NUREG-1745

Standard Format and 

Content for Technical 

Specifications for 

10 CFR Part 72 Cask 

Certificates of Compliance 

U.S. Nuclear Regulatory Commission + ,0 . 

Office of Nuclear Material Safety and Safeguards 

Washington, DC 20555-0001
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NUREG-1745

Standard Format and 

Content for Technical 

Specifications for 

10 CFR Part 72 Cask 

Certificates of Compliance 

Manuscript Completed: May 2001 

Date Published: June 2001 

Spent Fuel Project Office 

Office of Nuclear Material Safety and Safeguards 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001
ABSTRACT

The Standard Technical Specifications (STS) for dry cask storage are intended to be used by 

potential 10 CFR Part 72 Certificate Holders in developing a set of clear and consistent 

technical specifications for their dry cask storage applications. 

The NRC believes that these Dry Cask STS in this NUREG will assure the overall safety goals 

for dry cask storage are met, including maintaining subcriticality, controlling radiation dose to 

the workers and the public, assuring fuel retrievability, and maintaining the confinement 

barriers. This effort has removed the unnecessary detail from the technical specifications, 

moved the less significant requirements to administrative programs, made the requirements 

less prescriptive and maintained consistency with the site specific requirements contained in 10 

CFR 72.44. Although these STS were developed for Certificate Holders, the format and level of 

detail presented in this set of STS can easily be translated to technical specifications for 

site-specific licensees.

iii
PAPERWORK REDUCTION ACT STATEMENT

The information collections contained in this NUREG are covered by the requirements of 10 

CFR Parts 50, 72 and 73, which were approved by the Office of Management and Budget, 

approval numbers 3150-0011, 3150-0132 and 3150-0002. 

PUBLIC PROTECTION NOTIFICATION 

If a means used to impose an information collection does not display a currently valid OMB 

control number, the NRC may not conduct or sponsor, and a person is not required to respond 

to, the information collection.

iv
TABLE OF CONTENTS 

PAGE 

A BSTRA CT ..... ......................................................... iii 

ACKNOW LEDGMENT ..................................................... vii 

CERTIFICATE OF COMPLIANCE FOR DRY CASK STORAGE SYSTEMS ............. 1 

APPENDIX TO CERTIFICATE OF COMPLIANCE No. XXXX ....................... 5

V
ACKNOWLEDGMENT

The authors wish to acknowledge the valuable contribution of the members of the Standard 

Technical Specification Task Force consisting of Christopher Bajwa, Kenneth Erwin, 

Adelaide Giantelli, James Randall Hall, Geoffrey Hornseth, Henry Lee, Chester Poslusny, and 

Bernard White, IV. Without their significant contribution and support this document would not 

have been possible.

vii
NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION 

(3-1999) 

10 CFR 72 CERTIFICATE OF COMPLIANCE 

FOR SPENT FUEL STORAGE CASKS Page 1 of 4 

The U.S. Nuclear Regulatory Commission is issuing this Certificate of Compliance pursuant to Title 10 of the Code of Federal Regulations, 

Part 72, "Licensing Requirements for Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste" (10 CFR Part 72). 

This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the 

applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the Final Safety Analysis Report (FSAR) of the cask 

design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below. 

Certificate No. Effective Date Expiration Date Docket Number Amendment No. Amendment Date Package Identification No. 

XXXX XX/XX/XX XX/XX/XX 72-XXXX 0 USA/72-XXXX 

Issued To: (Name/Address) 

Safety Analysis Report Title 

CONDITIONS 

This certificate is conditioned upon fulfilling the requirements of 10 CFR Part 72, as applicable, the 

attached Appendix (Technical Specifications), and the conditions specified below: 

1. CASK 

a. Model No. XXXXX Cask Systern 

The XXXXX Cask System (the cask) consists of the following components: (1) a canister which 

contains the fuel; (2) a storage overpack (XXXXXX), which contains the canister during storage; 

and (3) a transfer cask (YYYYYY), which contains the canister during ioading, unloading, and 

transfer operations. The cask stores up to XX fuel assemblies. 

b. Description 

The XXXXXX Cask System is certified as described in the Safety Analysis Report (SAR) and in 

NRC's Safety Evaluation Report (SER) accompanying the Certificate of Compliance. The cask 

comprises three discrete components: the canister, the YYYYY transfer cask, and the XXXXX 

storage overpack.

I
NRC FORM 651A U.S. NUCLEAR REGULATORY COMMISSION 

(3-1999) 

10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. XXXX 

FOR SPENT FUEL STORAGE CASKS 

Supplemental Sheet Page 2 of 4 

1 . b. Description (continued) 

[The canister is the confinement system for the stored fuel. It is a welded, cylindrical container 

with a honeycombed fuel basket, a baseplate, a lid, a closure ring, and the canister shell. It is 

made entirely of stainless steel except for the neutron absorbers and aluminum heat conduction 

elements. The canister shell, baseplate, lid, vent and drain port cover plates, and closure ring are 

the main confinement boundary components. The honeycombed basket, which is equipped with 

Boral neutron absorbers, provides criticality control. The canister holds up to XX PWR fuel 

assemblies that must be intact. 

The YYYY transfer cask provides shielding and structural protection of the canister during loading, 

unloading, and movement of the canister from the spent fuel pool to the storage overpack. The 

transfer cask is a multi-walled (carbon steel/lead/carbon steel) cylindrical vessel with a water 

jacket attached to the exterior. The maximum weight of a loaded transfer cask during any loading, 

unloading, or transfer operation is XXX tons. 

The XXXX storage overpack provides shielding and structural protection of the canister during 

storage. The overpack is a heavy-walled, steel and concrete, cylindrical vessel. Its side wall 

consists of plain concrete that is enclosed between inner and outer carbon steel shells. The 

overpack has four air inlets at the bottom and-four air outlets at the top to allow air to circulate 

naturally through the cavity to coot the canister inside. The inner shell has channels attached to 

its interior surface to guide the canister during insertion and removal, provide a flexible medium to 

absorb impact loads, and allow cooling air to circulate through the overpack. A loaded canister is 

stored within the XXXX storage overpack in a vertical orientation.] 

