ML21125A330

From kanterella
Jump to navigation Jump to search
5 to Updated Final Safety Analysis Report, Chapter 1, Tables
ML21125A330
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/14/2021
From:
Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21125A344 List: ... further results
References
PNP 2021-008
Download: ML21125A330 (49)
v • d • e


Text

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-1 Revision 28 Page 1 of 3 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

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-1 Revision 28 Page 2 of 3 CHRONOLOGICAL LICENSING EVENTS Date Docket 50-255 FSAR Operating License Other CPOL Application 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 34 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 106 lb/h original 72.3 x 106 lb/h present nominal Number of Loops 2

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 34 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 34 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 34 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 (106 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 34 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 34 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 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 Maximum Flow 160 gpm Resin Type H-OH Resin Volume 32 ft3 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 ft3 Borated Water 1,000 ft3 Nitrogen @ 200 psia 1,000 ft3 Design Pressure 250 psia

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 34 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 106 (DBA)

Cooling Water Flow, Each Set per FSAR Sect 9.1.2.3 (DBA)

Airflow 30,000 ft3/min (DBA)

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

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

Cooling Water Flow, Each 500 gpm (Normal)

Airflow 60,000 ft3/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 34 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 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

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 34 Page 9 of 12 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

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-2 Revision 34 Page 10 of 12 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 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 34 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 106 ft3 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 34 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 1-3 Revision 25 Page 1 of 12 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.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 2 of 12 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.

III-3.A Effects of High Water Level on Structures S (The NRC concluded that the design approach used for Palisades CP Co Design Class 1 structures was adequate for resisting a design basis flood.) Sections 5.4.1 and 5.9.1.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 3 of 12 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-3.C Inservice Inspection of Water Control Structures

- Cooling Water System Structures Inspection 2/C (Inspection began in 1982) Section 9.12.

- Flood Protection Structures 4/N (Inspection part of Preventative Maintenance Program.)

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.C Internally Generated Missiles S Section 5.5.3.

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

III-5.A Effects of Pipe Break on Structures, Systems and Components 2/C (No modifications necessary. Reference CP Co letter of Inside Containment 5/31/85.) Section 5.6.

- Operability of Leakage Detection System 2/C (Technical Specifications change submitted by CP Co letter of 5/23/85.)

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

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 4 of 12 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-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)

III-7.A Inservice Inspection, Including Prestressed Concrete Containments With Either Grouted or Ungrouted Tendons

- Tendon Force Acceptance Criteria 3/C (Acceptance criteria developed for each tendon that varies with time. Reference CP Co 11/7/83 submittal.)

Sections 5.8.4.2 and 5.8.2.

- Inspect Tendon-End Anchorages 3/C (CP Co submitted Technical Specifications changes that specify when tendon-end anchorages will be inspected dur-ing ILRT. Reference 5/4/87 and 9/16/87 CP Co submittals.)

Sections 5.8.4.2 and 5.8.2.

III-7.B Design Codes, Design Criteria, Load Combinations and Reactor 3/C (Issue resolved. Reference CP Co letters of 6/28/84, Cavity Design Criteria 5/3/85 and 8/7/91.) Sections 5.8.3, 5.9.1 and 5.10.2; and Table 5.2-2.

III-7.C Delamination of Prestressed Concrete Containment Structures 3/C (One-time delamination inspection of containment dome completed.) Section 5.8.8.

III-7.D Containment Structural Integrity Tests S Section 5.8.8.4.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 5 of 12 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.

IV-2 Reactivity Control Systems Including Functional Design and S Section 7.4.1.

Protection Against Single Failures V-5 Reactor Coolant Pressure Boundary (RCPB) Leakage Detection 2/C (Technical Specifications for operability of leakage detection systems completed December 15, 1983.)

Section 4.7.

V-6 Reactor Vessel Integrity S Sections 4.3.3, 4.4.2 and 4.5.2.

V-7 Reactor Coolant Pump Overspeed S Section 4.3.5.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 6 of 12 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-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.)

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-2.D Mass and Energy Release for Postulated Pipe Break Inside 1/C (See PRA study submitted by CP Co letter of 5/23/85; NRC review dated 2/28/86.)

VI-3 Containment Pressure and Heat Removal Capability 1/C (Same as VI-2.D. NRC review dated 2/28/86.)

