Amendment No. 272, 273 

HOLTEC PALISADES, LLC 

HOLTEC DECOMMISSIONING INTERNATIONAL, LLC 

DOCKET NO. 50-255 

PALISADES NUCLEAR PLANT 

RENEWED FACILITY OPERATING LICENSE 

Renewed License No. DPR-20 

1. The Nuclear Regulatory Commission (NRC or the Commission) having previously made the 

findings set forth in Operating License No. DPR-20, dated February 21, 1991, has now 

found that: 

A. The application for Renewed Operating License No. DPR-20 complies with the 

standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 

and the Commission’s rules and regulations set forth in 10 CFR Chapter I, and all 

required notifications to other agencies or bodies have been duly made; 

B. [deleted]; 

C. Actions have been identified and have been or will be taken with respect to: 

(1) managing the effects of aging on the functionality of structures and components 

that have been identified to require review under 10 CFR 54.21(a)(1) during the period 

of extended operation, and (2) time-limited aging analyses that have been identified to 

require review under 10 CFR 54.21(c), such that there is reasonable assurance that 

the activities authorized by this renewed operating license will continue to be 

conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3 

for the facility, and that any changes made to the facility’s current licensing basis in 

order to comply with 10 CFR 54.29(a) are in accordance with the Act and the 

Commission’s regulations; 
- 2 - 

Renewed License No. DPR-20 

Amendment No. 272, 273 

D. The facility will operate in conformity with the application, the provisions of the Act, and 

the regulations of the Commission; 

E. There is reasonable assurance: (i) that the activities authorized by this renewed 

operating license can be conducted without endangering the health and safety of the 

public, and (ii) that such activities will be conducted in compliance with the 

Commission’s regulations set forth in 10 CFR Chapter I; 

F. Holtec Palisades, LLC (Holtec Palisades) is financially qualified and Holtec 

Decommissioning International, LLC (HDI) is financially and technically qualified to 

engage in the activities authorized by this renewed operating license in accordance 

with the Commission’s regulations set forth in 10 CFR Chapter I; 

G. Holtec Palisades and HDI have satisfied the applicable provisions of 10 CFR Part 140, 

“Financial Protection Requirements and Indemnity Agreements” of the Commission’s 

regulations; 

H. The issuance of this renewed operating license will not be inimical to the common 

defense and security or to the health and safety of the public; 

I. After weighing the environmental, economic, technical, and other benefits of the facility 

against environmental and other costs and considering available alternatives, the 

issuance of this renewed Facility Operating License No. DPR-20, subject to the 

conditions for protection of the environment set forth herein, is in accordance with 

10 CFR Part 51 (formerly Appendix D to Part 50), of the Commission’s regulations and 

all applicable requirements have been satisfied; and 

J. The receipt, possession, and use of source, byproduct, and special nuclear material as 

authorized by this renewed operating license will be in accordance with 10 CFR Parts 

30, 40, and 70. 

2. Renewed Facility Operating License No. DPR-20, is hereby issued to Holtec Palisades and 

HDI as follows: 

A. This renewed license applies to the Palisades Plant, a pressurized light water 

moderated and cooled reactor and electrical generating equipment (the facility). The 

facility is located in Van Buren County, Michigan, and is described in the Palisades 

Plant Updated Final Safety Analysis Report, as supplemented and amended, and in 

the Palisades Plant Environmental Report, as supplemented and amended. 

B. Subject to the conditions and requirements incorporated herein, the Commission 

hereby licenses: 

(1) Pursuant to Section 104b of the Act, as amended, and 10 CFR Part 50, “Licensing 

of Production and Utilization Facilities,” (a) Holtec Palisades to possess and use, 

and (b) HDI to possess and use, the facility at the designated location in Van 

Buren County, Michigan, in accordance with the procedures and limitation set 

forth in this license; 
- 3 - 

Renewed License No. DPR-20 

Amendment No. 272, 273 

(2) HDI, pursuant to the Act and 10 CFR Parts 40 and 70, to possess source, and 

special nuclear material that was used as reactor fuel, in accordance with the 

limitations for storage, as described in the Updated Final Safety Analysis Report, 

as supplemented and amended; 

(3) HDI, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, 

and use byproduct, source, and special nuclear material as sealed sources that 

were used for reactor startup, sealed sources that were used for reactor 

instrumentation and are used in the calibration of radiation monitoring equipment, 

and that were used as fission detectors in amounts as required; 

(4) HDI, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, 

and use in amounts as required any byproduct, source, or special nuclear 

material for sample analysis or instrument calibration, or associated with 

radioactive apparatus or components; and 

(5) HDI, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not 

separate, such byproduct and special nuclear materials that were produced by 

the operations of the facility. 

C. This renewed operating license shall be deemed to contain and is subject to the 

conditions specified in the Commission’s regulations in 10 CFR Chapter I and is subject 

to all applicable provisions of the Act; to the rules, regulations, and orders of the 

Commission now or hereafter in effect; and is subject to the additional conditions 

specified or incorporated below: 

(1) [deleted] 

(2) The Technical Specifications contained in Appendix A, as revised through 

Amendment No. 273, and the Environmental Protection Plan contained in 

Appendix B are hereby incorporated in the license. HDI shall maintain the facility 

in accordance with the Technical Specifications and the Environmental Protection 

Plan. 

(3) [deleted] 

(4) [deleted] 

(5) Movement of a fuel cask in or over the spent fuel pool is prohibited when 

irradiated fuel assemblies decayed less than 90 days are in the spent fuel pool. 
- 4 - 

Renewed License No. DPR-20 

Amendment No. 257, 272 

(6) Develop and maintain strategies for addressing large fires and explosions and 

that include the following key areas: 

a. Fire fighting response strategy with the following elements: 

1. Pre-defined coordinated fire response strategy and guidance 

2. Assessment of mutual aid fire fighting assets 

3. Designated staging areas for equipment and materials 

4. Command and control 

5. Training of response personnel 

b. Operations to mitigate fuel damage considering the following: 

1. Protection and use of personnel assets 

2. Communications 

3. Minimizing fire spread 

4. Procedures for implementing integrated fire response strategy 

5. Identification of readily-available pre-staged equipment 

6. Training on integrated fire response strategy 

7. Spent fuel pool mitigation measures 

c. Actions to minimize release to include consideration of: 

1. Water spray scrubbing 

2. Dose to onsite responders 

(7) [deleted] 

(8) [deleted] 
- 5 - 

Renewed License No. DPR-20 

Amendment No. 272, 273 

D. [deleted] 

E. HDI shall fully implement and maintain in effect all provisions of the 

Commission-approved physical security, training and qualification, and safeguards 

contingency plans including amendments made pursuant to provisions of the 

Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 

FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The 

combined set of plans, which contains Safeguards Information protected under 10 CFR 

73.21, is entitled: “Palisades Nuclear Plant Physical Security Plan.” 

HDI shall fully implement and maintain in effect all provisions of the 

Commission-approved cyber security plan (CSP), including changes made pursuant to 

the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Palisades CSP was approved 

by License Amendment No. 243 as supplemented by changes approved by License 

Amendment Nos. 248, 253, 259, and 264. 

F. [deleted] 

G. Holtec Palisades and HDI shall have and maintain financial protection of such type and 

in such amounts as the Commission shall require in accordance with Section 170 of 

the Atomic Energy Act of 1954, as amended, to cover public liability claims. 
- 6 - 

Renewed License No. DPR-20 

Amendment No. 224, 272 

H. [deleted] 

I. [deleted] 

J. [deleted] 

K. This license is effective as of the date of issuance and until the Commission notifies 

the licensee in writing that the license is terminated. 

FOR THE NUCLEAR REGULATORY COMMISSION 

/RA/ 

J. E. Dyer, Director 

Office of Nuclear Reactor Regulation 

Attachments: 

1. Appendix A – Permanently Defueled Technical Specifications 

2. Appendix B – Environmental Protection Plan 

Date of Issuance: January 17, 2007 
PALISADES PLANT

RENEWED FACILITY OPERATING LICENSE DPR-20

APPENDIX A

PERMANENTLY DEFUELED

TECHNICAL SPECIFICATIONS

As Amended through Amendment No. 272
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS

Palisades Nuclear Plant i Amendment No. 189, 272

1.0 USE AND APPLICATION

1.1 Definitions

1.2 Logical Connectors

1.3 Completion Times

1.4 Frequency

2.0 (Deleted)

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

3.7 FACILITY SYSTEMS

3.7.14 Spent Fuel Pool (SFP) Water Level

3.7.15 Spent Fuel Pool (SFP) Boron Concentration

3.7.16 Spent Fuel Pool Storage

4.0 DESIGN FEATURES

4.1 Site Location

4.2 (Deleted)

4.3 Fuel Storage

5.0 ADMINISTRATIVE CONTROLS

5.1 Responsibility

5.2 Organization

5.3 Facility Staff Qualifications

5.4 Procedures

5.5 Programs and Manuals

5.6 Reporting Requirements

5.7 High Radiation Area
Palisades Nuclear Plant 1.1-1 Amendment No. 189, 205, 216, 

262, 266, 272 

Definitions 

1.1 

1.0 USE AND APPLICATION 

1.1 Definitions 

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

The defined terms of this section appear in capitalized type and are applicable throughout these 

Technical Specifications and Bases. 