2. OPERATING PROCEDURES 

Written operating procedures shall-be prepared for cask handling, loading, unloading, movement, 

surveillance, and maintenance. The users site-specif ic written operating procedures shall be 

consistent with the technical basis described in Chapter 8 of the SAR.

2
11

3

NRC FORM 651A U.S. NUCLEAR REGULATORY COMMISSION 

(3-1999) 

10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. XXXX 

FOR SPENT FUEL STORAGE CASKS 

Supplemental Sheet Page 3 of 4 

3. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 

Written cask acceptance tests and maintenance program shall be prepared consistent with the 

technical basis described in Chapter 9 of the SAR. 

The heat transfer characteristics of the cask system will be recorded by temperature measurements 

for the first Spent Fuel Storage Canister (SFSC) System placed into service with a heat load equal to 

or greater than XX kW. An analysis shall be performed that demonstrates the temperature 

measurements validate the analytic methods and predicted thermal behavior described in Chapter 4 

of the SAR. 

Validation tests shall be performed for each subsequent cask system that has a heat load that 

exceeds a previously validated heat load by more than X kW. (e.g., if the initial test was conducted at 

XX kW, then no additional testing is needed until the heat load exceeds XX kW). No additional 

testing is required for a system after it has been tested at a heat load equal to or greater than XX kW. 

Letter reports summarizing the-results of each validation test shall be submitted to the NRC in 

accordance with 10 CFR 72.4. Cask users may satisfy these requirements by referencing validation 

test reports submitted tothe NRC by other cask users. 

4. QUALITY ASSURANCE 

Activities in the areas of design, purchase, fabrication, assembly, inspection, testing, operation, maintenance, repair, modification of structures, systems and'components, and decommissioning that 

are important to safety shall b~e conductedin accordance with a Commission-approved quality 

assurance program which satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and 

which is established, maintained, and executed with regard to the cask system. 

5. HEAVY LOADS REQUIREMENTS 

Each lift of a canister, a YY'Y transfer cask, or a XXXX overpack must be made in accordance with 

the existing heavy loads requirements and procedures of the licensed facility at which the lift is made. 

A plant-specific safety review (under 10 CFR 50.59 or 10 CFR 72.48,if applicable) is required to show 

operational compliance with existing plant-specific heavy loads requirements. Lifting operations outside of structures governed by 10 CFR Part 50 must be in accordance with Section 4.4 (Cask Transfer Operations) of the Appendix to this certificate. 

6. APPROVED CONTENTS 

Contents of the XXXX Cask System must meet the fuel description as provided for in the Appendix to 

this certificate. 

7. DESIGN FEATURES 

Features or characteristics for the site, cask, or ancillary equipment must be in accordance with the 

Appendix to this certificate.
NRC FORM 651A U.S. NUCLEAR REGULATORY COMMISSION 

(3-1999) 

10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. XXXX 

FOR SPENT FUEL STORAGE CASKS 

Supplemental Sheet Page 4 of 4 

8. PRE-OPERATIONAL TESTING AND TRAINING EXERCISE 

A dry run training exercise of the loading, closure, handling, unloading, and transfer of the 

Cask System shall be conducted by the licensee prior to the first use of the system to load 

spent fuel assemblies. The training exercise shall not be conducted with spent fuel in the 

canister. The dry run may be performed in an alternate step sequence from the actual 

procedures, but all steps must be performed. The dry run shall include, but is not limited to 

the following: 

a. [Each applicant shall list the procedures important to its design.] 

9. CHANGES TO THE CERTIFICATE OF COMPLIANCE 

The holder of this certificate who desires to make changes to the certificate, which includes the 

Appendix (Technical Specifications) shall submit an application for amendment of the certificate. 

10. AUTHORIZATION 

The XXXX Cask System, which is authorized by this certificate, is hereby approved for general use by 

holders of 10 CFR Part 50 licenses for nuclear reactors at reactor sites under the general license 

issued pursuant to 10 CFR 72.210, subject to the conditions specified by 10 CFR 72.212, and the 

attached Appendix. 

FOR THE U. S. NUCLEAR REGULATORY COMMISSION 

E. William Brach, Director 

Spent Fuel 'Project Office 

Office of Nuclear Material Safety 

and Safeguards 

Attachment: Appendix to Certificate of Compliance No. XXXX

4
APPENDIX TO 

CERTIFICATE OF COMPLIANCE No. XXXX 

STANDARDIZED TECHNICAL SPECIFICATIONS 

FOR THE NRC SAMPLE STORAGE CASK

5
TABLE OF CONTENTS 

1.0 USE AND APPLICATION ................................................ 1 

1.1 D efinitions ...................................................... 1 

1.2 Logical Connectors ............................................... 4 

1.3 Com pletion Tim es ................................................ 7 

1.4 Frequency .................................................... 11 

2.0 APPROVED CONTENTS ............................................ 14 

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ............... 15 

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ...................... 16 

3.1 Fuel Integrity ................................................... 17 

3.1.1 Fuel Integrity During Drying ................................ 17 

3.1.2 Fuel Integrity During Backfill and Transfer ..................... 19 

3.1.3 SFSC Heat Removal System ............................... 21 

3.2 Cask Integrity .................................................. 23 

3.2.1 Cask Interseal Pressure ................................... 23 

3.3 Cask Criticality Control Program .................................... 25 

3.3.1 Dissolved Boron Concentration .............................. 25 

3.3.2 CANISTER Water Temperature ............................. 27 

4.0 DESIGN FEATURES ................................................ 29 

4.1 Design Features Significant to Safety ............................. 29 

4.1.1 Criticality Control ................................... 29 

4.1.2 Materials ......................................... 29 

4.2 Codes and Standards ........................................ 29 

4.2.1 Alternatives to Codes, Standards, and Criteria ................. 29 

4.2.2 Construction/Fabrication Alternatives to Codes, 

Standards, and Criteria .............................. 30 

4.3 Structural Performance ........................................ 30 

4.3.1 Earthquake Loads ...................................... 30 

4.3.2 Design G-loads ......................................... 30 

4.4 Cask Handling/CANISTER Transfer Facility ........................ 30 

5.0 ADMINISTRATIVE CONTROLS ....................................... 31 

5.1 Administrative Programs ........................................ 31 

5.1.1 Radioactive Effluent Control Program ....................... 31 

5.1.2 Cask Loading, Unloading, and Preparation Program ............. 31 

5.1.3 ISFSI Operations Program ................................ 32
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. [Example definitions are given and changes or additional 

