ML23107A059

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6 to Updated Final Safety Analysis Report, Chapter 1, Tables
ML23107A059
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/31/2023
From:
Holtec Decommissioning International
To:
Office of Nuclear Reactor Regulation
Shared Package
ML23107A065 List: ... further results
References
HDI PNP 2023-002
Download: ML23107A059 (1)
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DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-1 Revision 36 Page 1 of 4 CHRONOLOGICAL LICENSING EVENTS Date Docket 50-255 FSAR Operating License Other CPOL Application June 2, 1966 CP Co Files CPOL PSAR Included With Application Application March 14, 1967 AEC Issues CPPR-25 November 1, 1968 CP Co Files Amendment 9 FSAR, Rev 0, Included Initial Operating License to CPOL Application 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 Full Revision to FSAR (Denoted CP Co Application for Full-Term 28 to CPOL as Amendment 28) Operating License at 2,638 MWt Core

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-1 Revision 36 Page 2 of 4 CHRONOLOGICAL LICENSING EVENTS 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

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-1 Revision 36 Page 3 of 4 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.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-1 Revision 36 Page 4 of 4 CHRONOLOGICAL LICENSING EVENTS December 13, 2021 On December 13, 2021, the NRC approved transfer of ownership of the Palisades facility the Palisades Entergy Nuclear Palisades, LLC, to Holtec Palisades, LLC (Holtec Palisades) and the transfer of operating authority of the Palisades facility to Holtec Decommissioning International, LLC (HDI).

May 13, 2022 On May 13, 2022, the NRC issued Amendment 272 to the Palisades Renewed Facility Operating License to reflect the permanent cessation of operations at PNP and permanent removal of fuel from the PNP reactor vessel.

June 13, 2022 On June 13, 2022, the licensee certified to the NRC that the Palisades Nuclear Plant had both permanently ceased operations (final shutdown May 20, 2022) and that all fuel had been removed from the reactor vessel and placed in the spent fuel pool.

June 28, 2022 June 28, 2022, the NRC issued Amendment 273 to the Palisades Renewed Facility Operating License to reflect the transfer of ownership/operation to Holtec Palisades and HDI, respectively.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 1 of 10 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Nuclear Steam Supply System Design Pressure 2,500 psia Pipe Size: Outlet (ID) 42" (Wall Thickness) 4" Inlet (ID) 30" (Wall Thickness) 3" Number of Loops 2 Number of Pumps 4 Type Vertical, Centrifugal, Mechanical Seals Design Flow/Pump 83,000 gpm Design Head 260' Core Number of Fuel Rods/Bundle 216 typical Fuel Rod Pitch 0.550" Fuel Clad Material Zircaloy-4 or M5 Control Rod Pitch 16.97" Absorber Material Silver-Indium-Cadmium Control Rod Drive Type Rack and Pinion

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 2 of 10 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

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 3 of 10 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Primary Side Tube Side Design Pressure 2,500 psia Tube Side Design Temperature 650°F Bottom Head Clad Material SS-304 Secondary Side Shell Side Design Pressure 1,000 psia Shell Side Design Temperature 550°F Turbine Cycle Turbine Design Tandem-Compound, 1 HP, 2 LP Turbines 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'

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 4 of 10 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

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

1. Chemical and Volume Control System Charging Pumps - Number 2 - Fixed Capacity 1 - Variable Capacity Design Flow 40 gpm Design Head 6,375' 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 106 Btu/h Letdown Heat Exchanger - Number 1 - Full Capacity Design Heat Transfer 19.1 x 106 Btu/h Demineralizers - Number 2 - Purification 1 - Deborating Nominal Rating 40 gpm Resin Type H-OH Resin Volume 32 ft3 Filter - Number 2

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 5 of 10 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Type Cartridge Design Rating 120 gpm Filter Size 2 Microns

2. Safety Injection System Safety Injection Tanks - Number 4 Volume - Total 2,000 ft3 Design Pressure 250 psia 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 106 (DBA)

Rating (Safety Related Cooler) 1.98 x 106 Btu/h (Normal)*

(Non-safety Related Cooler) 1.98 x 106 Btu/h (Normal)*

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

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 6 of 10 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 106 @ 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