----------------------------------------------------------------------------------------------------------------------------- 

Term Definition

ACTIONS ACTIONS shall be that part of a Specification that prescribes 

Required Actions to be taken under designated Conditions 

within specified Completion Times. 

CERTIFIED FUEL HANDLER A CERTIFIED FUEL HANDLER is an individual who complies 

with provisions of the CERTIFIED FUEL HANDLER training 

and retraining program required by Specification 5.3.2. 

NON-CERTIFIED OPERATOR A NON-CERTIFIED OPERATOR is a non-licensed operator 

who complies with the qualification requirements of 

Specification 5.3.1. 
Palisades Nuclear Plant 1.2-1 Amendment No. 189, 272 

Logical Connectors 

1.2 

1.0 USE AND APPLICATION 

1.2 Logical Connectors 

PURPOSE The purpose of this section is to explain the meaning of logical 

connectors. 

Logical connectors are used in Technical Specifications (TS) to 

discriminate between, and yet connect, discrete Conditions, Required 

Actions, Completion Times, Surveillances, and Frequencies. The only 

logical connector that appears in TS is AND. The physical arrangement 

of this connector constitutes logical conventions with specific meanings. 

BACKGROUND Levels of logic may be used to state Required Actions. These levels are 

identified by the placement (or nesting) of the logical connectors and by 

the number assigned to each Required Action. The first level of logic is 

identified by the first digit of the number assigned to a Required Action 

and the placement of the logical connector in the first level of nesting (i.e., 

left justified with the number of the Required Action). 
Logical Connectors 

1.2 

1.2 Logical Connectors 

Palisades Nuclear Plant 1.2-2 Amendment No. 189, 272 

EXAMPLES The following example illustrates the use of logical connectors. 

EXAMPLE 1.2-1 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. LCO not met. A.1 Suspend . . . 

AND 

A.2 Initiate . . . 

In this example the logical connector AND is used to indicate that when in 

Condition A, both Required Actions A.1 and A.2 must be completed. 
Palisades Nuclear Plant 1.3-1 Amendment No. 270, 272 

Completion Times 

1.3 

1.0 USE AND APPLICATION 

1.3 Completion Times 

PURPOSE The purpose of this section is to establish the Completion Time 

convention and to provide guidance for its use. 

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements 

for ensuring safe storage and handling of spent nuclear fuel. The 

ACTIONS associated with an LCO state Conditions that typically describe 

the ways in which the requirements of the LCO can fail to be met. 

Specified with each stated Condition are Required Action(s) and 

Completion Time(s). 

DESCRIPTION The Completion Time is the amount of time allowed for completing a 

Required Action. It is referenced to the discovery of a situation (e.g., 

variable not within limits) that requires entering an ACTIONS Condition 

unless otherwise specified, providing the facility is in a specified condition 

stated in the Applicability of the LCO. 

 The Completion Time begins when a Certified Fuel Handler (CFH) on the 

shift crew with responsibility for plant operations makes the determination 

that an LCO is not met and an ACTIONS Condition is entered. 

Required Actions must be completed prior to the expiration of the 

specified Completion Time. An ACTIONS Condition remains in effect and 

the Required Actions apply until the Condition no longer exists or the 

plant is not within the LCO Applicability. 
Completion Times 

1.3 

1.3 Completion Times 

Palisades Nuclear Plant 1.3-2 Amendment No. 189, 270, 272 

EXAMPLE The following example illustrates the use of Completion Times with 

different Required Actions. 

EXAMPLE 1.3-1 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Spent Fuel

Pool boron

concentration

not within

limit.

A.1 Suspend movement

of fuel assemblies in 

the Spent Fuel Pool.

AND 

A.2 Initiate action to

restore Spent Fuel 

Pool boron 

concentration to 

within limit

. 

Immediately 

Immediately 

Condition A has two Required Actions. Each Required Action has its own 

separate Completion Time. Each Completion Time is referenced to the 

time that Condition A is entered. 

The Required Actions of Condition A are to immediately suspend 

movement of fuel assemblies in the Spent Fuel Pool and initiate action to 

restore Spent Fuel Pool boron concentration within limit. 

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action 

COMPLETION TIME should be pursued without delay and in a controlled manner. 
Frequency 

1.4 

Palisades Nuclear Plant 1.4-1 Amendment No. 231, 272 

1.0 USE AND APPLICATION 

1.4 Frequency 

PURPOSE The purpose of this section is to define the proper use and application of 

Frequency requirements. 

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which 

the Surveillance must be met in order to meet the associated LCO. An 

understanding of the correct application of the specified Frequency is 

necessary for compliance with the SR. 

The "specified Frequency" is referred to throughout this section and each 

of the Specifications of Section 3.0, Surveillance Requirement (SR) 

Applicability. The "specified Frequency" consists of the requirements of 

the Frequency column of each SR. 

The use of "met” and “performed” in these instances conveys specific 

meanings. A Surveillance is "met” only when the acceptance criteria are 

satisfied. Known failure of the requirements of a Surveillance, even 

without a Surveillance specifically being “performed,” constitutes a 

Surveillance not "met.” “Performance” refers only to the requirement to 

specifically determine the ability to meet the acceptance criteria. 

. 
Frequency

1.4

1.4 Frequency

Palisades Nuclear Plant 1.4-2 Amendment No. 231, 272 

EXAMPLES The following examples illustrate the type of Frequency statements that 

appear in the Technical Specifications (TS). 

EXAMPLE 1.4-1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

Verify level is within limit. 7 days

Example 1.4-1 contains one type of SR encountered in the TS. The 

Frequency specifies an interval of 7 days during which the associated 

Surveillance must be performed at least one time. Performance of the 

Surveillance initiates the subsequent interval. Although the Frequency is

stated as 7 days, an extension of the time interval to 1.25 times the 

stated Frequency is allowed by SR 3.0.2 for flexibility. The measurement 

of this interval continues at all times, even when the SR is not required to 

be met per SR 3.0.1 (such as when a variable is outside specified limits, 

or the facility is outside the Applicability of the LCO). If the interval 

specified by SR 3.0.2 is exceeded while the facility is in a specified 

condition in the Applicability of the LCO, then SR 3.0.3 becomes 

applicable.

If the interval as specified by SR 3.0.2 is exceeded while the facility is not 

in a specified condition in the Applicability of the LCO for which 

performance of the SR is required, then SR 3.0.4 becomes applicable. 

The Surveillance must be performed within the Frequency requirements 

of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the specified 

condition or the LCO is considered not met (in accordance with SR 3.0.1). 
Frequency 

1.4 

1.4 Frequency 

Palisades Nuclear Plant 1.4-3 Amendment No. 231, 272 

EXAMPLES EXAMPLE 1.4-2 

 (continued) 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

Verify... Prior to storing a 

fuel assembly... 

Example 1.4-2 illustrates a one time performance Frequency. This type of 

Frequency does not qualify for the extension allowed by SR 3.0.2. 
Palisades Nuclear Plant 2.0-1 Amendment No. 189, 272 

2.0 (Deleted) 
Palisades Nuclear Plant 3.0-1 Amendment No. 252, 263, 270, 

272

LCO Applicability

3.0

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

LCO 3.0.1 LCOs shall be met during the specified conditions in the Applicability, 

except as provided in LCO 3.0.2. 

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the 

associated Conditions shall be met. 

If the LCO is met or is no longer applicable prior to expiration of the 

specified Completion Time(s), completion of the Required Action(s) is not 

required, unless otherwise stated.
Palisades Nuclear Plant 3.0-2 Amendment No. 219, 270, 272

SR Applicability

3.0

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for 

individual LCOs, unless otherwise stated in the SR. Failure to meet a 

Surveillance, whether such failure is experienced during the performance 

of the Surveillance or between performances of the Surveillance, shall be 

failure to meet the LCO. Failure to perform a Surveillance within the 

specified Frequency shall be failure to meet the LCO except as provided 

in SR 3.0.3. Surveillances do not have to be performed on variables 

outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is 

performed within 1.25 times the interval specified in the Frequency, as 

measured from the previous performance. 

