ML16243A249

License Amendment Request #323, Revision 0, Permanently Defueled Technical Specifications for the Independent Spent Fuel Storage Installation to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pools

ML16243A249
Person / Time
Site:	Crystal River
Issue date:	08/31/2016
From:	Reising R R Duke Energy Florida
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F0816-01
Download: ML16243A249 (113)

Text

U.S. Nuclear Regulatory Commission 3F0816-01 Page 2 of 2 Enclosure 1 to this letter contains a description, technical analysis , significant hazards determination, and environmental considerations evaluation for the proposed amendment.

Enclosure 2 contains marked-up Facility Operating License (FOL) and POTS pages. All POTS Bases pages are being deleted in their entirety.

Enclosure 3 provides the FOL and POTS pages that will remain after approval of this LAR in a revision bar format. As discussed in this submittal, the remaining design basis accidents and transients analyzed in Chapter 14 of the CR-3 Final Safety Analysis Report (FSAR) are no longer applicable for the condition where all spent nuclear fuel is transferred to dry cask storage within an ISFSI. The CR-3 Plant Nuclear Safety Committee has reviewed the proposed amendment and recommended it for submittal, and a copy of this submittal has been provided to the State of Florida in accordance with 1 O CFR 50.91 (b). There are no new regulatory commitments made within this submittal.

DEF requests approval of this POTS LAR by August 31, 2017. Once approved , the amendment will be implemented within sixty (60) days following DEF's submittal of written notification to the NRC that all spent nuclear fuel assemblies have been transferred out of the spent fuel pools and placed in dry storage within the ISFSI. This license amendment will not be implemented if the revision to the AREVA CoC , Amendment 14, is not approved.

If you have any questions regarding this submittal, please contact Mr. Phil Rose , Lead Engineer, Nuclear Regulatory Affairs, at (352) 563-4883. I declare under penalty of perjury that the foregoing is true and correct. Executed on August 30, 2016. Sincerely, (2_ President Operations Support ARR/par

Enclosures:

1. Discussion of Change , Technical Analysis , Significant Hazards Determination and Environmental Considerations

2. Marked-up Facility Operating License and Technical Specification Pages (Red Line) 3. Clean Facility Operating License and Technical Specification Pages (Rev Bar) xc: NMSS Project Manager Regional Administrator , Region I State of Florida

Facility Operating License No. DPR-72 Amendment No. UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 DUKE ENERGY FLORIDA, LLC DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

License No. DPR-72

1. The Nuclear Regulatory Commission (the Commission) having found that:

A. The application filed by Florida Power Corporation*** (the licensee), as supplemented by letter dated December 9, 1976, 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 1; B. Construction of the Crystal River Unit 3 Nuclear Generating Plant (facility) has been substantially completed in conformity with Provisional Construction Permit No. CPPR-51 and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this 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 rules and regulations of the Commission; E. The licensee is financially qualified and Duke Energy Florida, LLC is technically qualified and financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Commission; F. The licensee has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations;

• • • On April 29, 2013, the name "Florida Power Corporation" was changed to "Duke Energy Florida, Inc." On August 1, 2015, Duke Energy Florida, Inc. converted to a limited liability company and the name was changed to "Duke Energy Florida, LLC."

Facility Operating License No. DPR-72 Amendment No.

G. The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the public;

H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. DPR-72 subject to the conditions for protection of the environment set forth herein is in accordance with 10 CFR Part 51, (formerly Appendix D to 10 CFR Part 50), of the Commission's regulations and all applicable requirements have been satisfied;

I. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Part 30, 40 and 70, including 10 CFR Sections 30.33, 40.32 and 70.23 and 70.31. 2. Facility Operating License No. DPR-72, issued to the licensee, is hereby amended in its entirety to read as follows:

A. This amended license applies to the Crystal River Unit 3 Nuclear Generating Plant, a pressurized water nuclear reactor and associated equipment (the facility), owned by the licensee and operated by Duke Energy Florida, LLC. The facility is located on the Gulf of Mexico, about seven and one-half miles northwest of the town of Crystal River, Citrus County, Florida, and is described in the "Final Safety Analysis Report" as supplemented and amended and the Environmental Report as supplemented and amended.