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 7 of 10 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Heat Exchangers - Number 2 - Half Capacity Rating, Each 80.0 x 106 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 106 Btu/h (Normal)

Rating, Each 85.0 x 106 Btu/h (Post-DBA)

9. Spent Fuel Cooling System Spent Fuel Pool Capacity 4 Cores Volume of Empty SFP Cavity 21,885 ft3 Fuel Assemblies 892 Pumps - Number 2 - Half Capacity Rating, Each 1,700 gpm Head 64' Heat Exchanger - Number 2 Combined Rating 23 x 106 Btu/h Filter - Number 1 Type Cartridge Rating 150 gpm Size 25 Microns

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 8 of 10 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Demineralizer - Number 1 Resin Type H-OH Bed Size 68 ft3 Nominal Flow 150 gpm

10. Shield Cooling System Pumps - Number 2 - Full Capacity Rating, Each 154 gpm Head 79' Heat Exchanger - Number 1 - Full Capacity Rating 2 x 105 Btu/h Sets of Cooling Coils - Number 2 - Full Capacity Conventional Facility 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

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 9 of 10 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 106 ft3 Electrical Equipment Main Transformer - Rating 875 MVA Voltage 345 kV Diesel Generators - Number 2 - Full Capacity Rating 3,000 kVA Station Battery - Number 2 Type Lead Calcium Number of Cells 59 Rating 125 V, 1,800 Ah

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-2 Revision 36 Page 10 of 10 PALISADES DESIGN CHARACTERISTICS (NOMINAL VALUES)

Chargers - Number 4 Inverters - Number 4 AC/DC Voltage 120/125 Rating 6 kVA

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-3 Revision 36 Page 1 of 7 SYSTEMATIC EVALUATION PROGRAM (SEP) AND INTEGRATED ASSESSMENT PROGRAM (IAP)

PALISADES PLANT - NUREG-0820 Topic Title Status(a) IAP Disposition and Location Where Used in FSAR Update II-1.A Exclusion Area Authority and Control 4/N (Evaluation acceptable.) Section 2.1.

II-1.B Population Distribution S Section 2.1.2.

II-1.C Potential Hazards or Changes in Potential Hazards Due to S Sections 2.1.3 and 5.5.4.

Transportation, Institutional, Industrial and Military Facilities II-2.A Severe Weather Phenomena S Sections 8.7.1, 8.7.2 and 8.7.3.

II-2.C Atmospheric Transport and Diffusion Characteristics for S Section 2.5.

Accident Analysis II-3.A Hydrologic Description S Section 2.2.

II-3.B Flooding Potential and Protection Requirements 3/C (CP Co seiche evaluation established maximum flood level of 593.5 MSL accepted by staff October 7, 1982.)

Sections 2.2.2 and 5.4.1.

II-3.B.1 Capability of Operating Plant To Cope With Design-Basis 3/C (Same as II-3.B.) Section 5.4.1.

Flooding Conditions II-3.C Safety-Related Water Supply (Ultimate Heat Sink (UHS)) 3/C (Same as II-3.B.) Sections 5.4.1 and 9.1.

II-4 Geology and Seismology S Sections 2.3 and 2.4.

II-4.A Tectonic Province S Section 2.3.

II-4.B Proximity of Capable Tectonic Structures in Plant Vicinity S Section 2.4.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-3 Revision 36 Page 2 of 7 SYSTEMATIC EVALUATION PROGRAM (SEP) AND INTEGRATED ASSESSMENT PROGRAM (IAP)

PALISADES PLANT - NUREG-0820 Topic Title Status(a) IAP Disposition and Location Where Used in FSAR Update II-4.C Historical Seismicity Within 200 Miles of Plant S Section 2.4.

II-4.D Stability of Slopes S Section 2.4.

II-4.F Settlement of Foundations and Buried Equipment S Section 2.3.5.

III-1 Classification of Structures, Components and Systems (Seismic 3/C (Additional information supplied on radiography fracture and Quality) toughness, valves, pumps and storage tanks accepted by staff June 27, 1983.) Sections 5.1.5 and 11.2.1; and Tables 5.2-1, 5.2-2 and 5.2-3.