SR 3.0.3 If it is discovered that a Surveillance was not performed within its 

specified Frequency, then compliance with the requirement to declare the 

LCO not met may be delayed, from the time of discovery, up to 24 hours 

or up to the limit of the specified Frequency, whichever is greater. This 

delay period is permitted to allow performance of the Surveillance. The 

delay period is only applicable when there is a reasonable expectation the 

surveillance will be met when performed. A risk evaluation shall be 

performed for any Surveillance delayed greater than 24 hours and the risk 

impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must 

immediately be declared not met, and the applicable Condition(s) must be 

entered.

When the Surveillance is performed within the delay period and the 

Surveillance is not met, the LCO must immediately be declared not met, 

and the applicable Condition(s) must be entered. 

SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall only be 

made when the LCO's Surveillances have been met within their specified 

Frequency, except as provided by SR 3.0.3.
SFP Water Level

3.7.14

Palisades Nuclear Plant 3.7.14-1 Amendment No. 271, 272

3.7 FACILITY SYSTEMS 

3.7.14 Spent Fuel Pool (SFP) Water Level

LCO 3.7.14 The SFP water level shall be ≥ 647 ft elevation.

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

SFP level may be below the 647 ft elevation to support fuel cask 

movement, if the displacement of water by the fuel cask when submerged 

in the SFP, would raise SFP level to ≥ 647 ft elevation.

------------------------------------------------------------------------------------------------ 

APPLICABILITY: During movement of irradiated fuel assemblies in the SFP, 

During movement of a fuel cask in or over the SFP.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. SFP water level not within 

limit.

A.1 Suspend movement of 

irradiated fuel 

assemblies in SFP.

AND

Immediately

A.2 Suspend movement of 

fuel cask in or over the 

SFP. 

Immediately

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.7.14.1 Verify the SFP water level is ≥ 647 ft elevation. 7 days
SFP Boron Concentration

3.7.15

Palisades Nuclear Plant 3.7.15-1 Amendment No. 271, 272

3.7 FACILITY SYSTEMS 

3.7.15 Spent Fuel Pool (SFP) Boron Concentration

LCO 3.7.15 The SFP boron concentration shall be ≥ 1720 ppm.

APPLICABILITY: When fuel assemblies are stored in the Spent Fuel Pool.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. SFP boron concentration 

not within limit.

A.1 Suspend movement of 

fuel assemblies in the 

SFP. 

AND

Immediately

A.2 Initiate action to restore 

SFP boron 

concentration to within 

limit.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.15.1 Verify the SFP boron concentration is within limit. 7 days
Spent Fuel Pool Storage

3.7.16

Palisades Nuclear Plant 3.7.16-1 Amendment No. 250, 272

3.7 FACILITY SYSTEMS 

3.7.16 Spent Fuel Pool Storage

LCO 3.7.16 Storage in the spent fuel pool shall be as follows:

 

a. Each fuel assembly and non-fissile bearing component stored in a 

Region I Carborundum equipped storage rack shall be within the 

limitations in Specification 4.3.1.1 and, as applicable, within the 

requirements of the maximum nominal planar average U-235 

enrichment and burnup of Tables 3.7.16-2, 3.7.16-3, 3.7.16-4 or 

3.7.16-5, 

b. Fuel assemblies in a Region I Metamic equipped storage rack 

shall be within the limitations in Specification 4.3.1.2, and

c. The combination of maximum nominal planar average U-235 

enrichment, burnup, and decay time of each fuel assembly stored 

in Region II shall be within the requirements of Table 3.7.16-1. 

APPLICABILITY: Whenever any fuel assembly or non-fissile bearing component is stored 

in the spent fuel pool or the north tilt pit.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Requirements of the LCO 

not met.

A.1 Initiate action to restore 

the noncomplying fuel 

assembly or non-fissile 

bearing component 

within requirements.

Immediately

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.7.16.1 Verify by administrative means each fuel assembly 

or non-fissile bearing component meets fuel 

storage requirements.

Prior to storing the 

fuel assembly or 

non-fissile bearing 

component in the 

spent fuel pool
Table 3.7.16-1 (page 1 of 1) 

Spent Fuel Pool Storage 

3.7.16 

Spent Fuel Minimum Burnup and Decay Requirements 

for Storage in Region II of the Spent Fuel Pool and North Tilt Pit 

Nominal 

Planar 

Average 

U-235 Burnup Burnup Burnup Burnup Burnup Enrichment (GWD/MTU) (GWD/MTU) (GWD/MTU) (GWD/MTU) (GWD/MTU) (Wt%) No Decay 1 Year Decay 3 Year Decay 5 Year Decay 8 Year Decay 

.s 1.14 0 0 0 0 0 

> 1.14 3.477 3.477 3.477 3.477 3.477 

1.20 3.477 3.477 3.477 3.477 3.477 

1.40 7.951 7.844 7.464 7.178 6.857 

1.60 11.615 11.354 10.768 10.319 9.847 

1.80 14.936 14.535 13.767 13.187 12.570 

2.00 18.021 17.502 16.561 15.875 15.117 

2.20 21.002 20.417 19.313 18.499 17.611 

2.40 23.900 23.201 21.953 21.034 20.050 

2.60 26.680 25.905 24.497 23.487 22.378 

2.80 29,388 28.528 27.006 25.879 24.678 

3.00 32.044 31.114 29.457 28.243 26.942 

3.20 34.468 33.457 31.698 30.397 29.008 

3.40 36.848 35.783 33.920 32.544 31.079 

3.60 39.152 38,026 36.059 34.615 33.077 

3.80 41.419 40.226 38.163 36.650 35,049 

4.00 43.661 42.422 40.257 38.673 37.007 

4.20 45.987 44.684 42.415 40.778 39.028 

4.40 48.322 46.950 44.588 42.877 41.041 

4.60 50.580 49.158 46.690 44.911 43.003 

(a) Linear interpolation between two consecutive points will yield acceptable results. 

(b} Comparison of nominal assembly average bumup numbers to these in the table is acceptable if 

measurement uncertainty is .s 10%. 

Palisades Nuclear Plant 3.7.16-2 Amendment No. 489, ~. ~. 246 
Table 3.7.16-2 (page 1 of 1) 

Spent Fuel Pool Storage 

3.7.16 

Spent Fuel Minimum Burnup Requirements for 

Storage in Region 1 B (three-of-four loading configuration) 

of the Main Spent Fuel Pool 

Nominal Planar Burnup Burnup 

Average U-235 {GWD/MTU) {GWD/MTU) 

Enrichment (Batches L (Batches A 

(Wt%) and later) through K) 

S2.10 0 1.0 

2.40 4.1 5.1 

2.60 6.7 7.7 

2.80 9.5 10.5 

3.00 12.2 13.2 

3.20 14.9 15.9 

3.40 17.6 18.6 

3.60 20.2 21.2 

3.80 23.0 24.0 

4.00 25.7 26.7 

4.20 28.4 29.4 

4.40 31.1 32.1 

4.54 33.0 34.0 

(a) Linear interpolation between two consecutive points for nominal planar average U-235 enrichments 

between 2.1 0 and 4.54 will yield acceptable results. 

(b) Comparison of nominal assembly average bumup numbers to these in the table is acceptable if 

measurement uncertainty is ~ 10%. 

Palisades Nuclear Plant 3.7.16-3 Amendment No. 246 
Table 3.7.16-3 (page 1 of 1) 

Spent Fuel Pool Storage 

3.7.16 

Spent Fuel Minimum Burnup Requirements for 

Storage in Region 1 C (four-of-four loading configuration) 

of the Main Spent Fuel Pool 

Nominal Planar Bumup Bumup 

Average U-235 (GWD/MTU) (GWD/MTU) 

Enrichment (Batches L (Batches A 

(Wt%) and later) through K) 

S1.35 0 1.0 

2.40 20.7 21.7 

2.60 24.5 25.5 

2.75 27.5 28.5 

2.80 28.2 29.2 

3.00 31.0 32.0 

3.20 33.9 34.9 

3.40 36.7 37.7 

3.60 39.5 40.5 

3.80 42.4 43.4 

4.00 45.2 46.2 

4.20 48.0 49.0 

4.40 50.8 51.8 

4.54 52.8 53.8 

(a} Linear interpolation between two consecutive points for nominal planar average U-235 enrichments 

between 1.35 and 4.54 will yield acceptable results. 