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

(1) Duke Energy Florida, LLC, pursuant to Section 104b of the Act and 10 CFR

Part 50, "Licensing of Production and Utilization Facilities," to possess and use the facility; (2) The licensee to possess the facility at the designated location in Citrus County, Florida, in accordance with the procedures and limitations set forth in this license; (3) Duke Energy Florida, LLC, pursuant to the Act and 10 CFR Part 70, to possess at any time special nuclear material configured as reactor fuel, in accordance with the limitations for storage as described in the Final Safety Analysis Report, as supplemented and amended; (4) Duke Energy Florida, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to possess at any time any byproduct, source and special nuclear material as sealed neutron sources used previously for reactor startup, as fission detectors, and sealed sources for reactor instrumentation and to possess and use at any time any byproduct, source, and special nuclear material as sealed sources for radiation monitoring equipment calibration in amounts as required; Revised page submitted 2-24-77

Facility Operating License No. DPR-72 Amendment No.

(5) Duke Energy Florida, LLC, 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 without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6) Duke Energy Florida, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (7) Duke Energy Florida, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to receive and possess, but not separate, that byproduct and special nuclear materials associated with four (4) fuel assemblies (B&W Identification Numbers 1A-01, 04, 05 and 36 which were previously irradiated in the Oconee Nuclear Station, Unit No. 1) acquired by Florida Power Corporation*** from Duke Power Company for use as reactor fuel in the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and 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 per Amendment No. 247

(2) Technical Specifications

The Technical Specifications contained in Appendix A are hereby replaced with the Permanently Defueled Technical Specifications (PDTS). Duke Energy Florida, LLC shall maintain the facility in accordance with the Permanently Defueled Technical Specifications, as revised through Amendment No. 249. (3) Deleted per Amendment No. 247 (4) Deleted per Amendment No. 20 dated 7-3-79

(5) Deleted per Amendment No. 247

(6) Deleted per Amendment No. 21, 7-3-79 (7) Deleted per Amendment No. 247

(8) Deleted per Amendment No. 247

(9) Deleted per Amendment No. 247 (10) Deleted per Amendment No. 247

• • • On April 29, 2013, the name "Florida Power Corporation" was changed to "Duke Energy Florida, Inc." On August 1, 2015, Duke Energy Florida, Inc. converted to a limited liability company and the name was changed to "Duke Energy Florida, LLC."

Added per Amdt. 15, 7-24-78 Facility Operating License No. DPR-72 Amendment No. (11) Deleted per Amendment No. 247 (12) Deleted per Amendment No. 237 (13) Deleted per Amendment No. 229

(14) Deleted per Amendment No. Mitigation Strategy Licens e Condition The licensee shall develop and maintain strategies for addressing large fires and explosions that include the following key areas:

(1.) Fire fighting responses strategy with the following elements: a. Pre-defined coordinated fire response strategy and guidance b. Assessment of mutual aid fire fighting assets c. Designated staging areas for equipment and materials d. Command and control e. Training of response personnel (2.) Operations to mitigate fuel damage considering the following: a. Protection and use of personnel assets b. Communications c. Minimizing fire spread d. Procedures for implementing integrated fire response strategy e. Identification of readily-available pre-staged equipment f. Training on integrated fire response strategy g. Spent fuel pool mitigation measures (3.) Actions to minimize release to include consideration of: a. Water spray scrubbing b. Dose to onsite responders (15) Deleted per Amendment No. 247 D. Physical Security

The licensee 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 plan, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "ISFSI Physical Security Plan, ISFSI Safeguards Contingency Plan and ISFSI Guard Training and Qualification Plan", Revision 0, submitted by letter dated May 24, 2016.

Facility Operating License No. DPR-72 Amendment No. E. Deleted per Amendment No. 247 F. In accordance with the requirement imposed by the October 8, 1976, order of the United States Court Appeals for the District of Columbia Circuit in Natural Resources Defense Council v. Nuclear Regulatory Commission, No. 74-1385 and 74-1586, that the Nuclear Regulatory Commission "shall make any licenses granted between July 21, 1976 and such time when the mandate is issued subject to the outcome of the proceedings herein," the license issued herein shall be subject to the outcome of such proceedings.

G. This amended license is effective as of the date of issuance. Facility Operating License No. DPR-72, as amended, shall expire at midnight, December 3, 2016.