III-2 Wind and Tornado Loadings

- SIRW and Condensate Storage Tank 2/C (New EOPs were issued in December 1986.) Sections 5.3.2 and 5.3.3.

- Emergency Generators Supply and Exhaust Piping 4/N (Loss of both diesel generators and offsite power could present safe shutdown problems, however, the probability of both generators being disabled, precludes any back-fitting requirements.) Sections 5.3.2 and 5.3.3.

- Spent Fuel Pool Enclosure 4/N (The ability of the Plant to shut down is not affected by the inability of the steel enclosure to withstand tornado loadings, precluding any backfit requirements.) Sections 5.3.2 and 5.3.3.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-3 Revision 36 Page 3 of 7 SYSTEMATIC EVALUATION PROGRAM (SEP) AND INTEGRATED ASSESSMENT PROGRAM (IAP)

PALISADES PLANT - NUREG-0820 Topic Title Status(a) IAP Disposition and Location Where Used in FSAR Update III-4.A Tornado Missiles

- SIRW and Condensate Storage Tanks 2/C (New EOPs were issued in December 1986.) Sections 5.3.3 and 5.5.1.

- Emergency Diesel Supply and Exhaust Piping 4/N (Same as III-2.) Sections 5.3.3 and 5.5.1.

- Atmospheric Relief Stacks of Steam Relief Valves 4/N (Same as III-2.) Sections 5.3.3 and 5.5.1.

- Compressed Air System 4/N (Same as III-2.) Sections 5.3.3, 5.5.1 and 9.5.2.1.

III-4.B Turbine Missiles S Section 5.5.2.

III-4.D Site-Proximity Missiles (Including Aircraft) S Section 5.5.4.

III-5.B Pipe Break Outside Containment S Section 5.6.1.

III-6 Seismic Design Considerations

- Small Piping 3/C Supplemental SER issued July 12, 1991 and CPCo Letter dated April 8, 1992

- Electrical Components 3/C Resolved under SQUG Outlier process (Sections 5.7.1.3 and 5.7.7)

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-3 Revision 36 Page 4 of 7 SYSTEMATIC EVALUATION PROGRAM (SEP) AND INTEGRATED ASSESSMENT PROGRAM (IAP)

PALISADES PLANT - NUREG-0820 Topic Title Status(a) IAP Disposition and Location Where Used in FSAR Update III-8.A Loose-Parts Monitoring and Core Barrel Vibration Monitoring 3/C (A program of "Reactor Internals Vibration Monitoring" was instituted by Technical Specification 4.13 to monitor the adequacy of modifications to the core barrel clamping features made in 1974.) This Technical Specifications Program was discontinued in 1985 with NRC issuance of Technical Specifications Amendment No. 91 and SER dated 9/5/85. The SER dated 9/5/85 required an alternate non-Technical Specifications Monitoring Program as recommended by ASME Standard OM-05, 1981. CPCo committed to this program in a letter dated 3/29/85.

III-8.C Irradiation Damage, Use of Sensitized Stainless Steel and S -

Fatigue Resistance III-10.A Thermal-Overload Protection for Motors of Motor-Operated S Chapter 8.

Valves III-10.B Pump Flywheel Integrity S Section 4.3.5.

IV-1.A Operation With Less Than All Loops in Service S Section 7.2.3.3.

V-7 Reactor Coolant Pump Overspeed S Section 4.3.5.

V-10.A Residual Heat Removal System Heat Exchanger Tube Failures S Section 6.1.

V-10.B Residual Heat Removal System Reliability

- Overpressurization Protection (OPS) 2/C (Technical Specifications Amendment submitted on July 29, 1982 which would place OPS in service before shutdown cooling.) Section 7.4.2.

- Safety Grade Systems for Safe Shutdown 2/C (New EOPs were issued in December 1986.)

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-3 Revision 36 Page 5 of 7 SYSTEMATIC EVALUATION PROGRAM (SEP) AND INTEGRATED ASSESSMENT PROGRAM (IAP)

PALISADES PLANT - NUREG-0820 Topic Title Status(a) IAP Disposition and Location Where Used in FSAR Update V-11.A Requirements for Isolation of High- and Low-Pressure Systems 2/C (Technical Specifications Amendment submitted on July 29, 1982 which requires verification of LPSI check valve clo-sure before criticality after use of system.)