(b) Comparison of nominal assembly average bumup numbers to these in the table is acceptable if 

measurement uncertainty is s: 10%. 

Palisades Nuclear Plant 3.7.16-4 Amendment No. 246 
Table 3.7.16-4 (page 1 of 1) 

Spent Fuel Pool Storage 

3.7.16 

Spent Fuel Minimum Burnup Requirements for 

Storage in Region 1 D (three-of four loading configuration) 

of the North Tilt Pit 

Nominal Planar Burnup Burnup 

Average U-235 (GWD/MTU) (GWD/MTU) 

Enrichment (Batches L (Batches A 

(Wt%) and later) through K) 

S2.35 0 1.0 

2.40 0.5 1.5 

2.60 2.4 3.4 

2.80 4.3 5.3 

3.00 6.2 7.2 

3.20 8.1 9.1 

3.40 10.0 11.0 

3.60 11.9 12.9 

3.80 13.8 14.8 

4.00 15.7 16.7 

4.20 17.7 18.7 

4.40 19.6 20.6 

4.54 20.9 21.9 

(a) Linear interpolation between two consecutive points for nominal planar average U-235 enrichments 

between 2.35 and 4.54 will yield acceptable results. 

(b) Comparison of nominal assembly average burnup numbers to these in the table is acceptable if 

measurement uncertainty is~ 10%. 

Palisades Nuclear Plant 3.7.16-5 Amendment No. 246 
Table 3.7.16-5 (page 1 of 1) 

Spent Fuel Pool Storage 

3.7.16 

Spent Fuel Minimum Bumup Requirements for 

Storage in Region 1 E (four-of-four loading configuration) 

of the North Tilt Pit 

Nominal Planar Bumup Bumup 

Average U-235 (GWD/MTU) (GWD/MTU) 

Enrichment (Batches L (Batches A 

(Wt%) and later) through K) 

S1 .48 0 1.0 

2.40 13.9 14.9 

2.60 16.9 17.9 

2.80 19.9 20.9 

3.00 23.0 24.0 

3.20 26.0 27.0 

3.30 27.5 28.5 

3.40 28.7 29.7 

3.60 31.0 32.0 

3.80 33.3 34.3 

4.00 35.6 36.6 

4.20 37.9 38.9 

4.40 40.2 41.2 

4.54 41.8 42.8 

(a) Linear interpolation between two consecutive points for nominal planar average U-235 

enrichments between 1.48 and 4.54 will yield acceptable results. · 

(b) Comparison of nominal assembly average bumup numbers to these in the table is acceptable if 

measurement uncertainty is~ 10%. 

Palisades Nuclear Plant 3.7.16-6 Amendment No. 246 
 Design Features 

 4.0

Palisades Nuclear Plant 4.0-1 Amendment No. 272, 273 

4.0 DESIGN FEATURES 

4.1 Site Location 

The Palisades Nuclear Plant is located on property owned by Holtec Palisades, LLC 

on the eastern shore of Lake Michigan approximately four and one-half miles south 

of the southern city limits of South Haven, Michigan. The minimum distance to the 

boundary of the exclusion area as defined in 10 CFR 100.3 shall be 677 meters. 

4.2 (Deleted) 

4.3 Fuel Storage 

4.3.1 Criticality 

4.3.1.1 The Region I (See Figure B 3.7.16-1) Carborundum equipped fuel 

storage racks incorporating Regions 1A, 1B, 1C, 1D, and 1E are 

designed and shall be maintained with: 

a. Irradiated fuel assemblies having a maximum nominal planar 

average U-235 enrichment of 4.54 weight percent; 

b. Keff < 1.0 if fully flooded with unborated water, which includes 

allowances for uncertainties as described in Section 9.11 of the 

FSAR; 

c. Keff ≤ 0.95 if fully flooded with water borated to 850 ppm, which 

includes allowances for uncertainties as described in 

Section 9.11 of the FSAR; 

d. Regions 1A, 1B, and 1C have a nominal 10.25 inch center to 

center distance between fuel assemblies; 

e. Regions 1D and 1E have a nominal 11.25 inch by 10.69 inch 

center to center distance between fuel assemblies; 

f. Region 1A is defined as a subregion of the Region I storage 

racks located in the main spent fuel pool and is subject to the 

following restrictions. Fuel assemblies (or fissile bearing 

components) located in Region 1A shall be in a maximum of 

two-of-four checkerboard loading pattern of two fuel assemblies 

(or fissile bearing components) and two empty cells. 

Designated empty cells may contain non-fuel bearing 

components in accordance with Section 4.3.1.1m.2. below; 
Design Features

4.0

Palisades Nuclear Plant 4.0-2 Amendment No. 246, 272

4.3 Fuel Storage

4.3.1 Criticality (continued)

g. Region 1B is defined as a subregion of the Region I storage 

racks located in the main spent fuel pool and is subject to the 

following restrictions. Fuel assemblies (or fissile bearing 

components) located in Region 1B shall be in a maximum of 

three-of-four loading pattern consisting of three fuel assemblies

(or fissile bearing components) and one empty cell. Fuel 

assemblies in Region 1B shall meet the enrichment dependent 

burnup restrictions listed in Table 3.7.16-2. Designated empty 

cells may contain non-fuel bearing components in accordance 

with Section 4.3.1.1m.2. below;

h. Region 1C is defined as a subregion of the Region I storage 

racks located in the main spent fuel pool and is subject to the 

following restrictions. Fuel assemblies (or fissile bearing 

components) located in Region 1C may be in a maximum of 

four-of-four loading pattern with no required empty cells. Fuel 

assemblies in Region 1C shall meet the enrichment dependent

burnup restrictions listed in Table 3.7.16-3;

i. Interface requirements for the main spent fuel pool between 

Region 1A, 1B, and 1C are as follows. Region 1A, 1B, and 1C 

can be distributed in Region I, in the main spent fuel pool, in 

any manner provided that any two-by-two grouping of storage 

cells and the assemblies in them correspond to the 

requirements of 4.3.1.1f., 4.3.1.1g., or 4.3.1.1h. above;

j. Region 1D is defined as a subregion of the Region I storage 

rack located in the north tilt pit and is subject to the following 

restrictions. Fuel assemblies (or fissile bearing components) 

located in Region 1D may be in a maximum of three-of-four 

loading pattern consisting of three fuel assemblies (or fissile 

bearing components) and one empty cell. Fuel assemblies in 

Region 1D shall meet the enrichment dependent burnup 

restrictions listed in Table 3.7.16-4;

k. Region 1E is defined as a subregion of the Region I storage 

rack located in the north tilt pit and is subject to the following 

restrictions. Fuel assemblies (or fissile bearing components) 

located in Region 1E may be in a maximum of four-of-four 

loading pattern with no required empty cells. Fuel assemblies 

in Region 1E shall meet the enrichment dependent burnup 

restrictions listed in Table 3.7.16-5;
 Design Features

 4.0

Palisades Nuclear Plant 4.0-3 Amendment No. 246, 250, 272

4.3 Fuel Storage

4.3.1 Criticality (continued)

l. Interface requirements for the north tilt pit between Region 1D 

and 1E are as follows. Region 1D and 1E can be distributed in 

Region I in the north tilt pit in any manner provided that any 

two-by-two grouping of storage cells and the assemblies in 

them correspond to the requirements of 4.3.1.1j. or 4.3.1.1k. 

above; 

m. Non-fissile bearing component restrictions are as follows:

1. Non-fissile material components may be stored in any 

designated fuel location in Region 1A, 1B, 1C, 1D, or 1E 

without restriction.

2. The following non-fuel bearing components (NFBC) may 

be stored face adjacent to fuel in any designated empty 

cell in Region 1A or 1B.

 

 (i) The gauge dummy assembly and the lead dummy 

assembly may be stored face adjacent to fuel in 

any designated empty cells with no minimum 

required separation distance.

 

(ii) A component comprised primarily of stainless steel

that displaces less than 30 square inches of water 

in any plane within the active fuel region may be 

stored in any designated empty cell as long as the 

NFBC is at least ten locations away from any other 

NFBC that is in a designated empty cell, with the 

exception of 4.3.1.1m.2.(i) above.