definitions such as DAMAGED FUEL or FUEL DEBRIS may be needed to be consistent with a 

particular design.]

Term 

ACTIONS

[CANISTER

INTACT FUEL ASSEMBLY 

LOADING OPERATIONS

Definition 

ACTIONS shall be that part of a Specification that prescribes 

Required Actions to be taken under designated Conditions within 

specified Completion Times. 

The CANISTER is the sealed SPENT NUCLEAR FUEL container 

which consists of a basket contained in a cylindrical shell which is 

welded to a baseplate, lid with welded port cover plates, and 

closure ring. The CANISTER provides the confinement boundary 

for the contained radioactive materials. 

INTACT FUEL ASSEMBLY is a fuel assembly without known or 

suspected cladding defects greater than a pinhole leak or a 

hairline crack and which can be handled by normal means. A fuel 

assembly shall not be classified as an INTACT FUEL ASSEMBLY 

unless solid Zircaloy or stainless steel rods are used to replace 

missing fuel rods and which displace an amount of water equal to 

that displaced by the original fuel rod(s). 

LOADING OPERATIONS include all licensed activities on an 

OVERPACK or TRANSFER CASK while it is being loaded with 

fuel assemblies. LOADING OPERATIONS begin when the first 

fuel assembly is placed in the CANISTER and end when the 

OVERPACK or TRANSFER CASK is suspended from or secured 

on the transporter. LOADING OPERATIONS does not include 

CANISTER transfer between the TRANSFER CASK and the 

OVERPACK.

(continued)

Page 1 of 32
Definitions 

1.1 1.1 Definitions (continued)

OPERABLE/OPERABILITY 

OVERPACK 

SPENT FUEL STORAGE 

CASKS (SFSCs) 

SPENT NUCLEAR FUEL 

[STORAGE OPERATIONS 

TRANSFER CASK

A system, component, or device shall beOPERABLE or have 

OPERABILITY when it is capable of performing its specified 

safety function(s) and when all necessary attendant 

instrumentation, controls, normal or emergency electrical power, 

and other auxiliary equipment that are required for the system, 

component, or device to perform its specified safety function(s) 

are also capable of performing their related support function(s). 

OVERPACK is the cask which receives and contains the sealed 

CANISTER for interim storage in the independent spent fuel 

storage instillation (ISFSI). It provides gamma and neutron 

shielding, and provides for ventilated air flow to promote heat 

transfer from the CANISTER to the environs. The OVERPACK 

does not include the TRANSFER CASK. 

SFSCs are containers approved for the storage of 

spent fuel assemblies at the ISFSI. The [XXXX] SFSC System 

consists of the OVERPACK and its integral CANISTER.] 

SPENT NUCLEAR FUEL means fuel that has been withdrawn 

from a nuclear reactor following irradiation, has undergone at 

least one year's decay since being used as a source of energy in 

a power reactor and has not been chemically separated into its 

constituent elements by reprocessing. SPENT NUCLEAR FUEL 

includes the special nuclear material, byproduct material, source 

material, and other radioactive materials associated with fuel 

assemblies. 

STORAGE OPERATIONS include all licensed activities that are 

performed at the ISFSI while an SFSC containing spent fuel is 

sitting on a storage pad within the ISFSI perimeter. STORAGE 

OPERATIONS does not include CANISTER transfer between the 

TRANSFER CASK and the OVERPACK. 

TRANSFER CASKs are containers designed to contain the 

CANISTER during and after loading of spent fuel assemblies and 

to transfer the CANISTER to or from the OVERPACK.

(continued)

Page 2 of 32
Definitions 

1.1 

1.1 Definitions (continued) 

TRANSPORT OPERATIONSTRANSPORT OPERATIONS include all licensed activities 

performed on an OVERPACK or TRANSFER CASK loaded with 

one or more fuel assemblies when it is being moved to and from 

the ISFSI. TRANSPORT OPERATIONS begin when the 

OVERPACK or TRANSFER CASK is first suspended from or 

secured on the transporter and end when the OVERPACK or 

TRANSFER CASK is at its destination and no longer secured on 

or suspended from the transporter. TRANSPORT OPERATIONS 

include transfer of the CANISTER between the OVERPACK and 

the TRANSFER CASK. 

UNLOADING OPERATIONS UNLOADING OPERATIONS include all licensed activities on an 

SFSC to be unloaded of the contained fuel assemblies. 

UNLOADING OPERATIONS begin when the OVERPACK or 

TRANSFER CASK is no longer suspended from or secured on the 

transporter and end when the last fuel assembly is removed from 

the SFSC. UNLOADING OPERATIONS do not include 

CANISTER transfer between the TRANSFER CASK and the 

OVERPACK.]

Page 3 of 32
Logical Connectors 

1.2

1.0 USE AND APPLICATION

1.2 Logical Connectors 

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

connectors. 

Logical connectors are used in Technical Specifications (TS) to 

discriminate between, and yet connect, discrete Conditions, Required 

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

logical connectors that appear in TS are AND and OR. The physical 

arrangement of these connectors constitutes logical conventions with 

specific meanings. 