Sections 6.1.3 and 7.4.2.

V-11.B Residual Heat Removal System Interlock Requirements S Chapters 6 and 7.

VI-1 Organic Materials and Post-Accident Chemistry S -

VI-4 Containment Isolation System

- Manual Isolation Valve 1/C (Manual isolation valve on Penetration 44 was replaced with CV-2099 by Facility Change FC-563.)

- Threaded Pipe Connection 1/C (Modification of Penetration 19 threaded pipe connection was corrected by SC-83-013 and SC-83-162.)

- Containment Isolation Systems 1/C (Modifications of Penetrations 13, 17, 17a, 21, 21a, 28, 29, 48 and 73 have been completed.)

VI-7.D Long-Term Cooling Passive Failures (eg, Flooding of Redundant S Sections 5.4 and 9.1.3.

Components)

VI-7.F Accumulator Isolation Valves Power and Control System Design S Chapters 7 and 8.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-3 Revision 36 Page 6 of 7 SYSTEMATIC EVALUATION PROGRAM (SEP) AND INTEGRATED ASSESSMENT PROGRAM (IAP)

PALISADES PLANT - NUREG-0820 Topic Title Status(a) IAP Disposition and Location Where Used in FSAR Update VII-3 Systems Required for Safe Shutdown - Sections 7.2.3, 7.2.7, 7.2.9, 7.3.1, 7.4.1, 7.4.2, 7.6.2, 8.1.1, 8.1.2, 8.1.3, 8.4.1, 8.4.2, and 9.6.3.

- Removal of Nonessential Loads as an Alternative to 2/C (Procedure to remove nonessential loads from battery if 10 CFR 50, Appendix A, GDC 17 the immediate sources of offsite and onsite power are not available. Completed, see CP Co letter of 9/26/84.)

- Component Cooling Water Surge Tank Level 1/C (Installation of another level sensor to the component cooling water surge tank and control room indication completed.)

- Boric Acid Heat Tracing 4/C (The PRA study found that the boric acid system is a low contributor to risk and the impact of this issue on reactivity control is low, no backfit required.)

- Pressure Sensor on CCW Pumps 4/C (Because of redundancy in system failure indication, the PRA study concluded this issue has a small impact on availability, no backfit required.)

- Adequate Seismic Category I Water Supply for AFW 2/C (Same as III-2.)

VII-6 Frequency Decay S Section 14.7 and Chapter 8.

VIII-4 Electrical Penetrations of Reactor Containment 4/C (Evaluation acceptable based on similar SEP plants, modification unnecessary.) Section 8.5.1.

IX-1 Fuel Storage S Sections 9.4 and 9.11.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-3 Revision 36 Page 7 of 7 SYSTEMATIC EVALUATION PROGRAM (SEP) AND INTEGRATED ASSESSMENT PROGRAM (IAP)

PALISADES PLANT - NUREG-0820 Topic Title Status(a) IAP Disposition and Location Where Used in FSAR Update IX-5 Ventilation Systems

- AFW Pump Room 2/C (AFW pumps qualified for 160(F service.) Section 9.8.

- Cable Spreading, Switchgear and Battery Rooms 2/C (Ventilation fans for additional cooling to inverter cabi-nets, charger cabinets and auxiliary feedwater junction boxes completed during 1983/84 outage.) Sections 8.7.2, 8.7.3 and 9.8.

IX-6 Fire Protection 3/C (11/7/83 NRC letter. FP will be reviewed generically outside the context of SEP.) Sections 7.4.1, 7.4.2, 7.6.2, 7.7.3, 7.7.4, 7.7.8, 8.3.5, 8.5.3, 8.7.2, 8.8, and 9.6.3.