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.)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 7 of 12 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 VI-6 Containment Leak Testing 3/C (Technical Specifications Amendment submitted March 3, 1982 for verification of airlock door seal integrity following opening. Approved by Amendment 126 dated June 1, 1989.)

VI-7.A.3 Emergency Core Cooling System Actuation System S Sections 7.3.2, 7.3.5 and 8.1.1; and Appendix 7A.

VI-7.B Engineered Safety Feature Switchover From Injection to S Section 6.1.2.2.

Recirculation Mode (Automatic Emergency Core Cooling System Realignment)

VI-7.C Emergency Core Cooling System (ECCS) Single-Failure Criterion S Section 7.3.

and Requirements for Locking Out Power to Valves, Including Independence of Interlocks on ECCS Valves VI-7.C.1 Appendix K - Electrical Instrumentation and Control S Chapter 7, Sections 8.1.1 and 8.3.5.

Re-reviews VI-7.C.2 Failure Mode Analysis (Emergency Core Cooling System) S Section 7.2.3.10.

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.

VI-10.A Testing of Reactor Trip System and Engineered Safety 3/C (Requires response-time testing on a periodic basis.)

Features, Including Response-Time Testing Sections 7.3.2 and 7.3.5.

VII-1.A Isolation of Reactor Protection System From Nonsafety 1/C Section 7.2.9.

Systems, Including Qualification of Isolation Devices VII-1.B Trip Uncertainty and Setpoint Analysis Review of Operating S -

Data Base VII-2 Engineered Safety Features System Control Logic and Design S Chapter 6 and Section 7.3.1.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 8 of 12 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-1.A Potential Equipment Failures Associated With Degraded Grid S Sections 7.3.2.2 and 7.3.5.

Voltage VIII-2 Onsite Emergency Power Systems (Diesel Generator) S (Separate annunciator modification complete.) Section 8.4.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 9 of 12 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 VIII-3.A Station Battery Capacity Test Requirements 2/C (CP Co proposed an amendment to the Technical Specifica-tions to conduct battery test pursuant to NRC guidelines, see CP Co letter dated 5/13/85.) Section 8.4.2.

VIII-3.B DC Power System Bus Voltage Monitoring and Annunciation S (Installation of (1) 125 V dc tie breaker open (both buses), (2) public address system inverter loss of voltage and (3) battery undervoltage (both batteries) is complete.)

Sections 8.3.5 and 8.4.2.

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.

IX-3 Station Service and Cooling Water Systems

- 2.7.1 Cooling of CCW Heat Exchanger 2/C (Revision to EOP for FWS alignment acceptable and complete.)

- 2.7.2 Flooding of Intake Safety Systems 2/C Section 5.4.2.

IX-4 Boron Addition Systems (PWR) S Section 9.10.

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.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 10 of 12 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-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 -

XV-1 Decrease in Feedwater Temperature, Increase in Feedwater S Section 14.9, 14.10.

Flow, Increase in Steam Flow and Inadvertent Opening of a Steam Generator Relief or Safety Valve XV-2 Spectrum of Steam System Piping Failures Inside and Outside 3/C (See PRA study submitted by CP Co letter of 5/23/85, NRC Containment (PWR) review required. NRC review letter dated 2/28/86.)

Section 14.14.

- Failure of Main Feedwater Isolation 3/C (No modifications necessary, pending NRC review. NRC review letter dated 2/28/86.)

XV-3 Loss of External Load, Turbine Trip, Loss of Condenser S Section 14.12.

Vacuum, Closure of Main Steam Isolation Valve (BWR) and Steam Pressure Regulator Failure (Closed)

XV-4 Loss of Nonemergency AC Power to the Station Auxiliaries S Chapter 8.

XV-5 Loss of Normal Feedwater Flow S Section 14.13.

XV-6 Feedwater System Pipe Breaks Inside and Outside Containment S Section 5.6.

(PWR)

XV-7 Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump S Section 14.17.

Shaft Break

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 11 of 12 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 XV-8 Control Rod Misoperation (System Malfunction or Operator S Sections 14.2, 14.4, 14.6 and 14.16.

Error)

XV-9 Start-Up of an Inactive Loop or Recirculation Loop at an S Section 14.8.

Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control System Malfunction That Results S Section 14.3.

in a Decrease in Boron Concentration in the Reactor Coolant (PWR)

XV-12 Spectrum of Rod Ejection Accidents (PWR) 2/C (The staff found that radiological consequences of a rod ejection accident are acceptable and do not require any departure from existing analysis.)

XV-14 Inadvertent Operation of Emergency Core Cooling System and S -

Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a PWR Pressurizer Safety/Relief Valve S -

or a BWR Safety/Relief Valve XV-16 Radiological Consequences of Failure of Small Lines Carrying S Section 14.23.

Primary Coolant Outside Containment XV-17 Radiological Consequences of Steam Generator Tube Failure S Section 14.15.

(PWR)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-3 Revision 25 Page 12 of 12 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 XV-19 Loss-of-Coolant Accidents Resulting From Spectrum of S Section 14.17.

Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences of Fuel-Damaging Accidents (Inside S Sections 14.11 and 14.19.

and Outside Containment)

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 (b) - Action required in progress 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

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 1 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition I.A.1.1 Shift Technical Advisor 1. On duty 1 Additional training produced.

2. Technical 1 Additional training produced.

Specifications

3. Trained per LL Cat B 1 Additional training produced.
4. Describe long-term 1 Additional training produced.

program I.A.1.2 Shift Supervisor Delegate nonsafety duties 1 Defined Shift Supervisor's responsibilities.

Responsibilities I.A.1.3 Shift Manning 1. Limit overtime 1 Reviewed and revised procedures for shift manning.

2. Min shift crew 1 To be addressed when final rule is issued.

I.A.2.1 Immediate Upgrading of RO 1. SRO experience 1 Training and qualification procedures at Palisades Plant and SRO Training and have been modified to meet NRC criteria.

Qualifications 2. SROs be ROs in one year 1 Training and qualification procedures at Palisades Plant have been modified to meet NRC criteria.

3. Three-month training 1 Training and qualification procedures at Palisades Plant on shift have been modified to meet NRC criteria.
4. Modify training 1 Training and qualification procedures at Palisades Plant have been modified to meet NRC criteria.
5. Facility certification 1 Training and qualification procedures at Palisades Plant have been modified to meet NRC criteria.

I.A.2.3 Administration of Training Instructors complete SRO exam 1 Assure trainers are qualified at SRO qualifications level.

Programs (a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 2 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition I.A.3.1 Revise Scope and Criteria 1. Increase scope 1 Include simulator examinations with training.

for Licensing Exams 2. Increase passing grade 1 Include simulator examinations with training.

3. Simulator exams 1 Include simulator examinations with training.

I.C.1 Short-Term Accident and 1. SB LOCA 1 Complete per EOP upgrade.

Procedures Review 2. Inadequate Core Cooling 1 Complete per EOP upgrade.

a. Reanalyze and pro-pose guidelines
b. Revise procedures
3. Transients and accidents 1 Complete.
a. Reanalyze and pro-pose guidelines
b. Revise procedures I.C.2 Shift and Relief Turnover Implement shift turnover 1 Revised procedure for shift turnover.

Procedures checklist I.C.3 Shift Supervisor Clearly define supervisor 1 Defined Shift Supervisor's responsibilities.

Responsibility and operator responsibilities I.C.4 Control Room Access Establish authority; limit 1 Access controlled by Shift Supervisor or No 1 Control access Operator.

I.C.5 Feedback of Operating Licensee to implement 1 Assess operating experience and incorporate (if needed)

Experience procedures into operating procedures, training and retraining programs.

(a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 3 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition I.C.6 Verify Correct Performance Revise performance 1 Evaluate procedures and revise when appropriate.

of Operating Activities procedures I.D.1 Control Room Design 1. Assessment and schedule 1 Complete - SER issued 9/14/89. See Note 1.

Reviews for correcting deficiencies

2. Implementation of cor- 1 Continuing.

rective actions I.D.2 Plant Safety Parameter 1. Description 1 Complete - SER issued 6/29/87.

Display Console 2. Installed 1 Complete - SER issued 6/29/87.

- CPCo Certification letter 7/10/89

- NRC Closure letter 4/19/90

3. Fully implemented 1 Complete - SER issued 6/29/87.

- CPCo Certification letter 7/10/89

- NRC Closure letter 4/19/90 II.B.1 Reactor Coolant System 1. Design vents 1 Modification of gas venting system and revised procedures Vents accordingly.