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

levels are identified by the placement (or nesting) of the logical 

connectors and by the number assigned to each Required Action. The 

first level of logic is identified by the first digit of the number assigned to a 

Required Action and the placement of the logical connector in the first 

level of nesting (i.e., left justified with the number of the Required Action). 

The successive levels of logic are identified by additional digits of the 

Required Action number and by successive indentions of the logical 

connectors. 

When logical connectors are used to state a Condition, Completion Time, 

Surveillance, or Frequency, only the first level of logic is used, and the 

logical connector is left justified with the statement of the Condition, 

Completion Time, Surveillance, or Frequency. 

(continued)

Page 4 of 32
Logical Connectors 

1.2 

1.2 Logical Connectors (continued)

EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION 

TIME 

A. LCO not A.1 Verify... 

met. 

AND 

A.2 Restore... 

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

in Condition A, both Required Actions A.1 and A.2 must be completed.

(continued)

Page 5 of 32
Logical Connectors 

1.2 

1.2 Logical Connectors (continued)

EXAMPLES 

(continued)

EXAMPLE 1.2-2

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION 

TIME 

A. LCO not A.1 Stop ... 

met. 

OR 

A.2.1 Verify... 

AND 

A.2.2.1 Reduce... 

OR 

A.2.2.2Perform... 

OR 

A.3 Remove... 

This example represents a more complicated use of logical connectors. 

Required Actions A.1, A.2, and A.3 are alternative choices, only one of 

which must be performed as indicated by the use of the logical connector 

OR and the left justified placement. Any one of these three ACTIONS 

may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be 

performed as indicated by the logical connector AND. Required 

Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented 

position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are 

alternative choices, only one of which must be performed.

Page 6 of 32
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

DESCRIPTION

Limiting Conditions for Operation (LCOs) specify the lowest functional 

capability or performance levels of equipment required for safe operation 

of the facility. 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 Times(s).

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

Required Action. It is referenced to the time of discovery of a situation 

(e.g., equipment or variable not within limits) that requires entering an 

ACTIONS Condition unless otherwise specified, providing the Cask 

System is in a specified condition stated in the Applicability of the LCO. 

Required Actions must be completed prior to the expiration of the 

specified Completion Time. An ACTIONS Condition remains in effect 

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

Cask System is not within the LCO Applicability. 

Once a Condition has been entered, subsequent subsystems, 

components, or variables expressed in the Condition, discovered to be 

not within limits, will not result in separate entry into the Condition unless 

specifically stated. The Required Actions of the Condition continue to 

apply to each additional failure, with Completion Times based on initial 

entry into the Condition.

(continued)

Page 7 of 32
Completion Times 

1.3

1.3 Completion Times (continued)

EXAMPLES The following examples illustrate the use of Completion Times with 

different types of Conditions and changing Conditions.

EXAMPLE 1.3-1

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION 

TIME 

B. Required B.1 Perform Action 12 hours 

Action and B.1. 

associated 

Completion AND 

Time not 36 hours 

met. B.2 Perform Action 

B.2. 

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

separate Completion Time. Each Completion Time is referenced to the 

time that Condition B is entered. 

The Required Actions of Condition B are to complete action B.1 within 12 

hours AND complete action B.2 within 36 hours. A total of 12 hours is 

allowed for completing action B.1 and a total of 36 hours (not 48 hours) is 

allowed for completing action B.2 from the time that Condition B was 

entered. If action B.1 is completed within 6 hours, the time allowed for 

completing action B.2 is the next 30 hours because the total time allowed 

for completing action B.2 is 36 hours.

(continued)

Page 8 of 32
Completion Times 

1.3

1.3 Completion Times (continued)

EXAMPLES 

(continued)

EXAMPLE 1.3-2

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION 

TIME 

A. One system not A.1 Restore system to 7 days 

within limit, within limit. 

B. Required Action B.1 Complete action 12 hours 

and associated B.1. 

Completion 

Time not met. AND 

36 hours 

B.2 Complete action 

B.2. 

When a system is determined not to meet the LCO, Condition A is 

entered. If the system is not restored within 7 days, Condition B is also 

entered and the Completion Time clocks for Required Actions B.1 

and B.2 start. If the system is restored after Condition B is entered, 

Conditions A and B are exited, and therefore, the Required Actions of 

Condition B may be terminated.

(continued)

Page 9 of 32
Completion Times 

1.3

1.3 Completion Times (continued)

EXAMPLES 

(continued)

IMMEDIATE 

COMPLETION 

TIME

EXAMPLE 1.3-3 

ACTIONS 

-------------------------------------- NO -TE ------------------------------------------

Separate Condition entry is allowed for each component. --------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION 

TIME 

A. LCO not met. A.1 Restore compliance 4 hours 

with LCO. 

B. Required Action B.1 Complete action 6 hours 

and associated B.1. 

Completion AND 

Time not met. 

B.2 Complete action 12 hours 

B.2. 

The Note above the ACTIONS table is a method of modifying how the 

Completion Time is tracked. If this method of modifying how the 

Completion Time is tracked was applicable only to a specific Condition, 

the Note would appear in that Condition rather than at the top of the 

ACTIONS Table. 

The Note allows Condition A to be entered separately for each 

component and Completion Times tracked on a per component basis. 

When a component is determined to not meet the LCO, Condition A is 

entered and its Completion Time starts. If subsequent components are 

determined to not meet the LCO, Condition A is entered for each 

component and separate Completion Times start and are tracked for 

each component. 

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

Action should be pursued without delay and in a controlled manner.

Page 10 of 32
Frequency 

1.4

1.0 USE AND APPLICATION 

1.4 Frequency

PURPOSE

DESCRIPTION

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

Frequency requirements.

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

the Surveillance must be met in order to meet the associated Limiting 

Condition for Operation (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. 

Situations where a Surveillance could be required (i.e., its Frequency 

could expire), but where it is not possible or not desired that it be 

performed until sometime after the associated LCO is within its 

Applicability, represent potential SR 3.0.4 conflicts. To avoid these 

conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such 

that it is only "required" when it can be and should be performed. With 

an SR satisfied, SR 3.0.4 imposes no restriction.