XIII-2 Safeguards/Industrial Security S -

XVII Operational Quality Assurance Program S -

(a) Staff Position Code___________________ Status Code S - Reviewed and accepted during SEP (N) - No action required 1 - Evaluated during integrated assessment, modification required (C) - Action required complete and item resolved 2 - Evaluated during integrated assessment, procedure development or Technical Specifications Change required 3 - Evaluated during integrated assessment, refined engineering analysis or continuation of ongoing analysis required 4 - Evaluated during integrated assessment; no further work required

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-5 Revision 36 Page 1 of 1 UNRESOLVED SAFETY ISSUES Task Reference No Title FSAR Chapter(s)

A-1 Water Hammer 4 and 9 A-2 Asymmetric Blowdown Loads on the Primary Coolant System 6 A-4 Pressurized Water Reactor Steam Generator Tube Integrity 4 A-11 Reactor Vessel Materials Toughness 4 A-12 Fracture Toughness of Steam Generators and Primary -(a)

Coolant Pump Supports A-17 Systems Interactions in Nuclear Power Plants -(a)

A-24 Environmental Qualification of Safety-Related 8 Electrical Equipment (EEQ)

A-26 Reactor Vessel Pressure Transient Protection 4 A-31 Residual Heat Removal Requirements 7 and 9 A-36 Control of Heavy Loads Near Spent Fuel 9 A-40 Seismic Design Criteria Short-Term Program 5 A-43 Containment Emergency Sump Reliability 6 A-45 Shutdown Decay Heat Removal Requirements 6 and 9 A-46 Seismic Qualification of Equipment in Operating Plants 5 A-47 Safety Implications of Control System 8 A-48 Hydrogen Control Measures and Effects of Hydrogen 6 Burns on Safety Equipment A-49 Pressurized Thermal Shock 3 and 4 (a) Not specifically addressed in FSAR.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-6 Revision 36 Page 1 of 1 ESTIMATED USE ON MARCH 24, 2031 RPV Material Material Cu (%) Initial USE 1/4t Neutron USE (ft-lbs)

Heat # (ft-lbs) Fluence (1019 n/cm2) 2-112A/C* W5214 0.213 118 1.275 64.9 W5214 0.213 118 1.275 64.9 3-112A/C*

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 materials (Reference 104)
      • CVGraph Method
        • 95% Shear Method

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-7 Revision 36 Page 1 of 1 RTMAX-X Values for Reactor Vessel at 42.1 Effective Full Power Years Lower and Intermediate Upper Shell Region Shell Region (10.5 inches < Twall (Twall 9.5 inches)(1) 11.5 inches)(1)

Reactor 10 CFR Reactor 10 CFR Vessel 50.61a Vessel 50.61a Screening Screening Criteria 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 - 436.4 538 285.0 445 RT MAX-AW + RT MAX-PL (°F)

Circumferential Weld - 247.6 312 149.8 269 RT MAX-CW (°F)

Note:

(1) TWALL is the reactor vessel thickness including the cladding.

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-8 Revision 36 Page 1 of 1

SUMMARY

OF FATIGUE USAGE FACTORS AT NUREG/CR-6260 SAMPLE LOCATIONS APPLICABLE TO PALISADES Location Material 60 Year Fen Environmental CUF CUF RPV Lower Head to SA-533 Grade B 0.004 2.50 0.009 Shell Juncture Class 1 RPV Inlet Nozzle SA-302 Grade B 0.104 2.50 0.260 RPV Outlet Nozzle SA-508 Class 2 0.181 2.50 0.454 Charging Nozzle SB-166 Alloy 600 0.306 1.49 0.456 Stainless Steel 0.006 15.35 0.092 Surge Line Elbow SA-376 Type 316 0.015 15.35 0.238 Safety Injection Nozzle SA-516 Grade 70 0.036 1.76 0.064 Shutdown Cooling Line SA-516 Grade 70 0.0097 1.76 0.017 Inlet Transition Values from Reference 96, Attachment 5.4

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-9 Revision 36 Page 1 of 7 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

1. Deleted Deleted
2. Deleted Deleted
3. Deleted Deleted
4. Deleted Deleted
5. Deleted Deleted
6. Update Alloy 600 Program - HDI will revise the Alloy 600 Program to update the PWSCC Alloy 600 Inspection corrosion rate assessments and inspection program consistent with the latest NRC Program requirements and industry commitments (e.g., EPRI Report 1010087 Materials Reliability Program: Primary System Piping System Butt Weld Inspection and Evaluation Guidelines

[MRP-139], (August 2005)). (Reference 57)