2. Install vents 1 Modification of gas venting system and revised procedures (LL Cat B) accordingly.
3. Procedures 1 Modification of gas venting system and revised procedures accordingly.

(a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 4 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition II.B.2 Plant Shielding 1. Review designs 1 Modification completed of facility to provide access to vital areas under accident conditions.

2. Plant modifications 1 Modification completed of facility to provide access to (LL Cat B) vital areas under accident conditions.
3. Equipment qualification 1 Modification completed of facility to provide access to vital areas under accident conditions.

II.B.3 Deleted II.B.4 Training for Mitigating 1. Develop training program 1 Complete training program.

Core Damage 2. Implement program 1 Complete training program.

a. Initial
b. Complete II.D.1 Relief and Safety Valve 1. Submit program 1 Complete.

Test Requirements 2. RV and SV testing 1 Complete.

(LL Cat B)

a. Complete testing
b. Plant specific report
3. Block valve testing 1 Block valve requirement analysis complete, new block valves and PORVs installed during 1989 maintenance outage.

II.D.3 Valve Position Indication 1. Install direct indica- 1 Complete.

tions of valve position

2. Technical Specifications 1 Modification of valve indicators and Technical Specifica-tions changes as required (reference Amendment 67, 10/8/81).

(a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 5 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition II.E.1.1 Auxiliary Feedwater System 1. Short term 1 Auxiliary Feedwater Systems modified as required.

Evaluation 2. Long term 1 Auxiliary Feedwater Systems modified as required.

II.E.1.2 Auxiliary Feedwater System 1. Initiation 1 Modification of instrumentation to level of safety grade Initiation and Flow a. Control grade complete.

b. Safety grade
2. Flow indication 1 Modification of instrumentation to level of safety grade
a. Control grade complete.
b. LL A Technical Specifications
c. Safety grade II.E.3.1 Emergency Power for 1. Upgrade power supply 1 Modified system to provide emergency power.

Pressurizer Heaters 2. Technical Specifications 1 Modified system to provide emergency power.

II.E.4.1 Dedicated Hydrogen 1. Design 1 Not required for Palisades Plant.

Penetrations 2. Install 1 Not required for Palisades Plant.

II.E.4.2 Containment Isolation 1-4. Imp diverse isolation 1 Modified containment isolation circuitry.

Dependability 5. Containment pressure 1 Lower containment pressure set point to level compatible set point with normal operation.

a. Specify pressure
b. Modifications
6. Containment purge valves 1 Consumers Power Company has committed to use valves only during outages.
7. Radiation signal on 1 Isolate purge and vent valves on radiation signal.

purge valves

8. Technical Specifications 1 Isolate purge and vent valves on radiation signal.

(a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 6 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition II.F.1 Accident Monitoring 1. Noble gas monitor 1 Modifications made and included in Offsite Dose Calculation Manual (ODCM).

2. Iodine/particulate sampling 1 Modifications made and included in Offsite Dose Calculation Manual (ODCM).
3. Containment high-range monitor 1 Modifications made and included in Technical Specifications
4. Containment pressure 1 Modifications made and included in Technical Specifications
5. Containment water level 1 Modifications made and included in Technical Specifications
6. Containment hydrogen 1 Existing equipment meets the NRC's criteria.

II.F.2 Instrumentation for Detec- 1. Subcool meter 1 Instrumentation modified during 1988 refueling outage.

tion of Inadequate Core 2. Technical Specifications 1 Issued as Amendment 129.

Cooling (LL Cat A)

3. Install level instru- 1 Instrumentation modified during 1988 refueling outage.

ments (LL Cat B)

II.G.1 Power Supplies for Pres- 1. Upgrade to emergency 1 No action required.

surizer Relief Valves, sources Block Valves and Level 2. Technical Specifications 1 No action required.

Indicators II.K.1 IE Bulletins 79-05 1 See Bulletin for specific disposition, no further action required.

79-06 1 See Bulletin for specific disposition, no further action required.

79-08 1 See Bulletin for specific disposition, no further action required.

(a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 7 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition II.K.2 Orders on B&W Plants 13. Thermal mechanical 1 Analysis shows that vessel integrity will be maintained for report such an event.