(continued)

Page 11 of 32
Frequency 

1.4 

1.4 Frequency (continued) 

EXAMPLES The following examples illustrate the various ways that Frequencies are 

specified. 

EXAMPLE 1.4-1 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

Verify pressure within limit. 12 hours 

Example 1.4-1 contains the type of SR most often encountered in the 

Technical Specifications (TS). The Frequency specifies an interval 

(12 hours) during which the associated Surveillance must be performed 

at least one time. Performance of the Surveillance initiates the 

subsequent interval. Although the Frequency is stated as 12 hours, an 

extension of the time interval to 1.25 times the interval specified in the 

Frequency is allowed by SR 3.0.2 for operational flexibility. The 

measurement of this interval continues at all times, even when the SR is 

not required to be met per SR 3.0.1 (such as when the equipment or 

variables are 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 condition specified in the Applicability of the LCO, 

the LCO is not met in accordance with SR 3.0.1. 

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

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

performance of the SR is required, the Surveillance must be performed 

within the Frequency requirements of SR 3.0.2 prior to entry into the 

specified condition. Failure to do so would result in a violation of SR 

3.0.4 

(continued)

Page 12 of 32
Frequency 

1.4

1.4 Frequency (continued)

EXAMPLES 

(continued) EXAMPLE 1.4-2

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

Verify flow is within limits. Once within 

12 hours prior to 

starting activity 

AND 

24 hours thereafter 

Example 1.4-2 has two Frequencies. The first is a one time performance 

Frequency, and the second is of the type shown in Example 1.4-1. The 

logical connector "AND" indicates that both Frequency requirements must 

be met. Each time the example activity is to be performed, the 

Surveillance must be performed within 12 hours prior to starting the 

activity. 

The use of "once" indicates a single performance will satisfy the specified 

Frequency (assuming no other Frequencies are connected by "AND"). 

This type of Frequency does not qualify for the 25% extension allowed by 

SR 3.0.2. 

"Thereafter" indicates future performances must be established per 

SR 3.0.2, but only after a specified condition is first met (i.e., the "once" 

performance in this example). If the specified activity is canceled or not 

performed, the measurement of both intervals stops. New intervals start 

upon preparing to restart the specified activity.

Page 13 of 32
Approved Contents 

2.0 

2.0 APPROVED CONTENTS 

2.1 Cask contents shall be limited to SPENT NUCLEAR FUEL initially approved by the NRC 

in Appendix [X.XX] of the FSAR, through the issuance of a cask Certificate of 

Compliance. 

2.2 Proposed alternatives to contents listed in Appendix [X.XX] of the FSAR may be 

authorized by the Director of The Office of Nuclear Material Safety and Safeguards or 

designee. The request for such alternative contents should demonstrate that: 

1. The proposed alternative contents would provide an acceptable level of safety, and 

2. The proposed alternative contents are consistent with the applicable requirements. 

Requests for alternatives to contents shall be submitted in accordance with 

10 CFR 72.4. 

[A description of the fuel parameters to be listed in Appendix [X.XX] is provided below: 

Fissile Isotopes (U0 2 vs. MOX) 

Maximum Initial [Planar Average] Enrichment 

Fuel Class (e.g., 14x14, 15x15) 

Number of Fuel Rods 

Number of Water Holes 

Maximum Assembly Average Burnup 

Minimum Cooling Time after Reactor Shutdown 

Minimum Active Fuel Average Enrichment 

Cladding Material 

Non-Fuel Hardware (e.g., BPRANTPAs (cooling time and burnup)) 

Maximum Weight per Storage Location (including fuel channels and non-fuel 

hardware) 

Maximum Decay Heat per Storage Location 

Fuel Condition (intact, damaged or debris) 

To change these parameters requires NRC approval. All other fuel parameters, also identified 

in the FSAR, can be changed through the 10 CFR 72.48 process. The parameter list may need 

to be modified based on unique features of a particular design or for specialized areas such as 

high burnup fuel and burnup credit. This list is intended for intact fuel. As a result, the list may need to be modified if damaged fuel or fuel debris is stored in the cask. 

When preferential loading configurations are part of the design basis, they need to be included 

in the contents description.]

Page 14 of 32
LCO Applicability 

3.0 

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 

LCO 3.0.1 LCOs shall be met during 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. 

LCO 3.0.3 Not applicable. 

LCO 3.0.4 When an LCO is not met, entry into a specified condition in the Applicability shall 

not be made except when the associated ACTIONS to be entered permit continued 

operation in the specified condition in the Applicability for an unlimited period of 

time. This Specification shall not prevent changes in specified conditions in the 

Applicability that are required to comply with ACTIONS or that are related to the 

unloading of an SFSC. 

LCO 3.0.5 Not applicable.

Page 15 of 32
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 

equipment or variables outside specified limits. 

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

1.25 times the interval specified in the Frequency, as measured from the previous 

performance or as measured from the time a specified condition of the Frequency 

is met. 

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

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

above Frequency extension applies to each performance after the initial 

performance. 

Exceptions to this Specification are stated in the individual Specifications. 

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

Frequency, then compliance with the requirement to declare the LCO not met may 

be delayed, from the time of discovery, up to 24 hours or up to the limit of the 

specified Frequency, whichever is less. This delay period is permitted to allow 

performance of the Surveillance. 

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 not be made 

unless the LCO's Surveillances have been met within their specified Frequency. 

This provision shall not prevent entry into specified conditions in the Applicability 

that are required to comply with Actions or that are related to the unloading of an 

SFSC.

Page 16 of 32
Fuel Integrity During Drying 

3.1.1

3.1 Fuel Integrity

3.1.1 Fuel Integrity.During Drying

The time after draining the [CANISTER/Cask] and before helium backfill operation 

is complete shall not exceed [X] days [the vacuum drying time may be a function of 

decay heat in a table or chart].