7. Commitment deleted (Reference 94). Deleted.
8. Deleted Deleted
9. Expand Quality Program to NSR SSC - The Quality Program implementation procedures will Quality be expanded to apply the elements of corrective action, confirmation process, and administrative controls to both safety related and non-safety related systems, structures, and components that are subject to aging management review for license renewal. (Reference 57)
10. Update Bolting Program Standards - Review and revise ASME ISI Master Plan, procedures Bolting Integrity Program that implement credited License Renewal Programs, and plant maintenance procedures to reflect and reference the applicable guidance provided in NUREG-1339 and EPRI TR-104213 for safety and non-safety related bolting. These revisions should also include instructions for selection of bolting material and use of lubricants and sealants, in accordance with the guidelines of EPRI NP-5769 and the additional recommendations of NUREG-1339 to prevent or mitigate degradation and failure of safety-related bolting. (Reference 57)
11. Define Insp Reqts High Strength Bolts - Evaluate the high strength bolting used for Bolting Integrity Program

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-9 Revision 36 Page 2 of 7 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program component supports for susceptibility to cracking as described in NUREG-1801,Section XI.M.18, "Parameters Monitored/Inspected," and implement appropriate inspection requirements to provide adequate age-management for these bolts (Reference 57).

12. Define Boric Acid Insp Walkdown Criteria - Revise applicable plant procedures to include Boric Acid Corrosion criteria for observing susceptible SSC, within the scope of license renewal, for boric acid Program leakage and degradation, during system walkdown inspections. (Reference 57)
13. Boric Acid Insp Criteria - Revise applicable plant procedure(s) to include explicit acceptance Boric Acid Corrosion criteria for boric acid inspections. (Reference 57) Program
14. Boric Acid Insp of Struct & NonASME - Revise applicable plant procedures to include Boric Acid Corrosion inspection of structural steel and non-ASME component supports for evidence of boric acid Program residue and boric acid wastage/corrosion on a periodic frequency. (Reference 57)
15. Implement Buried Services Monitoring Program - A Buried Services Corrosion Monitoring Buried Services Program will be developed and implemented. Features of the program will include Corrosion Monitoring development and implementation of procedures for inspection of selected buried SSCs for Program corrosion, pitting and MIC. The periodicity of these inspections will be based on opportunities for inspection such as scheduled excavation and maintenance work. (Reference 57)
16. Periodic Clean Inspect FO Storage Tank - Develop and implement procedures for periodic Diesel Fuel Monitoring draining and cleaning of diesel fuel oil storage tanks, Emergency Diesel Generator day tanks, and Storage Program and Diesel Fire Pump Day Tanks. These procedures shall include steps to perform a visual inspection of interior tank surfaces for signs of degradation or corrosion, with acceptance criteria, corrective actions, and documentation of inspection results. (Reference 57)
17. Periodic Drain Water from Fuel Oil Tanks - Develop and implement procedures for periodic Diesel Fuel Monitoring draining of water accumulated in the bottom of the fuel oil storage tanks and fuel oil day tanks and Storage Program for the Diesel Generators and Diesel Fire Pumps. (Reference 57)
18. Fuel Oil Tank Bottom Thickness Measurements - Develop and implement procedures for Diesel Fuel Monitoring

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-9 Revision 36 Page 3 of 7 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program periodic ultrasonic measurement of thickness of the bottom of Fuel Oil Storage Tanks, and Storage Program Emergency Diesel Generator Day Tanks, and Diesel Fire Pump Day Tanks. (Reference 57)

19. Structural Monitoring Program for Fire Barriers - The Structures Monitoring Program shall Structures Monitoring be revised to include specific inspection criteria and documentation requirements for verifying Program that walls, ceilings and floors that serve as Fire Protection Program fire barriers are verified to be free from aging related degradation that would impact the fire barrier's intended function.