Duke Energy Florida, LLC submitted the 10 CFR 50.82(a)(1) notification to the Nuclear Regulatory Commission on February 20, 2013. Per 10 CFR 50.51(b), the Facility Operating License No DPR-72 continues in effect until the Commission notifies the licensee that the License has been terminated.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation Attachments:

Appendices A & B - Technical Specifications

Date of Issuance: Jan 28 1977 Amdt. #97 March 31, 1987 Amendment Nos. 159, 164, 166, 171, 173, 181, 189, 190, 226, 235, 238 , 239, 242 , 24 3 , 245 and 246 amended the CR

-3 Operating License, only, and did not effect changes to the ITS LCOs or Bases.

Crystal River Unit 3 i Amendment No. 247 TABLE OF CONTENTS 1.0 USE AND APPLICATION

....................................

1.1-1 1.1 Definitions

.........................................

1.1-1 1.2 Logical Connectors

..................................

1.2-1 1.3 Completion Times

....................................

1.3-1 1.4 Frequency ...........................................

1.4-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

............

3.0-2 3.7 PLANT SYSTEMS

.......................................

3.7-1 3.7.13 Fuel Storage Pool Water Level

...................

3.7-1 3.7.14 Spent Fuel Pool Boron Concentration

.............

3.7-2 3.7.15 Spent Fuel Assembly Storage

.....................

3.7-4 4.0 DESIGN FEATURES

........................................

4.0-1 5.0 ADMINISTRATIVE CONTROLS

................................

5.0-1 Crystal River Unit 3 ii Amendment No. 247 TABLE OF CONTENTS B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

... B 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

............

B 3.0-2 B 3.7 PLANT SYSTEMS

....................................... B 3.7-1 B 3.7-13 Fuel Storage Pool Water Level

.......................

B 3.7-1 B 3.7.14 Spent Fuel Pool Boron Concentration

.................

B 3.7-4 B 3.7-15 Spent Fuel Assembly Storage

.........................

B 3.7-7 Definitions

1.1 Crystal

River Unit 3 1.1-1 Amendment No. 247 1.0USE AND APPLICATION 1.1Definitions

---

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

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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.

Logical Connectors 1.2 (continued)

Crystal River Unit 3 1.2-1 Amendment No. 149 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.

Logical Connectors 1.2 (continued)

Crystal River Unit 3 1.2-2 Amendment No. 149

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 met.

A.1 Verify. . .

AND A.2 Restore . . .

In this example the logical connector AND is used to indicate that both Required Actions A.1 and A.2 must be completed when in Condition A.

Logical Connectors

1.2 Crystal

River Unit 3 1.2-3 Amendment No. 149 1.2Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.

A.1 Trip . . .

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

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 either 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.

Completion Times

1.3 Crystal

River Unit 3 1.3-1 Amendment No. 247 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 handling and storage of 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 time of discovery of a situation (e.g., inoperable equipment or 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 Specification. 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 facility is not within the Specification Applicability.

IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

Frequency 1.4 (continued)

Crystal River Unit 3 1.4-1 Amendment No. 247 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 thi s 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.

Frequency 1.4 Crystal River Unit 3 1.4-2 Amendment No. 247 1.4Frequency EXAMPLES The following example illustrates the type of frequency statement that appears in the Permanently Defueled Technical Specifications (PDTS).

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform (activity). 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Example 1.4-1 contains the type of SR encountered in the PDTS. The Frequency specifies an interval (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) during which the associated Surveillance must be performed at least one time. Completion of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for flexibility.

LCO Applicability

3.0 Crystal

River Unit 3 3.0-1 Amendment No. 247 3.0 LIMITING CONDITION FOR OPERATION (LC0) 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.

SR Applicability

3.0 Crystal

River Unit 3 3.0-2 Amendment No. 247 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual Specifications, 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.

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. 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

Fuel Storage Pool Water Level 3.7.13 Crystal River Unit 3 3.7-1 Amendment No. 247

3.7 PLANT

SYSTEMS 3.7.13 Fuel Storage Pool Water Level LCO 3.7.13 The fuel storage pool water level shall be 156 ft Plant Datum. APPLICABILITY:

During movement of irradiated fuel assemblies in fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool water level not within limit. A.1 Suspend movement of irradiated fuel assemblies in fuel storage pool.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify the fuel storage pool water level is 156 ft Plant Datum.