[NOTE: The time specification [X] may be relocated to an administrative program if a 

methodology for calculating fuel temperature based on decay heat and heatup time is approved 

by the NRC.]

APPLICABILITY: During LOADING OPERATIONS.

ACTIONS: 

------------------------------------------------- N O T E -----------------------------------------------------------

Separate Condition entry is allowed for each [CANISTER/Cask]. 

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

CONDITION REQUIRED ACTION COMPLETION 

TIME 

A. LCO not met. A.1 Verify adequate heat Immediately 

removal to prevent 

exceeding a short-term fuel 

temperature limit. 

AND 

A.2 Complete helium backfill [X] days 

operation. 

B. Required Actions B.1 Place [CANISTER/Cask] in Immediately 

and associated [a safe condition. The 

Completion Times not applicant shall propose an 

met. appropriate condition and 

completion time for its 

design.] 

(continued)

Page 17 of 32

LCO 3.1.1
Fuel Integrity During Drying 

3.1.1

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.1 Verify the time after draining the [CANISTER/Cask] Once, prior to 

and before helium backfill operation is completed TRANSPORT 

is __ [XI days. SR 3.0.4 does not apply. operations

Page 18 of 32
Fuel Integrity During Backfill and Transfer 

3.1.2 

3.1 Fuel Integrity

3.1.2 Fuel Integrity During Backfill and Transfer

LCO 3.1.2 The time after completion of helium backfill operation and until the 

CANISTER is inserted into the storage cask shall not exceed [X] days [the 

time may be a function of decay heat in a table or chart].

[NOTE: This LCO may not be needed ff the associated casks and approved contents provide 

adequate cooling to prevent approaching short-term fuel temperature limits. The time 

specification [X] may be relocated to an administrative program if a methodology for calculating 

fuel temperature based on decay heat and heatup time is approved by the NRC. A similar type 

LCO may be needed for UNLOADING operations.] 

APPLICABILITY: During LOADING OPERATIONS. 

ACTIONS: 

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

Separate Condition entry is allowed for each CANISTER. 

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

COMPLETION 

CONDITION REQUIRED ACTION TIME 

A. LCO not met. A.1 Verify adequate heat removal to Immediately 

prevent exceeding a short-term 

fuel temperature limit. 

AND 

A.2 Complete CANISTER transfer. [X] days 

B. Required Actions B.1 Place CANISTER in [a safe Immediately 

and associated condition. The applicant shall 

Completion Times not propose an appropriate 

met. condition and completion-time 

for its design.] 

(continued)

Page 19 of 32
Fuel Integrity During Backfill and Transfer 

3.1.2

SURVEILLANCE FREQUENCY 

SR 3.1.2 Verify that the time after completion of helium backfill Once, prior to 

operation and until insertion of the CANISTER into TRANSPORT 

the storage cask is _< [X] days. SR 3.0.4 does not operations 

apply.

Page 20 of 32
SFSC Heat Removal System 

3.1.3 

Note: this-LCO is only appicable to cask designs with cooling vents. 

3.1 Fuel Integrity

3.1.3 SFSC Heat Removal System 

LCO 3.1.3 The SFSC Heat Removal System shall be OPERABLE 

APPLICABILITY: While CANISTER is in the storage OVERPACK. 

ACTIONS: 

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

Separate Condition entry is allowed for each SFSC.

COMPLETION 

CONDITION REQUIRED ACTION TIME 

TIME 

A. LCO not met. A.1 Restore SFSC Heat Removal [8] hours 

System to OPERABLE status. 

OR 

A.2.1 Verify adequate heat 

removal to prevent Immediately 

exceeding short-term fuel 

temperature limit; 

AND 

A.2.2 Restore SFSC Heat 

Removal System to [30] days 

OPERABLE status. 

B. Required Actions B.1 Place SFSC in [a safe Immediately 

and associated Completion condition. The applicant shall 

Times not met. propose an appropriate 

condition and completion time 

for its design.] 

(continued)

Page 21 of 32
SFSC Heat Removal System 

3.1.3

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.3 Verify all OVERPACK inlet and outlet air ducts are free of [24] hours 

blockage. 

OR 

For OVERPACKS with temperature monitoring [24] hours 

equipment, verify the difference between the average 

OVERPACK air outlet temperature and ISFSI ambient 

temperature is [_< XX0 F or C].

Page 22 of 32
Cask Interseal Pressure 

3.2.1 

Note: Required only for those casks with bolted closures and an interseal pressure monitoring 

system. 

3.2 Cask Integrity

3.2.1 Cask Interseal Pressure 

LCO 3.2.1 The cask interseal minimum pressure shall be maintained at the value listed in 

Section xxxx of the FSAR, as updated. 

APPLICABILITY: During STORAGE OPERATIONS. 

ACTION: 

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

Separate Condition entry is allowed for each SFSC.

COMPLETION 

CONDITION REQUIRED ACTION TIME 

TIME 

A. Cask interseal pressure A.1 Re-establish cask interseal [7] days 

below limit, pressure above limit. 

B. Required Action and B.1 Place SFSC in [a safe [30] days 

associated Completion condition. The applicant shall 

time not met. propose an appropriate 

condition and completion time 

for its design.] 

(continued)

Page 23 of 32
Cask Interseal Pressure 

3.2.1

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.1 Verify cask interseal helium pressure above limit. [7] days 

SR 3.2.2 Perform a channel operational test to verify proper Once, within [7] 

function of pressure switch/transducer on cask days of 

overpressure system. commencing 

storage operations 

and every [36] 

months thereafter

Page 24 of 32
Dissolved Boron Concentration 

3.3.1 

Note: Required only for those casks that take credit for boron in the water for criticality control. 

Not needed for BWR plants. 

3.3 Cask Criticality Control Program 

3.3.1 Dissolved Boron Concentration 

LCO 3.3.1 The dissolved boron concentration in the water of the [CANISTER/Cask] cavity 

shall be Ž [XXX] ppmb. 