(Reference 57)

20. Fire Door Inspection - Plant procedures shall be revised to more specifically address aging Fire Protection Program related degradation and expectations for documentation of fire door condition. (Reference 57)
21. Fire Door Clearance Inspections - Develop and implement procedures to perform visual Fire Protection Program inspections for fire door clearances. (Reference 57)
22. Diesel Fire Pump Fuel Line Inspection - Revise diesel-driven fire pump performance test Fire Protection Program procedures to more specifically address requirement to inspect and monitor fuel oil supply line for aging related degradation, and to document inspection results.
23. Inspect Below Grade Fire Piping - Develop and implement procedures for inspection of Fire Protection Program below grade fire protection system piping. Inspections shall be implemented under the Buried / Buried Services Services Corrosion Monitoring Program. In addition, results of wall thickness inspections of Program above grade fire protection system piping shall be extrapolated to evaluate the wall thickness condition of below grade fire protection system piping. Procedures shall include acceptance criteria, and criteria for further corrective actions if acceptance criteria are not met. (Reference 94)
24. Fire Hydrant Inspection & Testing - Plant procedures shall be revised to more specifically Fire Protection Program address identification of aging related degradation and expectations for documentation of fire hydrant condition. Also, these revisions shall include provisions to perform flow testing for fire hydrants within the scope of License Renewal that are credited for fire suppression in the Palisades current licensing basis. (Reference 57)

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-9 Revision 36 Page 4 of 7 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

25. Replace or Test Sprinkler Heads - Develop and implement procedures to replace all sprinkler Fire Protection Program heads prior to the end of the 50 year service life, or for testing of a representative sample of sprinkler 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)
26. Non-EQ Commodities Condition Monitoring - A Non-EQ Electrical Commodities Condition Non-EQ Electrical Monitoring Program will be developed and implemented. Features of the program will include Commodity Condition development and implementation of procedures to conduct periodic inspection of insulated Monitoring Program cables and connectors, test sensitive instrumentation circuits, test medium voltage cables, inspect manhole water levels, and inspect non-segregated phase bus and connections.

(Reference 94)

27. One Time Inspection Program - A One Time Inspection Program will be developed and One-Time Inspection implemented. Features of the program are as described in the Enhancement section of LRA Program Section B2.1.13. (Reference 57)
28. Crane Inspection Requirements - Revise crane and fuel handling machine inspection Overhead Load procedures to specifically inspect for general corrosion on passive components making up the Handling Systems bridge, trolley, girders, etc., and to inspect rails of Bridge Cranes for wear. Revision should also Inspection Program include documentation of results of these inspections, acceptance criteria, and qualification requirements for inspectors and crane supervisors. (Reference 57)
29. Deleted Deleted
30. Deleted Deleted
31. Deleted Deleted
32. Deleted Deleted
33. Deleted Deleted

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-9 Revision 36 Page 5 of 7 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

34. Withdrawn -
35. Incorporate Members in Structural Monitoring Program - Incorporate into the Structural Structures Monitoring Monitoring Program all structural members listed in Tables 3.5.2-1 through 3.5.2-10 that will Program use the Structural Monitoring Program as an AMR. (Reference 57)
36. Enhance System Walkdown Procedures - Enhance system walkdown procedures to more System Monitoring specifically address the types of components to be inspected, and to specifically describe the Program relevant degradation mechanisms and effects of interest, and for use of the Corrective Action Program to document aging related degradation, identified during the inspections, that may affect the ability of the SSC to perform its intended function. (Reference 57)
37. Fatigue Monitoring Program - A Fatigue Monitoring Program will be developed and Fatigue Monitoring implemented. Features of the program will include monitoring and tracking selected cyclic Program loading transients (cycle counting) and their effects on critical reactor pressure boundary components and other selected components. (Reference 57)
38. Incorporate Commitments into FSAR - The final text and schedule of licensee commitments NA that are confirmed by NRC in the final SER for the Palisades Renewed Operating License will be incorporated into appropriate locations of the FSAR in the first regular FSAR update under 10 CFR 50.71 (e) following NRC issuance of the renewed operating license. (Reference 83)
39. Buried Piping Opportunistic Inspection - Visual inspections of a sample of buried carbon, Buried Services low-alloy, and stainless steel components will be performed within ten years prior to entering, Corrosion Monitoring and within ten years after entering, the period of extended operation. Prior to the tenth year of Program each period, HDI will perform an evaluation of available data to determine if sufficient opportunistic inspections have been performed within that period to assess the condition of the components. If insufficient data exists, focused inspection(s) will be performed as needed.