3. Control blades may be stored in both fueled and unfueled 

locations in Regions 1D and 1E, with no limitation on the 

number.
Design Features

4.0

Palisades Nuclear Plant 4.0-4 Amendment No. 250, 272

4.3 Fuel Storage

4.3.1.2 The Region I (See Figure B 3.7.16-1) Metamic equipped fuel storage 

racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum nominal planar average 

U-235 enrichment of 4.95 weight percent; 

b. Keff < 1.0 if fully flooded with unborated water, which includes 

allowances for uncertainties as described in Section 9.11 of the 

FSAR; 

c. Keff ≤ 0.95 if fully flooded with water borated to 850 ppm, which 

includes allowances for uncertainties as described in 

Section 9.11 of the FSAR; 

d. A nominal 10.25 inch center to center distance between fuel 

assemblies; 

e. Irradiated fuel assemblies; 

f. Two empty rows of storage locations shall exist between the 

fuel assemblies in a Carborundum equipped rack and the fuel 

assemblies in an adjacent Metamic equipped rack; and

g. A minimum Metamic B10 areal density of 0.02944 g/cm2. 

 4.3.1.3 The Region II fuel storage racks (See Figure B 3.7.16-1) are designed 

and shall be maintained with: 

 a. Fuel assemblies having maximum nominal planar average 

U-235 enrichment of 4.60 weight percent;

 b. Keff < 1.0 if fully flooded with unborated water, which includes 

allowances for uncertainties as described in Section 9.11 of the 

FSAR. 

c. Keff ≤ 0.95 if fully flooded with water borated to 850 ppm, which 

includes allowance for uncertainties as described in Section 

9.11 of the FSAR.

d. A nominal 9.17 inch center to center distance between fuel 

assemblies; and

e. Irradiated fuel assemblies which meet the maximum nominal 

planar average U-235 enrichment, burnup, and decay time 

requirements of Table 3.7.16-1.

4.3.1.4 (Deleted)
Design Features

4.0

Palisades Nuclear Plant 4.0-5 Amendment No. 236, 250, 272

4.3 Fuel Storage

4.3.2 Drainage

The spent fuel storage pool cooling system suction and discharge piping is 

designed and shall be maintained to prevent inadvertent draining of the pool 

below elevation 644 ft 5 inches.

4.3.3 Capacity

The spent fuel storage pool and north tilt pit are designed and shall be 

maintained with a storage capacity limited to no more than 892 fuel assemblies.
5.0 ADMINISTRATIVE CONTROLS 

5.1 Responsibility 

Responsibility 

5.1 

5.1.1 The plant manager shall be responsible for overall facility operation and shall 

delegate in writing the succession for this responsibility during absences. 

The plant manager or designee shall approve, prior to implementation, each 

proposed test, experiment or modification to systems or equipment that affect 

safe storage and maintenance of spent nuclear fuel. 

5.1.2 The shift manager shall be responsible for the shift command function. 

Palisades Nuclear Plant 5.0-1 Amendment No. 489, 266 
Organization 

5.2 

5.0 ADMINISTRATIVE CONTROLS 

5.2 Organization 

5.2.1 

5.2.2 

Onsite and Offsite Organizations 

Onsite and offsite organizations shall be established for facility staff and 

corporate management, respectively. The onsite and offsite organizations shall 

include the positions for activities affecting the safe storage and handling of spent 

nuclear fuel. 

a. Lines of authority, responsibility and communication shall be established 

and defined for the highest management levels through intermediate 

levels to and including all facility organization positions. These 

relationships shall be documented, and updated, as appropriate, in the 

form of organization charts, functional descriptions of departmental 

responsibilities and relationships, and job descriptions for key positions, 

or in equivalent forms of documentation. These requirements and the 

plant specific equivalent of those titles referred to in these Technical 

Specifications shall be documented in the FSAR. 

b. The plant manager shall be responsible for overall facility safe operation 

and shall have control over those onsite activities necessary for safe 

storage and maintenance of spent nuclear fuel. 

c. A specified corporate officer shall have corporate responsibility for the 

safe storage and handling of spent nuclear fuel and shall take any 

measures needed to ensure acceptable performance of the staff in 

operating, maintaining and providing technical support to the facility to 

ensure safe management of spent nuclear fuel. 

d. The individuals who train the CERTIFIED FUEL HANDLERS and those 

who carry out radiation protection and quality assurance functions may 

report to the appropriate onsite manager; however, they shall have 

sufficient organizational freedom to ensure their ability to perform their 

assigned functions. 

Facility Staff 

The facility staff organization shall include the following: 

a. Each duty shift shall be composed of at least one shift manager and one 

NON-CERTIFIED OPERATOR. The NON-CERTIFIED OPERATOR 

position may be filled by a CERTIFIED FUEL HANDLER. 

b. Oversight of fuel handling operations shall be provided by a CERTIFIED 

FUEL HANDLER. 

Palisades Nuclear Plant 5.0-2 Amendment No. ~. 266 
Organization 

5.2 

5.2 Organization 

5.2.2 Facility Staff ( continued) 

c. Shift crew composition may be less than the minimum requirement of 

5.2.2a. for a period of time not to exceed 2 hours in order to 

accommodate unexpected absence of on-duty shift crew members 

provided immediate action is taken to restore the shift crew composition 

to within the minimum requirements and all the following are met: 

1) No fuel movements are in progress, and 

2) No movement of loads over fuel are in progress, and 

3) No unmanned shift positions during shift turnover shall be 

permitted due to an incoming shift crew member being late or 

absent. 

d. A radiation protection technician shall be on site during the movement of 

fuel and during the movement of loads over fuel. The position may be 

vacant for not more than 2 hours, in order to provide for unexpected 

absence, provided immediate action is taken to fill the required position. 

e. At least one person qualified to stand watch in the control room 

(NON-CERTIFIED OPERATOR or CERTIFIED FUEL HANDLER) shall be 

present in the control room when nuclear fuel is stored in the spent fuel 

pool. 

f. The shift manager shall be a CERTIFIED FUEL HANDLER. 

g. (Deleted) 

Palisades Nuclear Plant 5.0-3 Amendment No. ~. 266 
5.0 ADMINISTRATIVE CONTROLS 

5.3 Facility Staff Qualifications 

Plant Staff Qualifications 

5.3 

5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications 

of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the 

Quality Assurance Program Manual (QAPM). 

5.3.2 A NRC approved training and retraining program for CERTIFIED FUEL 

HANDLERs shall be maintained. 

5.3.3 (Deleted) 

5.3.4 (Deleted) 

5.3.5 (Deleted) 

Palisades Nuclear Plant 5.0-4 Amendment No. ~. 266 
5.0 ADMINISTRATIVE CONTROLS 

5.4 Procedures 

Procedures 

5.4 

5.4.1 Written procedures shall be established, implemented, and maintained covering 

the activities referenced below: 

a. The procedures applicable to the safe storage of spent nuclear fuel 

recommended in Regulatory Guide 1.33, Revision 2, Appendix A, 

February 1978. 

b. (Deleted) 

c. Not used; 

d. All programs specified in Specification 5.5. 

Palisades Nuclear Plant 5.0-5 Amendment No. ~. 266 
Programs and Manuals 

5.5 

5.0 ADMINISTRATIVE CONTROLS 

5.5 Programs and Manuals 

The following programs shall be established, implemented, and maintained: 

5.5.1 Offsite Dose Calculation Manual (ODCM} 

a. The ODCM shall contain the methodology and parameters used in the 

calculation of offsite doses resulting from radioactive gaseous and liquid 

effluents, in the calculation of gaseous and liquid effluent monitoring 

alarm and trip setpoints, and in the conduct of the radiological 

environmental monitoring program; and 

b. The ODCM shall also contain (1) the radioactive effluent controls and 

radiological environmental monitoring activities and (2) descriptions of 

the information that should be included in the Radiological Environmental 

Operating Report, and Radioactive Effluent Release Report required by 

Specification 5.6.2 and Specification 5.6.3. 

c. Changes to ODCM: 

1. Shall be documented and records of reviews performed shall be 

retained. This documentation shall contain: 

a. Sufficient information to support the change together with 

the appropriate analyses or evaluations justifying the 

changes.and 

b. A determination that the change will maintain the level of 

radioactive effluent control required by 10 CFR 20.1302, 

40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, 

and not adversely impact the accuracy or reliability of 

effluent, dose, or setpoint calculations. 

2. Shall become effective after approval by the plant manager. 

3. Shall be submitted to the NRC in the form of a complete, legible 

copy of the entire ODCM as a part of or concurrent with the 

Radioactive Effluent Release Report for the period of the report in 

which any change to the ODCM was made. Each change shall be 

identified by markings in the margin of the affected pages, clearly 

indicating the area of the page that was changed, and shall 

indicate the date (e.g., month/year) the change was implemented. 