[NOTE: The boron concentration [XXX] may be relocated to an administrative program if a 

methodology for calculating k-eff of the spent fuel storage [CANISTER/Cask] is approved by 

the NRC.] 

APPLICABILITY: During LOADING OPERATIONS and UNLOADING OPERATIONS with 

water and at least one fuel assembly in the [CANISTER/Cask] 

ACTIONS: 

COMPLETION 

CONDITION REQUIRED ACTION TIME 

TIME 

A. Dissolved boron A.1 Suspend loading of fuel Immediately 

concentration not met. assemblies into cask and any 

other actions that increase 

reactivity. 

AND 

A.2 Restore boron concentration to Immediately 

exceed limit. 

AND 

A.3 Remove all fuel assemblies [24] hours 

from cask. 

(continued)

Page 25 of 32
Dissolved Boron Concentration 

3.3.1

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.1.1 Verify the dissolved boron concentration is met using Within [4] hours 

two independent measurements, prior to 

commencing 

LOADING 

OPERATIONS 

AND 

every [48] hours 

thereafter while the 

cask is in the spent 

fuel pool or while 

water is in the cask 

SR 3.3.1.2 Verify the dissolved boron concentration is met using Within [4] hours 

two independent measurements. prior to 

commencing 

UNLOADING 

OPERATIONS 

AND 

every [48] hours 

thereafter while the 

cask is in the spent 

fuel pool or while 

water is in the cask

Page 26 of 32
[CANISTER/Cask] Water Temperature 

3.3.2 

Note: This specification is only required if: 

a. Boron credit is assumed in the criticality analysis, and/or 

b. Optimum moderation is not assumed in the criticality analysis. 

3.3.2 [CANISTER/Cask] Water Temperature 

LCO 3.3.2 The temperature of the water in the canister shall be _! 200 'F [alternatively, in 

lieu of a temperature limit, a time limit can be applied that is based on decay 

heat]. 

APPLICABILITY: During LOADING and UNLOADING OPERATIONS. 

ACTIONS:

-----------------------------...- - ----------------- ' II j I

Separate Condition entry is allowed for each [CANISTER/Cask] system. 

COMPLETION 

CONDITION REQUIRED ACTION TIME 

A. [CANISTER/Cask] water A.1 Restore [CANISTER/Cask] [2] hours 

temperature limit not met. water temperature to below 

limit. 

B. Required Action and B.1 Place [CANISTER/Cask] in [a Immediately 

Associated Completion safe condition. The applicant 

time not met. shall propose an appropriate 

condition and completion time 

for its design.] 

(continued)

Page 27 of 32

r,,---------------------------------------------------------...
CANISTER Water Temperature 

3.3.2

SURVEILLANCE REQUIREMENTS

SURVEILLANCE

SR 3.3.2 Verify temperature of the water in the [CANISTER/Cask] 

has not exceeded 200 OF.

FREQUENCY

i

Once within [18] 

hours after 

[TRANSFER 

CASK with loaded 

CANISTER/Cask] 

is removed from 

fuel pool 

AND 

Every [30] minutes 

thereafter

I _______________________________

Page 28 of 32
Design Features 

4.0 

4.0 DESIGN FEATURES 

4.1 Design Features Significant to Safety 

4.1.1 Criticality Control 

[Items listed in 4.1.1 are those which would have a significant effect on safety if altered or 

modified. Item 1 and/or 2 may be removed if the application includes an analysis which 

shows that the parameter does not significantly affect criticality safety in the particular 

design.] 

1. Flux trap size or fuel cell spacing: _> [X.XX] in. 

2. '

0B loading in the Boral neutron absorbers: > [X.XX] g/cm 2 

[4.1.2 Materials 

1. Protective coatings used inside the cask 

2. Neutron Absorbers and Shields 

3. Containment Boundary Seals 

Instead of specifying a material directly, the applicant may propose a set of performance 

standards along with proposed methods for determining that the material will meet the 

applicable standards. 

Note: Section 4.1.2 may be incorporated into the Cask Description in Condition 1 .b. of the 

Certificate of Compliance if the applicant prefers.] 

4.2 Codes and Standards 

The following provides information on the governing codes for components of the [XXX ] cask 

design: 

Cask Component Applicable Codes Editions/Years 

Important to Safety 

[XXXX] [XXXXXX] [XXXXX] 

4.2.1 Alternatives to Codes, Standards, and Criteria 

Table [X.XX ] of the FSAR lists approved alternatives to the [code(s) of record] for 

the design of the Cask System. 

(continued)

Page 29 of 32
Design Features 

4.0 

4.2.2 -Construction/Fabrication Alternatives to Codes, Standards, and Criteria 

Proposed alternatives to the [code(s) of record] including alternatives allowed by Table X.XX of the FSAR may be used when authorized by the Director of the Office 

of Nuclear Material Safety and Safeguards or designee. The request for such 

alternatives should demonstrate that: 

1. The proposed alternatives would provide an acceptable level of quality and 

safety, or 

2. Compliance with the specified requirements of the [code of record] would result 

in hardship or unusual difficulty without a compensating increase in the level of 

quality and safety. 

Requests for alternatives shall be submitted in accordance with 10 CFR 72.4. 

4.3 Structural Performance 

4.3.1 Earthquake Loads 

The spent fuel storage cask design earthquake load on the top surface of the ISFSI 

pad shall not exceed: 

Horizontal Peak Acceleration in Corresponding Vertical Peak 

each of the two orthogonal Accelerations 

Directions 

[XX] [XX] 

4.3.2 Design G-loads 

The fission product barrier design g-loads due to postulated handling accidents shall 

not exceed: 

Fission Product Barrier End Drop Side Drop Tipover 

[Cask and/or CANISTER] [XX] [XX] [XX]

4.4 Cask Handling/ CANISTER Transfer Facility 

[Note that certain designs may require a specification for operations outside 

of the Part 50 facility.]