17. Voiding in RCS 1 Existing equipment meets NRC requirements.
19. Bench mark analysis of 1 Not applicable to Palisades Plant.

seq AFW flow II.K.3 Final Recommendations, B&O 1. Auto PORV isolation 1 Not applicable to Palisades. Palisades operates with the Task Force a. Design PORVs isolated.

b. Test/install
2. Report on PORV failures 1 Complete.
3. Reporting SV and RV 1 RVs are isolated - are not challenged. SVs have never been failures and challenges challenged. Complete per CE Reports CEN-213 and -227.
5. Auto trip of RCPs 1 Complete Trip 2/leave 2 incorporated in EOPs.
a. Propose modifications
b. Modify
17. Emergency Core Cooling 1 No action required.

System outages

25. Power on pump seals 1 Item not applicable to Palisades Plant.
a. Propose modifications
b. Modifications
30. SB LOCA methods 1 CE-CEFLASH 4AS acceptable.
a. Schedule outline
b. Model
c. New analyses
31. Compliance with 1 Not required.

CFR 50.46

44. Evaluate transient with 1 Item not applicable to Palisades Plant.

single failure (a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-4 Revision 23 Page 8 of 8 POST-TMI REQUIREMENTS FOR CONSUMERS POWER COMPANY'S PALISADES PLANT - NUREG-0737 Item Number Title Description Status(a) Disposition III.A.1.1 Emergency Preparedness, Short-term improvements 1 Emergency Plan will be changed on an as-needed basis.

Short Term III.A.1.2 Upgrade Emergency Support 1. Interim TSC, OCS and EOF 1 Emergency support facilities have been constructed/modified Facilities to meet NRC criteria.

2. Design 1 Emergency support facilities have been constructed/modified to meet NRC criteria.
3. Modifications 1 Emergency support facilities have been constructed/modified to meet NRC criteria.

III.A.2 Emergency Preparedness 1. Upgrade emergency plans 1 Complete. Emergency Plan has been upgraded to meet to Appendix E, 10 CFR 50 Appendix E.

2. Meteorological data 1 Complete. Emergency Plan has been upgraded to meet Appendix E.

III.D.1.1 Primary Coolant Outside 1. Leak reduction 1 Leakage reduction program has been implemented.

Containment 2. Technical Specifications 1 Leakage reduction program has been implemented.

III.D.3.3 In-Plant Radiation 1. Provide means to deter- 1 Existing Plant equipment meets NRC requirements.

Monitoring mine presence of radioiodine

2. Modifications to 1 Existing Plant equipment meets NRC requirements.

accurately measure III.D.3.4 Control Room Habitability 1. Review 1 Control room HVAC was modified to satisfy NRC criteria.

2. Modification 1 Control room HVAC was modified to satisfy NRC criteria.

NOTE 1: See Supplement 1 to NUREG-0737 for details.

(a)Status Codes:

1 - Completed 2 - In Process

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-5 Revision 21 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-9 Anticipated Transients Without Scram (ATWS) 7 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-44 Station Blackout 8 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.

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 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

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 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.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-8 Revision 30 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

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 1 of 9 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

1. Each year, following the submittal of the Palisades License Renewal Application and at least NA three months before the scheduled completion of the NRC review, Entergy will submit an amendment to the application pursuant to 10 CFR 54.21 (b). This amendment will identify any changes to the Current Licensing Basis of the facility that materially affect the contents of the License Renewal Application, including the FSAR supplement, that have not already been submitted. (Reference 57)
2. Equivalent Margins Analysis - Entergy will submit an equivalent margins analysis, completed Reactor Vessel Integrity in accordance with 10 CFR 50 Appendix G Section IV.A.1, for NRC approval, at least three Surveillance Program years before any reactor vessel beltline material upper shelf energy decreases to less than 50 ft-lb. (Reference 57)
3. PTS Management - At the appropriate time, prior to exceeding the PTS screening criteria, Reactor Vessel Integrity Palisades will select the optimum alternative to manage PTS in accordance with NRC Surveillance Program regulations and make relevant submittals to obtain NRC review and approval. (Reference 57)
4. Charging Line Fatigue - Entergy will evaluate the effect the increase in variable speed Fatigue Monitoring charging pump out-of-service events may have on these lines (Charging Lines Inboard of the Program Regenerative Heat Exchanger), and will take actions necessary to ensure these lines meet licensing basis design criteria for the extended operating period. Entergy will complete this evaluation 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)
5. Fatigue Monitoring of PZR TEs - Entergy will monitor the cumulative number of pressurizer Fatigue Monitoring temperature element nozzle fatigue cycles within the Fatigue Monitoring Program, and Program maintain a special action level to ensure that appropriate actions are taken if at any time the cycle count for any design basis event since 1993 reaches the number assumed by these analyses. (Reference 57)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 2 of 9 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