Palisades Nuclear Plant 5.0-6 Amendment No. 4-Qa, 266 
Programs and Manuals

5.5

5.5 Programs and Manuals

Palisades Nuclear Plant 5.0-7 Amendment No. 196, 213, 272

5.5.2 (Deleted)

5.5.3 (Deleted)

5.5.4 Radioactive Effluent Controls Program

A program shall be provided conforming with 10 CFR 50.36a for the control of 

radioactive effluents and for maintaining the doses to members of the public from 

radioactive effluents as low as reasonably achievable. The program (1) shall be 

contained in the Offsite Dose Calculation Manual (ODCM), (2) shall be 

implemented by operating procedures, and (3) shall include remedial actions to 

be taken whenever the program limits are exceeded. The program shall include 

the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous 

monitoring instrumentation including surveillance tests and setpoint 

determination in accordance with the methodology in the ODCM,

b. Limitations on the concentrations of radioactive material released in liquid 

effluents to unrestricted areas conforming to ten times the concentration 

values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402.

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous 

effluents in accordance with 10 CFR 20.1302 and with the methodology 

and parameters in the ODCM,

d. Limitation on the annual and quarterly doses or dose commitment to a 

member of the public from radioactive materials in liquid effluents 

released from each plant to unrestricted areas conforming to 10 CFR 50, 

Appendix I,

e. Limitations on the dose rate resulting from radioactive material released 

in gaseous effluents from the site to areas at or beyond the site boundary 

shall be in accordance with the following:

1. For noble gases: a dose rate ≤ 500 mrem/yr to the whole body 

and a dose rate ≤ 3000 mrem/yr to the skin, and

2. For iodine-131, iodine-133, tritium, and all radionuclides in 

particulate form with half-lives greater than 8 days: a dose rate

≤ 1500 mrem/yr to any organ; 
Programs and Manuals

5.5

5.5 Programs and Manuals

Palisades Nuclear Plant 5.0-8 Amendment No. 189, 196, 261, 

262, 263, 272

5.5.4 Radioactive Effluent Controls Program (continued)

f. Limitations on the annual and quarterly air doses resulting from noble 

gases released in gaseous effluents from each unit to areas beyond the

site boundary conforming to 10 CFR 50, Appendix I,

g. Limitations on the annual and quarterly doses to a member of the public 

from Iodine-131, Iodine-133, tritium and all radionuclides in particulate

form with half-lives greater than 8 days in gaseous effluents released 

from each plant to areas beyond the site boundary conforming to 

10 CFR 50, Appendix I,

h. Limitations on the annual doses or dose commitment to any member of 

the public, beyond the site boundary, due to releases of radioactivity and 

to radiation from uranium fuel cycle sources conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive 

Effluent Controls Program surveillance frequency.

5.5.5 (Deleted) 

5.5.6 (Deleted) 

5.5.7 (Deleted) 

5.5.8 (Deleted) 

5.5.9 (Deleted) 

5.5.10 (Deleted) 

5.5.11 (Deleted) 
Programs and Manuals

5.5

5.5 Programs and Manuals

Palisades Nuclear Plant 5.0-9 Amendment No. 261, 266, 272

5.5.12 Technical Specifications (TS) Bases Control Program

This program provides a means for processing changes to the Bases of these 

Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate 

administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval 

provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated FSAR or Bases that requires NRC 

approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the 

Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of Specification 5.5.12.b. above 

shall be reviewed and approved by the NRC prior to implementation. 

Changes to the Bases implemented without prior NRC approval shall be 

provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.13 (Deleted) 

5.5.14 (Deleted) 

5.5.15 Process Control Program

a. The Process Control Program shall contain the current formula, sampling, 

analyses, tests, and determinations to be made to ensure that the 

processing and packaging of solid radioactive wastes based on 

demonstrated processing of actual or simulated wet solid wastes will be 

accomplished in such a way as to assure compliance with 10 CFR 20, 

10 CFR 71, Federal and State regulations, and other requirements 

governing the disposal of the radioactive waste.
Programs and Manuals

5.5

5.5 Programs and Manuals

Palisades Nuclear Plant 5.0-10 Amendment No. 261, 266, 

 271, 272

5.5.15 Process Control Program (continued)

b. Changes to the Process Control Program:

1. Shall be documented and records of reviews performed shall be 

retained as required by the Quality Program. This documentation 

shall contain:

a) Sufficient information to support the change together with 

the appropriate analyses or evaluation justifying the 

change(s) and

b) A determination that the change will maintain the overall 

conformance of the solidified waste product to existing 

requirements of Federal, State, or other applicable 

regulations.

2. Shall become effective after approval by the plant manager. 

5.5.16 (Deleted) 

5.5.17 (Deleted) 
Palisades Nuclear Plant 5.0-11 Amendment No. 209, 220, 234

261, 272

Reporting Requirements

5.6

5.0 ADMINISTRATIVE CONTROLS

5.6 Reporting Requirements

The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 (Deleted)

5.6.2 Radiological Environmental Operating Report

The Radiological Environmental Operating Report covering the operation of the 

facility during the previous calendar year shall be submitted before May 15 of 

each year. The report shall include summaries, interpretations, and analysis of 

trends of the results of the radiological environmental monitoring program for the 

reporting period. The material provided shall be consistent with the objectives 

outlined in the Offsite Dose Calculation Manual and in 10 CFR 50, Appendix I, 

Sections IV.B.2, IV.B.3, and IV.C.

5.6.3 Radioactive Effluent Release Report

The Radioactive Effluent Release Report covering operation of the facility in the 

previous year shall be submitted prior to May 1 of each year in accordance with 

10 CFR 50.36a. The report shall include a summary of the quantities of 

radioactive liquid and gaseous effluents and solid waste released from the 

facility. The material provided shall be consistent with the objectives outlined in 

the Offsite Dose Calculation Manual and Process Control Program, and shall be 

in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1. 

5.6.4 (Deleted) 

5.6.5 (Deleted) 

5.6.6 (Deleted)

5.6.7 (Deleted)

5.6.8 (Deleted)
Palisades Nuclear Plant 5.0-12 Amendment No. 196, 272

High Radiation Area 

5.7

5.0 ADMINISTRATIVE CONTROLS

5.7 High Radiation Area

As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied 

to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 

CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 

Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation

a. Each entryway to such an area shall be barricaded and conspicuously 

posted as a high radiation area. Such barricades may be opened as 

necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means 

of Radiation Work Permit (RWP), or equivalent, that includes 

specification of radiation dose rates in the immediate work area(s) and 

other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel 

continuously escorted by such individuals may be exempted from the 

requirement for an RWP, or equivalent, while performing their assigned 

duties, provided that they are otherwise following plant radiation 

protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation 

dose rates in the area; or

2. A radiation monitoring device that continuously integrates the 

radiation dose rates in the area and alarms when the device’s 

dose alarm setpoint is reached, with an appropriate alarm 

setpoint, or

3. A radiation monitoring device that continuously transmits dose 

rate and cumulative dose information to a remote receiver 

monitored by radiation protection personnel responsible for 

controlling personnel radiation exposure within the area, or
High Radiation Area

5.7

5.7 High Radiation Area 

Palisades Nuclear Plant 5.0-13 Amendment No. 196, 272

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 

Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation (continued)

4. A self-reading dosimeter (e.g., pocket ionization chamber or 

electronic dosimeter) and,

(i) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, of an individual qualified in 

radiation protection procedures, equipped with a radiation 

monitoring device that continuously displays radiation dose 

rates in the area, and who is responsible for controlling 

personnel exposure within the area, or

(ii) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, by means of closed circuit 

television, of personnel qualified in radiation protection 

procedures, responsible for controlling personnel radiation 

exposure in the area, and with the means to communicate 

with individuals in the area who are covered by such

surveillance.

e. Except for individuals qualified in radiation protection procedures, or 

personnel continuously escorted by such individuals, entry into such 

areas shall be made only after dose rates in the area have been 

determined and entry personnel are knowledgeable of them. These 

continuously escorted personnel will receive a pre-job briefing prior to 

entry into such areas. This dose rate determination, knowledge, and prejob briefing does not require documentation prior to initial entry.
High Radiation Area

5.7

5.7 High Radiation Area

Palisades Nuclear Plant 5.0-14 Amendment No. 196, 266, 272

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 

Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or 

from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high 

radiation area and shall be provided with a locked or continuously 

guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the 

administrative control of the shift manager, radiation protection 

manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of 

personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means 

of an RWP or equivalent that includes specification of radiation dose rates 

in the immediate work area(s) and other appropriate radiation protection 

equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted 

from the requirement for an RWP, or equivalent, while performing 

radiation surveys in such areas, provided that they are otherwise 

following plant radiation protection procedures for entry to, exit from, and 

work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the 

radiation rates in the area and alarms when the device’s dose 

alarm setpoint is reached, with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits dose 

rate and cumulative dose information to a remote receiver 

monitored by radiation protection personnel responsible for 

controlling personnel radiation exposure within the area, and with 

the means to communicate with and control every individual in the 

area, or
High Radiation Area

5.7

5.7 High Radiation Area

Palisades Nuclear Plant 5.0-15 Amendment No. 196, 272

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 

Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or 

from any Surface Penetrated by the Radiation (continued)

3. A self-reading dosimeter (e.g., pocket ionization chamber or 

electronic dosimeter) and,

(i) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, of an individual qualified in 

radiation protection procedures, equipped with a radiation 

monitoring device that continuously displays radiation dose 

rates in the area; and who is responsible for controlling 

personnel exposure within the area, or

(ii) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, by means of closed circuit 

television, of personnel qualified in radiation protection

procedures, responsible for controlling personnel radiation 

exposure in the area, and with the means to communicate

with and control every individual in the area.