Page 30 of 32
Administrative Controls 

5.0 

5.0 ADMINISTRATIVE CONTROLS 

5.1 Administrative Programs 

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

5.1.1 Radioactive Effluent Control Program 

A program shall be established that includes: 

1. Implementation of the requirements of [10 CFR 72.44(d) or 72.126, as 

appropriate]. 

2. Limits on the surface contamination and verification of meeting those limits prior 

to removal of the cask from the Part 50 structure, 

3. Limits on the leakage rate and verification of meeting those limits prior to removal 

of the cask from the Part 50 structure, and, 

4. An effluent monitoring program, if the surface contamination limits are greater 

than the values specified in [Regulatory Guide 1.86 or an NRC-approved 

methodology in the FSAR can be inserted in place of RG-1.86]; or if the leakage 

rate limits are greater than the values specified as "leaktight" in [ANSI N 14.5 

1997 "Leakage Tests on Packages for Shipment" or an NRC-approved 

methodology in the FSAR can be inserted in place of ANSI N14.5]. 

5.1.2 Cask Loading, Unloading, and Preparation Program 

A program shall be established to implement the FSAR requirements for loading fuel 

and components into the cask, unloading fuel and components from the cask, and 

preparing the cask for storage. The requirements of the program for loading and 

preparing the cask shall be complete prior to removing the cask from the 10 CFR 

Part 50 structure. [Items 1, 5, and 6 are associated with requirements that will 

remain in the STS, however, the process for establishing the specified action limit 

may be moved to this administrative program if a method of evaluation acceptable to 

the NRC is presented in the FSAR. Items 2, 3, and 4 have been relocated from the 

LCO section to this administrative program because it is felt that NRC approved 

methods of evaluation will be relatively easy to develop. If appropriate methods are 

not presented in the FSAR, these items will retain LCOs.] 

At a minimum, the program shall establish criteria that need to be verified to address 

FSAR commitments and regulatory requirements for: 

1. Vacuum drying times and pressures to assure that the short-term fuel 

temperature limits are not violated and the cask is adequately dry, 

2. Inerting pressure and purity to assure adequate heat transfer and corrosion 

control, 

3. Leak testing to assure adequate cask integrity and consistency with the offsite 

dose analysis, 

(continued)

Page 31 of 32
Administrative Controls 

5.0 

5.0 Administrative Controls (continued) 

4. Surface dose rates to assure proper loading and consistency with the offsite 

dose analysis, 

5. Ambient and pool water temperature to assure adequate subcriticality and 

material ductility, 

6. Spent fuel pool boron concentration to verify the acceptable subcriticality margin, 

and 

7. [Clad oxidation thickness for high-burnup fuel in accordance with ISG-1 1 or other 

NRC-approved methodology if high-burnup fuel is included in the contents.] 

The program shall include compensatory measures and appropriate completion 

times if the program requirements are not met. 

5.1.3 ISFSI Operations Program 

A program shall be established to implement the FSAR requirements for ISFSI 

Operations. 

At a minimum, the program shall establish criteria that need to be verified for: 

1. Minimum cask center-to-center spacing, 

2. Pad parameters (i.e., pad thickness, concrete strength, soil modulus, 

reinforcement, etc.) that are consistent with the FSAR analysis, and 

3. Maximum lifting heights for the cask system to ensure that the g-load limits in the 

table in Section 4.3.2 are met for the design basis events.

Page 32 of 32
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER 

(2-89) (Assigned by NRC, Add Vol., Supp., Rev., 

NRCM 1102, and Addendum Numbers, if any.) 

3201.3202 BIBLIOGRAPHIC DATA SHEET 

(See instructions on the reverse) NUREG-1 745 

2. TITLE AND SUBTITLE 

Standard Format and Content for Technical Specifications for 

10 CFR Part 72 Cask Certificates of Compliance MONTH YED 

June 2001 

4. FIN OR GRANT NUMBER 

5. AUTHOR(S) 6. TYPE OF REPORT 

C. Withee, C. Jackson, et al. Technical 

7. PERIOD COVERED (Inclusive Dates) 

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor. 

provide name and mailing address.) 

Spent Fuel Project Office 

Office of Nuclear Material Safety and Safeguards 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type "Same as above ; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, 

and mailing address.)

Same as 8. above.

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less) 

The Standard Technical Specifications (STS) for dry cask storage are intended to be used by potential 10 CFR Part 72 

Certificate Holders in developing a set of clear and consistent technical specifications for their dry cask storage applications. 

The NRC believes that these Dry Cask STS in this NUREG will assure the overall safety goals for dry case storage are met, 

including maintaining subcriticality, controlling radiation dose to the workers and the public, assuring fuel retrievability, and 

maintaining the confinement barriers. This effort has removed the unnecessary detail from the technical specifications, moved 

the less significant requirements to administrative programs, made the requirements less prescriptive and maintained 

consistency with the site specific requirements contained in 10 CFR 72.44. Although these STS were developed for Certificate 

Holders, the format and level of detail presented in this set of STS can easily be translated to technical specifications for 

site-specific licensees.

12. KEY WORDS/DESCRIPTORS (List words orphrases that will assist researchers in locating the report.) 13. AVAILABILITY STATEMENT 

unlimited 

Spent Fuel Storage Cask unlim ited 

Independent Spent Fuel Sorage Installation 14. SECURITY CLASSIFICATION 

Standard Technical Specification (This Page) 

unclassified 

(This Report) 

unclassified 

15. NUMBER OF PAGES 

16. PRICE

NRC FORM 335 (2-89)
Federal Recycling Program

I
NUREG-1745 STANDARD FORMAT AND CONTENT FOR TECHNICAL SPECIFICATIONS FOR 10 CFR PART 72 

CERTIFICATES OF COMPLIANCE

UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASHINGTON, DC 20555-0001 

OFFICIAL BUSINESS 

PENALTY FOR PRIVATE USE, $300

JUNE 2001