(Reference 84)

40. HVAC Flex Joint PM Enhancement - HDI will enhance the preventive maintenance program NA to periodically inspect, and replace as necessary, the expansion joints/flexible connections in

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-9 Revision 36 Page 6 of 7 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program the portions of the Heating, Ventilation and Air Conditioning System that are in-scope for license renewal. (Reference 94)

41. Industry Standard Use for Tank Inspection - HDI will identify specific methods of inspection System Monitoring for individual components as part of the System Monitoring Program implementation procedure Program development. Industry documents such as EPRI 1009743, EPRI GS-7086, and API 575 will be used as source documents to define tank testing and inspection requirements. (Reference 85)
42. FAC Acceptance Criterion NSR Pipe Wall - HDI will revise the governing procedure for the Flow Accelerated Flow Accelerated Corrosion Program to include the value of 87.5% of nominal wall thickness Corrosion Program for non safety related piping as a trigger point to initiate engineering analysis to confirm that remaining wall thickness is acceptable to support the intended function or to determine corrective action, as applicable. (Reference 82)
43. Neutron Blackness Test of SFP Racks - HDI will perform a neutron absorption ("blackness") NA test of selected cells in the NUS spent fuel racks to validate that there is no significant degradation of the neutron absorption capability. If degradation is identified, an evaluation of the condition will be performed under the HDI Corrective Action Program. If applicable, this evaluation will determine the need for additional testing. (References 86 and 95)
44. Internal Inspections of Opportunity - Palisades procedures will be enhanced to inspect and Inspections of document the internal condition of applicable components, in-scope for license renewal, when Opportunity for Internal maintenance provides an opportunity. Applicable components are those that have an internal Surfaces of Selected environment of water, are constructed of materials that are potentially susceptible to internal Components aging degradation in a wetted environment, but are not subject to another Aging Management Program (e.g., Water Chemistry, Open Cycle Cooling) that would manage the internal environment such that aging degradation of the internal surfaces would not be expected.

(Reference 87)

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-9 Revision 36 Page 7 of 7 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

45. Corrosion Under Insulation - To verify that Corrosion Under Insulation (CUI) is not causing System Monitoring excessive corrosion of insulated piping and components, inspections of opportunity will be Program performed to assess the external surface condition when insulation is removed for maintenance or surveillance. The piping and components of interest are those within the scope of the System Monitoring Program, constructed of carbon or low alloy steel, with low normal operating temperatures in an indoor or outdoor environment such that the piping could be wetted under its insulation (e.g., from condensation or rain water) for extended periods without being detected. The System Monitoring Program will be enhanced to require a periodic review of documented under-insulation inspection results to verify that there were a sufficient number 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 under insulation. (Reference 88)

DSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF FACILITY TABLE 1-10 Revision 36 Page 1 of 1 LISTING OF NEWLY IDENTIFIED SYSTEMS, STRUCTURES, AND COMPONENTS PER 10 CFR 54.37(b)

System Component Type Intended Material Environment Aging Effect Aging Management Function(s) Requiring Program Management ESS - Engineering Safeguards Loss of Material Fluid Pressure System1 Treated Water Boundary Closed Cycle Cooling Heat Exchanger / Cooler Stainless Steel (internal) Heat Transfer Water Program Degradation -

Heat Transfer Fouling ESS - Engineering Safeguards Loss of Material Fluid Pressure System1 Oil (external)

Boundary Oil Sampling and Heat Exchanger / Cooler Stainless Steel Heat Transfer Analysis Program Degradation -

Heat Transfer Fouling FWS - Feedwater System1 Loss of Material Fluid Pressure Boundary Treated Water Water Chemistry Heat Exchanger / Cooler Stainless Steel (internal) Heat Transfer Program Degradation -

Heat Transfer Fouling FWS - Feedwater System1 Loss of Material Fluid Pressure Boundary Oil (external) Oil Sampling and Heat Exchanger / Cooler Stainless Steel Heat Transfer Analysis Program Degradation -

Heat Transfer Fouling Atmosphere/

FOS - Fuel Oil System2 Fluid Pressure Loss of Material System Monitoring Accumulator Carbon Steel Weather Boundary Program (external) 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.

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