7 days Spent Fuel Pool Boron Concentration 3.7.14 Crystal River Unit 3 3.7-2 Amendment No. 247

3.7 PLANT

SYSTEMS 3.7.14 Spent Fuel Pool Boron Concentration LCO. 3.7.14 The spent fuel pool boron concentration shall be 1925 ppm. APPLICABILITY:

When fuel assemblies are stored in the spent fuel pool and a spent fuel pool verification has not been performed since the last movement of fuel assemblies in the spent fuel pool.

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.2.1 Initiate action to restore spent fuel pool boron concentration to within limit.

OR A.2.2 Verify by administrative means a Storage Pool A and Storage Pool B spent fuel pool verification has been performed since the last movement of fuel assemblies in the spent fuel pool.

Immediately Immediately Immediately

Spent Fuel Pool Boron Concentration 3.7.14 Crystal River Unit 3 3.7-3 Amendment No. 247 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the spent fuel pool boron concentration is 1925 ppm. 7 days Spent Fuel Assembly Storage 3.7.15 Crystal River Unit 3 3.7-4 Amendment No. 247

3.7 PLANT

SYSTEMS 3.7.15 Spent Fuel Assembly Storage LCO 3.7.15 The combination of initial enrichment and burnup of each spent fuel assembly stored in Storage Pool A and Storage Pool B, shall be within the acceptable region of Figure 3.7.15-1 or Figure 3.7.15

-2. APPLICABILITY:

Whenever any fuel assembly is stored in Storage Pool A or Storage Pool B of the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO not met.

A.1 Initiate action to move the noncomplying fuel assembly to an acceptable configuration.

Immediately

Spent Fuel Assembly Storage 3.7.15 Crystal River Unit 3 3.7-5 Amendment No. 247 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify by administrative means the initial enrichment and burnup of the fuel assembly is in accordance with Figure 3.7.15

-1 or Figure 3.7.15

-2. Prior to storing the fuel assembly in Storage Pool A or Storage Pool B.

Spent Fuel Assembly Storage 3.7.15 Crystal River Unit 3 3.7-6 Amendment No. 247

1. Category B: Fuel from this category can be stored with no restrictions except as noted below. 2. Category A: Fuel from this category can be stored with fuel from Categories A or B.

3. Category F: Fuel from this category must be stored in a one

-out-of-two checkerboard configuration with fuel from Category B or empty water cells. Category F fuel stored in a checkerboard pattern with either Category B fuel or empty water cells must be separated from Category A fuel by a transition row of Category B fuel.

Figure 3.7.15-1 Burnup versus Enrichment Curve for Spent Fuel Storage Pool A

Spent Fuel Assembly Storage 3.7.15 Crystal River Unit 3 3.7-7 Amendment No. 247 1.Category B: Fuel from this category can be stored with no restrictions except as noted below. 2. Category BP: Fuel from this category (between lower and upper curves) can be stored in the peripheral cells of the pool.

3. Category BE: Unacceptable for storage unless surrounded by eight empty water cells.

4. Fuel of any enrichment and burnup including fresh, unburned fuel may be stored in Pool B if surrounded by eight empty water cells.

Category BE fuel assemblies must be separated by two adjacent empty cells in Pool B.

Figure 3.7.15-2 Burnup versus Enrichment Curve for Spent Fuel Storage Pool B

Design Features 4.0 (continued)

Crystal River Unit 3 4.0-1 Amendment No.

247 4.0DESIGN FEATURES

4.1 Site The 4,738 acre site is characterized by a 4,400 foot minimum exclusion radius centered on the Reactor Building; isolation from nearby population

centers; sound foundation for structures; an abundant supply of cooling water; an ample supply of power; and favorable conditions of hydrology, geology, seismology, and meteorology.

4.2 Not Used 4.3 Fuel Storage Spent fuel shall not be stored in the spent fuel pool.

Design Features 4.0 (continued)

Crystal River Unit 3 4.0-2 Amendment No. 247 4.0DESIGN FEATURES 4.3 Fuel Storage

4.3.1 Criticality

4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U

-235 enrichment of 5.0 weight percent; b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.6 of the FSAR;

c. A nominal 9.11 inch center to center distance between fuel assemblies placed in the B pool;

d. A nominal 10.5 inch center to center distance between fuel assemblies placed in the A pool.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U

-235 enrichment of 5.0 weight percent; b. k eff 0.95 is fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.6 of the FSAR;

c. k eff 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.6 of the FSAR; and

d. A nominal 21.125 inch center to center distance between fuel assemblies placed in the storage racks.