4. In those cases where options (2) and (3), above, are impractical 

or determined to be inconsistent with the “As Low As is 

Reasonably Achievable” principle, a radiation monitoring device 

that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or 

personnel continuously escorted by such individuals, entry into such 

areas shall be made only after dose rates in the area have been 

determined and entry personnel are knowledgeable of them. These 

continuously escorted personnel will receive a pre-job briefing prior to 

entry into such areas. This dose rate determination, knowledge, and prejob briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure 

exists for the purpose of locking and where no enclosure can reasonably 

be constructed around the individual area need not be controlled by a 

locked door or gate, nor continuously guarded, but shall be barricaded, 

conspicuously posted, and a clearly visible flashing light shall be 

activated at the area as a warning device.
PALISADES PLANT 

RENEWED FACILITY OPERATING LICENSE DPR-20 

APPENDIX B 

 ENVIRONMENTAL PROTECTION PLAN 

(NON-RADIOLOGICAL)

Amendment No. 176, 272 
PALISADES PLANT

ENVIRONMENTAL PROTECTION PLAN

(NON-RADIOLOGICAL)

TABLE OF CONTENTS

Section Page

1.0 Objectives of the Environmental Protection Plan ..................................... 1-1 

2.0 Environmental Protection Issues.............................................................. 2-1 

2.1 Aquatic Issues.......................................................................................... 2-1 

2.2 Terrestrial Issues...................................................................................... 2-1 

3.0 Consistency Requirements ...................................................................... 3-1 

3.1 Facility Design and Operation .................................................................. 3-1 

3.2 Reporting Related to the NPDES Permits and State Certification............ 3-2 

3.3 Changes Required for Compliance with Other Environmental

Regulations .............................................................................................. 3-3 

4.0 Environmental Conditions ........................................................................ 4-1 

4.1 Unusual or Important Environmental Events............................................ 4-1 

4.2 Environmental Monitoring......................................................................... 4-1 

5.0 Administrative Procedures ....................................................................... 5-1 

5.1 Review and Audit ..................................................................................... 5-1 

5.2 Records Retention ................................................................................... 5-1 

5.3 Changes in Environmental Protection Plan.............................................. 5-2 

5.4 Facility Reporting Requirements .............................................................. 5-2 

Amendment No. 63, 272 

May 13, 2022
1.0 Objectives of the Environmental Protection Plan

The Environmental Protection Plan (EPP) is to provide for protection of 

environmental values during handling and storage of spent fuel and maintenance

of the nuclear facility. The principal objectives of the EPP are as follows:

(1) Verify that the facility is maintained in an environmentally acceptable

manner, as established by the FES and other NRC environmental impact

assessments.

(2) Coordinate NRC requirements and maintain consistency with other

Federal, State and local requirements for environmental protection.

(3) Keep NRC informed of the environmental effects of handling and storage

of spent fuel and maintenance of the facility and of actions taken to control

those effects.

Environmental concerns identified in the FES which relate to water quality 

matters are regulated by way of the licensee's NPDES permit.

1-1

Amendment No. 272 

May 13, 2022 
2.0 Environmental Protection Issues

In the final addendum to the FES-OL dated February 1978 the staff considered 

the environmental impacts associated with the operation of the Palisades Plant. 

Certain environmental issues were identified which required study or license 

conditions to resolve environmental concerns and to assure adequate protection 

of the environment.

2.1 Aquatic Issues

Specific aquatic issues raised by the staff in the FES-OL were:

The need for aquatic monitoring programs to confirm that thermal mixing occurs 

as predicted, that chlorine releases are controlled within those discharge 

concentrations evaluated, and that effects on aquatic biota and water quality due 

to facility operation are no greater than predicted.

Aquatic issues are addressed by the effluent limitations, and monitoring 

requirements are contained in the effective NPDES permit issued by the State of 

Michigan, Department of Natural Resources. The NRC will rely on this agency 

for regulation of matters involving water quality and aquatic biota.

2.2 Terrestrial Issues

1. Potential impacts on the terrestrial environment associated with drift from

the mechanical draft cooling towers. (FES-OL addendum Section 6.3)

2-1

Amendment No. 272 

May 13, 2022 
• 

• 

• 

2. Potential increase in fogging associated with operation of the mechanical draft 

cooling towers. (FES-OL addendum Section 6.3) . 

3. The need for controlled used of herbicides on transmission rights-of-way. 

(FES-OL addendum Sections 6.3.3) 

l'IRC requirements with regard to the 3 terrestrial issues are specified in Subsection 4.2 

of this EPP . 

2-2 

January 22, 1981 
3.0 Consistency Requirements

3.1 Facility Design and Operation

The licensee may make changes in facility design or operation or perform tests

or experiments affecting the environment provided such changes, tests or

experiments do not involve an unreviewed environmental question, and do not

involve a change in the Environmental Protection Plan. Changes in facility

design or operation or performance of tests or experiments which do not affect

the environment are not subject to the requirements of this EPP. Activities

governed by Section 3.3 are not subject to the requirements of this section.

Before engaging in additional construction or operational activities which may

affect the environment, the licensee shall prepare and record an environmental

evaluation of such activity. When the evaluation indicates that such activity

involves an unreviewed environmental question, the licensee shall provide a 

written evaluation of such activities and obtain prior approval from the Director,

Office of Nuclear Reactor Regulation. When such activity involves a change in 

the Environmental Protection Plan, such activity and change to the 

Environmental Protection Plan may be implemented only in accordance with an 

appropriate license amendment as set forth in Section 5.3.

A proposed change, test or experiment shall be deemed to involve an 

unreviewed environmental question if it concerns (1) a matter which may result in 

a significant increase in any adverse environmental impact previously evaluated 

in the final environmental statement (FES) as modified by staff's testimony to the 

Atomic Safety and Licensing Board, supplements to the FES, environmental

impact appraisals, or in any decisions of the Atomic Safety and Licensing 

Board; or (2) a significant change in effluents [in accordance with 10 CFR Part 

51.5(b)(2)] or (3) a matter not previously reviewed and evaluated in the 

documents specified in (1) of this Subsection, which may have a significant

adverse environmental impact.

3-1

Amendment No. 272 

May 13, 2022 
The licensee shall maintain records of changes in facility design or operation and 

of tests and experiments carried out pursuant to this Subsection. These records 

shall include a written evaluation which provide bases for the determination that 

the change, test, or experiment does not involve an unreviewed environmental 

question nor constitute a decrease in the effectiveness of this EPP to meet the 

objectives specified in Section 1.0. The licensee shall include as part of his 

Annual Environmental Operating Report (per Subsection 5.4.1) brief descriptions, 

analyses, interpretations, and evaluations of such changes, tests and 

experiments.

3.2 Reporting Related to the NPDES Permits and State Certifications

Violations of the NPDES Permit or the State certification (pursuant to Section 401 

of the Clean Mater Act) shall be reported to the NRC by submittal of copies of the 

reports required by the NPDES Permit or certification.

Changes and additions to the NPDES Permit or the State certification shall be 

reported to the NRC within 30 days following the date the change is approved. If 

a permit or certification, in part or in its entirety, is appealed and stayed, the NRC 

shall be notified within 30 days following the date the stay is granted.

The NRC shall be notified of changes to the effective NPDES Permit proposed 

by the licensee by providing NRC with a copy of the proposed change at the 

same time it is submitted to the permitting agency. The notification of a licenseeinitiated change shall include a copy of the requested revision submitted to the 

permitting agency. The licensee shall provide the NRC a copy of the application 

for renewal of the NPDES permit at the same time the application is submitted to 

the permitting agency.

