision 30Page 9 of 9LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANTText of Commitment, Due Date, SourceAffected Program 45.Corrosion Under Insulation - To verify that Corrosion Under Insulation (CUI) is not causingexcessive corrosion of insulated piping and components, inspections of opportunity will beperformed to assess the external surface condition when insulation is removed formaintenance or surveillance. The piping and components of interest are those within thescope of the System Monitoring Program, constructed of carbon or low alloy steel, with lownormal operating temperatures in an indoor or outdoor environment such that the piping couldbe wetted under its insulation (e.g., from condensation or rain water) for extended periodswithout being detected. The System Monitoring Program will be enhanced to require a periodicreview of documented under-insulation inspection results to verify that there were a sufficientnumber of inspection opportunities to provide a representative indication of system condition,and to assess the need for further action. If there were insufficient opportunities for inspection,insulation will be removed from additional sample locations to assess system condition underinsulation. (Reference 88)System Monitoring Program FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-10 Revision 32 Page 1 of 1 LISTING OF NEWLY IDENTIFIED SYSTEMS, STRUCTURES, AND COMPONENTS PER 10 CFR 54.37(b)

System Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Program ESS - Engineering Safeguards System 1 Heat Exchanger / Cooler Fluid Pressure Boundary Heat Transfer Stainless Steel Treated Water (internal) Loss of Material Heat Transfer Degradation - Fouling Closed Cycle Cooling Water Program ESS - Engineering Safeguards System 1 Heat Exchanger / Cooler Fluid Pressure Boundary Heat Transfer Stainless Steel Oil (external) Loss of Material Heat Transfer Degradation - Fouling Oil Sampling and Analysis Program FWS - Feedwater System 1 Heat Exchanger / Cooler Fluid Pressure Boundary Heat Transfer Stainless Steel Treated Water (internal) Loss of Material Heat Transfer Degradation - Fouling Water Chemistry Program FWS - Feedwater System 1 Heat Exchanger / Cooler Fluid Pressure Boundary Heat Transfer Stainless Steel Oil (external) Loss of Material Heat Transfer Degradation - Fouling Oil Sampling and Analysis Program FOS - Fuel Oil System 2 Accumulator Fluid Pressure Boundary Carbon Steel Atmosphere/ Weather (external) Loss of Material System Monitoring Program 110 CFR 50.37(b) Determination Log No. 54.37-PLP-2011-004.

210 CFR 50.37(b) Determination Log No. 54.37-PLP-2015-001.