6. Update Alloy 600 Program - Entergy 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. Incorporate AMP & TLAA into FSAR - In a periodic FSAR update following NRC issuance of NA the renewed operating license, in accordance with 10 CFR 50.71 (e), the summary descriptions of Aging Management Programs and Time Limited Aging Analyses, provided in Appendix A, will be incorporated into appropriate sections of the FSAR. (Reference 57)
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 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).

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 3 of 9 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

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 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)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 4 of 9 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

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)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 5 of 9 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. Reactor Vessel PT/LTOP Curves - The Reactor Vessel Integrity Surveillance Program will Reactor Vessel Integrity ensure that pressure-temperature and LTOP curves are updated to reflect the additional Surveillance Program neutron fluence accumulated during the extended operating period. (Reference 57)
30. RV Surveillance Capsules - Document and establish requirement to save and store all pulled Reactor Vessel Integrity and tested reactor vessel surveillance capsules for future reconstitution use. (Reference 57) Surveillance Program

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 6 of 9 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

31. Surv Capsule Withdrawal Schedule - Evaluate and revise as necessary, the surveillance Reactor Vessel Integrity capsule withdrawal and testing schedule of FSAR Table 4-20 such that at least one capsule Surveillance Program remains 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)
32. Reactor Vessel Integrity Program - Develop a program level procedure to implement and Reactor Vessel Integrity control Technical Specification and FSAR activities associated with the Reactor Vessel Surveillance Program Integrity Surveillance Program, including activities associated with surveillance capsules, pressure-temperature limit curves, LTOP setpoints, neutron embrittlement calculation methodology, neutron fluence calculations and control, and documentation requirements. Title of procedure should be, "Reactor Vessel Integrity Surveillance Program." (Reference 57)
33. Reactor Vessel Internals Program Submittal - Entergy will participate in industry initiatives Reactor Vessel Internals that will generate additional data on aging mechanisms relevant to reactor vessel internals Inspection Program (RVI), including void swelling, and develop appropriate inspection techniques to permit detection and characterization of features of interest. Recommendations for augmented inspections and techniques resulting from this effort will be incorporated into the Reactor Vessel Internals Program as applicable. (Reference 82)
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)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 7 of 9 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

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, Entergy 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 - Entergy will enhance the preventive maintenance NA program 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)
41. Industry Standard Use for Tank Inspection - Entergy will identify specific methods of System Monitoring inspection for individual components as part of the System Monitoring Program implementation Program procedure 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)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 8 of 9 LONG-TERM COMMITMENTS FOR LICENSE RENEWAL OF PALISADES NUCLEAR PLANT Text of Commitment, Due Date, Source Affected Program

42. FAC Acceptance Criterion NSR Pipe Wall - Entergy will revise the governing procedure for Flow Accelerated the Flow Accelerated Corrosion Program to include the value of 87.5% of nominal wall Corrosion Program thickness 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 - Entergy will perform a neutron absorption NA

("blackness") 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 Entergy 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)

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-9 Revision 30 Page 9 of 9 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)

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 Material Environment Aging Effect Aging Management Function(s) Requiring Program Management ESS - Engineering Safeguards Loss of Material 1 Fluid Pressure System 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 1 Fluid Pressure System 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 Accumulator Fluid Pressure Carbon Steel Weather Loss of Material System Monitoring Boundary Program (external) 1 10 CFR 50.37(b) Determination Log No. 54.37-PLP-2011-004.

2 10 CFR 50.37(b) Determination Log No. 54.37-PLP-2015-001.

Retrieved from "https://kanterella.com/w/index.php?title=ML21125A330&oldid=3415531"