3-2

Amendment No. 272 

May 13, 2022 
3.3 Changes Required for Compliance with Other Environmental Regulations

Changes in facility design or operation and performance of tests or experiments 

which are required to achieve compliance with other Federal, State, or local 

environmental regulations are not subject to the requirements of Section 3.1.

3-3

Amendment No. 272 

May 13, 2022 
4.0 Environmental Conditions

4.1 Unusual or Important Environmental Events

Any occurrence of an unusual or important event that indicates or could result in 

significant environmental impact causally related to the handling and storage of 

spent fuel and maintenance of the facility shall be recorded and promptly 

reported to the NRC within 24 hours by telephone, telegraph, or facsimile 

transmissions followed by a written report per Subsection 5.4.2. The following 

are examples: excessive bird impaction events, onsite plant or animal disease 

outbreaks, mortality or unusual occurrence of any species protected by the 

Endangered Species Act of 1973, fish kills, increase in nuisance organisms or 

conditions and unanticipated or emergency discharge of waste water or chemical 

substances.

No routine monitoring programs are required to implement this condition.

4.2 Environmental Monitoring

4.2.1 Meteorological Monitoring

A meteorological monitoring program shall be conducted in the vicinity of the

plant site for at least two years after conversion to cooling towers to document 

effects of cooling tower operation on meteorological variables. Data on the 

following meteorological variables shall be obtained from the station network 

shown in Figure 4.2.1: precipitation, temperature, humidity, solar radiation, 

downcoming radiation, visibility, wind direction and wind speed. In addition, 

studies shall be conducted for at least two years to measure affects of cooling 

tower drift on vegetation by associated salt deposition, icing or other causes.

4-1

Amendment No. 272 

May 13, 2022 
• 

• 

• 

(a) 

(b) 

(c) 

(d) 

(e) 

(f) 

(g) 

Observations shall be made of a series of sample vegetation plots, and chemical 

analyses shall be made of representative samples of vegetation, soil and 

collected moisture to establish relative amounts of drift at various locations and 

influences on plant life. The incidence of icing and fogging on nearby 

transportation arteries shall be determined. Noise measurements shall be taken 

with and without the cooling tower in operation at different locations on site and 

around the surrounding areas. The study program to assess the meteorological 

and terrestrial effects of cooling tower operation onsite and offsite shall be 

carried out as follows: 

METEOROLOGICAL STUDY 

Sample Frequency Objective 

Precipitation Continuously To determine if the c.t.* 

influence natural precipitation 

processes. 

Temperature Continuously To establish c.t.* plume 

influences on temperature if 

any. 

Relative Humidity Continuously To determine if the c.t.* plume 

produces an increase in R.H. 

Total Solar Radiation Continuously To determine if the c.t.* plume 

inhibit total solar radiation. 

Total Solar Plus Continuously To determine the presence 

Atmosphere Radiation of nocturnal c.t.* plume. 

Visibility Continuously To detect the presence of fog. 

Wind Direction Continuously To determine the direction of 

movement to the c.t.* plume 

and alterations in wind patterns. 

*c.t. - cooling towers 

4-2 

January 22, 1981 
• 

• 

• 

METEOROLOGICAL STUDY (Cont'd) 

Sample Frequency Objective 

(h) Wind Speed Continuously To determine if the c.t.* plume 

affect local wind speeds. 

(i) Icing During winter To determine if c.t.* plume 

months creates icing problems of 

nearby highways and roads. 

DRIFT STUDY 

(a) Precipitation Monthly To establish pattern and 

and Analyzed for rate of drift deposited 

S04 and Ca ions. 

(b) Analysis of Survey 3 times To determine if c.t.* drift 

Vegetation al per year (spring, is altering the vegetational 

Composition summer, fall) composition. 

(c) Vegetational Chemical Yearly To determine if drift 

Analysis deposited elements are 

concentrating in vegetation . 

(d) Soil Chemical Yearly To determine if drift 

Analysis deposited elements are 

concentrating in soils. 

(e) Icing Winter months To determine if c.t.* drift (ice) is 

physically damaging to 

vegetation. 

4.2.2 Herbicide Application 

The use of herbicides within the transmission corridor rights-of-way shall 

conform to the approved use of selected herbicides as registered by the 

Environmental Protection Agency and approved by State authorities and 

applied as directed by said authorities. 

*c.t. - cooling towers 

4-3 

January 22, 1981 
A DRAV\dNG BELONGS HERE 

• 

• 

• 4-4 

January 22, 1981 
• 

• 

• 

Records s',,all be maintained in the appropriate division office concerning 

herbicide . use. Such records shall include the following in" infotmatio.n: . . 

commercial and chemical names of materials used; concentration of active 

material in formulations diluted for field use; diluting substances other than 

water; rates of application; method and frequency of application; location; and 

the date of application. __ Such records shall be maintained for a period of 5 

years and be made readily available to the NRC upon request. There shall 

be no routine reporting requirement associated with this condition . 

4-5 

January 22, 1981 
5.0 Administrative Procedures

5.1 Review and Audit

The licensee shall provide for review and audit of compliance with the 

Environmental Protection Plan. The audits shall be conducted independently 

of the individual or groups responsible for performing the specific activity. A 

description of the organization structure utilized to achieve the independent 

review and audit function and results of the audit activities shall be maintained 

and made available for inspection.

5.2 Records Retention

Records and logs relative to the environmental aspects of previous plant 

operation and the handling and storage of spent fuel and maintenance of the

facility shall be made and retained in a manner convenient for review and 

inspection. These records and logs shall be made available to NRC on 

request.

Records of modifications to facility structures, systems and components 

determined to potentially affect the continued protection of the environment 

shall be retained for the life of the facility. All other records, data and logs 

relating to this EPP shall be retained for five years or, where applicable, in 

accordance with the requirements of other agencies.

5-1

Amendment No. 272 

May 13, 2022 
5.3 Changes in Environmental Protection Plan

Request for change in the Environmental Protection Plan shall include an 

assessment of the environmental impact of the proposed change and a 

supporting justification. Implementation of such changes in the EPP shall not 

commence prior to NRC approval of the proposed changes in the form of a 

license amendment incorporating the appropriate revision to the 

Environmental Protection Plan.

5.4 Facility Reporting Requirements

5.4.1 Routine Reports

An Annual Environmental Operating Report describing implementation of this 

EPP for the previous year shall be submitted to the NRC prior to May 1 of 

each year. The initial report shall be submitted prior to May 1 of the year 

following issuance of the operating license. The period of the first report shall 

begin with the date of issuance of the operating license.

The report shall include summaries and analyses of the results of the 

environmental protection activities required by Subsection 4.2 of this 

Environmental Protection Plan for the report period, including a comparison 

with preoperational studies, operational controls (as appropriate), and 

previous nonradiological environmental monitoring reports, and an 

assessment of the observed impacts of the facility operation on the 

environment. If harmful effects or evidence of trends towards irreversible 

damage to the environment are observed, the licensee shall provide a 

detailed analysis of the data and a proposed course of action to alleviate the 

problem.

5-2

Amendment No. 272 

May 13, 2022 
The Annual Environmental Operating Report shall also include:

(a) A list of EPP noncompliances and the corrective actions taken to remedy them.

(b) A list of all changes in facility design or operation, tests, and experiments made in

accordance with Subsection 3.1 which involved a potentially significant

unreviewed environmental issue.

(c) A list of nonroutine reports submitted in accordance with Subsection 5.4.2.

In the event that some results are not available by the report due date, the report shall 

be submitted noting and explaining the missing results. The missing data shall be 

submitted as soon as possible in a supplementary report.

5-3

Amendment No. 272 

May 13, 2022 
5.4.2 Nonroutine Reports

A written report shall be submitted to the NRC within 30 days of occurrence of 

nonroutine event. The report shall (a) describe, analyze, and evaluate the 

event, including extent and magnitude of the impact and facility operating 

characteristics, (b) describe the probable cause of the event, (c) indicate the 

action taken to correct the reported event, (d) indicate the corrective action 

taken to preclude repetition of the event and to prevent similar occurrences 

involving similar components or systems, and (e) indicate the agencies 

notified and their preliminary responses.

Events reportable under this subsection which also require reports to other 

Federal, State or local agencies shall be reported in accordance with those 

reporting requirements in lieu of the requirements of this subsection. The 

NRC shall be provided a copy of such report at the time it is submitted to the 

other agency.

5-4

Amendment No. 272 

May 13, 2022