Design Features

4.0 Crystal

River Unit 3 4.0-3 Amendment No. 247 DESIGN FEATURES

4.3.2 Drainage

The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 138 feet 4 inches.

4.3.3 Capacity

The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1474 fuel assemblies and six failed fuel containers.

Responsibility

5.1 Crystal

River Unit 3 5.0-1 Amendment No. 249

5.0 ADMINISTRATIVE

CONTROLS

5.1 Responsibility

5.1.1 The General Manager Decommissioning shall be responsible for overall facility functions and shall delegate in writing the succession to this responsibility during his absence.

The General Manager Decommissioning or his designee shall approve, prior to implementation, each proposed test, experiment or modifications to systems or equipment that affect stored nucle ar fuel. 5.1.2 The Shift Supervisor shall be responsible for the shift command function.

Organization 5.2 (continued)

Crystal River Unit 3 5.0-2 Amendment No. 24 9 5.0 ADMINISTRATIVE CONTROLS

5.2 Organization

5.2.1 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 responsible for activities affecting the safe handling and storage of nuclear fuel. a. Lines of authority, responsibility, and communications shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These shall be documented in the FSAR;

b. The General Manager Decommissioning shall have overall responsibility for the safe handling and storage of nuclear fuel and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure the safe handling and storage of nuclear fuel.

The General Manager Decommissioning shall be responsible to control those onsite activities necessary for the safe handling and storage of nuclear fuel; and

c. The individuals who train the Certified Fuel Handlers, carry out health physics, or perform 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. 5.2.2 Unit Staff The unit staff organization shall include the following: a. Each duty shift shall be composed of at least one Shift Supervisor and one Non

-certified Operator.

b.Shift crew composition may be less than the minimum requirement of 5.2.2.a for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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.

Organization

5.2 Crystal

River Unit 3 5.0-3 Amendment No. 244 5.2Organization 5.2.2 Unit Staff (continued) c.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 pools. d. An individual qualified in Radiation Protection procedures shall be on site during fuel handling operations and during movement of heavy loads over the fuel storage racks. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position. e.Oversight of fuel handling operations shall be provided by a Certified Fuel Handler. f.The Shift Supervisor shall be a Certified Fuel Handler.

Unit Staff Qualifications

5.3 Crystal

River Unit 3 5.0-4 Amendment No. 249

5.0 ADMINISTRATIVE

CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1, 1971 for comparable positions, except for the Radiation Protection Manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. 5.3.2 A training and retraining program for the Certified Fuel Handler positions shall be maintained under the direction of the General Manager Decommissioning.

Not Used 5.4 Crystal River Unit 3 5.0-5 Amendment No. 149

5.0 ADMINISTRATIVE

CONTROLS 5.4 Not Used Not Used 5.5 Crystal River Unit 3 5.0-6 Amendment No. 149

5.0 ADMINISTRATIVE

CONTROLS 5.5 Not Used Procedures, Programs, and Manuals 5.6 (continued)

Crystal River Unit 3 5.0-7 Amendment No. 244 5.0 ADMINISTRATIVE CONTROLS 5.6 Procedures, Programs, and Manuals

5.6.1 Procedures

5.6.1.1 Scope Written procedures shall be established, implemented, and maintained covering the following activities:

a. The procedures applicable to the safe storage of nuclear fuel recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978; b. Quality assurance for effluent and environmental monitoring;

c. Fire Protection Program implementation; and

d. All programs specified in Specification 5.6.2. 5.6.2 Programs and Manuals The following programs shall be established, implemented, and maintained. Programs and Manuals may be titled as Reports.

5.6.2.1 Not Used 5.6.2.2 Not Used 5.6.2.3 Offsite Dose Calculation Manual (ODCM):

This Manual contains offsite dose calculation methodologies, the radioactive effluent controls program, and radiological environmental monitoring activities. The ODCM shall contain:

1. The methodologies and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents;

2. The methodologies and parameters used in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints;

3. The controls for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable in accordance with 10 CFR 50.36a. These include:

Procedures, Programs and Manuals 5.6 (continued)

Crystal River Unit 3 5.0-8 Amendment No. 149 5.6Procedures, Programs and Manuals 5.6.2.3 ODCM (continued)

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values of 10 CFR 20.1001 - 20.2401, Appendix B, Table II, Column 2; c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302; d. Limitations on the annual and quarterly doses or dos e commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I; e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year at least every 31 days; f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; g. 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 limited to the following:

1. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and

Procedures, Programs and Manuals

5.6 Crystal

River Unit 3 5.0-9 Amendment No. 24 9 5.6Procedures, Programs and Manuals 5.6.2.3 ODCM (continued)

2. For tritium and for all radionuclides in particulate form with half

-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrems/yr to any organ;

h. 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; i. Limitations on the annual and quarterly doses to a member of the public from tritium and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and j. Limitations on the annual dose 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. Licensee Initiated Changes to the 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 change(s), and

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the on-site review function and the approval of the General Manager Decommissioning; and Procedures, Programs and Manuals 5.6 (continued)

Crystal River Unit 3 5.0-10 Amendment No. 244 5.6Procedures, Programs and Manuals 5.6.2.3 ODCM (continued)

3. Shall be submitted to the Commission 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 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.

5.6.2.4 Not Used 5.6.2.5 Not Used 5.6.2.6 Not Used 5.6.2.7 Not Used 5.6.2.8 Not Used 5.6.2.9 Not Used 5.6.2.10 Not Used 5.6.2.11 Not Used Procedures, Programs and Manuals

5.6 Crystal

River Unit 3 5.0-11 Amendment No. 24 7 5.6Procedures, Programs and Manuals 5.6.2.12 Not Used 5.6.2.13 Not Used 5.6.2.14 Not Used 5.6.2.15 Not Used 5.6.2.16 Not Used 5.6.2.17 Technical Specifications (TS) Bases Control Program Changes to the Bases of the TS shall be made under appropriate administrative controls and reviewed according to the review process specified in the Quality Assurance Plan.

Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the followi ng: a. A change in the TS incorporated in the license; or

b. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

Proposed changes that meet the criteria of Specification 5.6.2.17.a or Specification 5.6.2.17.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. 5.6.2.18 Not Used 5.6.2.19Not Used 5.6.2.20 Not Used 5.6.2.21 Not Used Reporting Requirements 5.7 (continued)

Crystal River Unit 3 5.0-12 Amendment No. 247

5.0 ADMINISTRATIVE

CONTROLS

5.7 Reporting

Requirements

5.7.1 Routine

Reports 5.7.1.1 Reports required on an annual basis include:

a. Not Used b. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, a nd analyses of trends of the results of the radiological environmental monitoring for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM).

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, a s well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

c. Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year, and 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 unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program, and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV B.1.

Reporting Requirements 5.7 Crystal River Unit 3 5.0-13 Amendment No. 247 5.7Reporting Requirements 5.7.1.2 Not Used 5.7.2 Not Used High Radiation Area 5.8 (continued)

Crystal River Unit 3 5.0-14 Amendment No. 24 7

5.0 ADMINISTRATIVE

CONTROLS 5.8 High Radiation Area

5.8.1 Pursuant

to 10 CFR 20, paragraph 20.1601(c), alternative methods are used to control access to high radiation areas. Each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation (measured at 30 cm) is >

100 mrem/hr but <

1000 mrem/hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the a rea.

b. A radiation monitoring device that continuously integrates the radiation dose in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance.

5.8.2 In addition to the requirements of Specification 5.8.1, areas with radiation levels 1000 mrem/hr at 30 cm from the radiation source or from any surface penetrated by the radiation but less than 500 rads/hr at 1 meter from the radiation source or from any surface penetrated by the radiation shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Shift Supervisor or health physics supervision. Doors shall remain locked except during periods of access by personnel.

Direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

High Radiation Area

5.8 Crystal

River Unit 3 5.0-15 Amendment No. 247

5.8 High Radiation Area (continued) 5.8.3 For individual high radiation areas with radiation levels of > 1000 mrem/hr at 30 cm from the radiation source or from any surface penetrated by the radiation but less than 500 rads/hr at 1 meter from the radiation source or from any surface penetrated by the radiation, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that are not continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

Amendment Nos. 159, 164, 166, 171, 173, 181, 189, 190, 226, 235, 238, 239, 242 , 243 , 245 and 246 amended the CR

-3 Operating License, only, and did not effect changes to the ITS LCOs or Bases. Page Revision LCO Applicability B 3.0 Crystal River Unit 3 B 3.0-1 Revision No. 89 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCO 3.0.1 and 3.0.2 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e., when the unit is in the specified conditions of the Applicability statement of each Specification).

LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes that completion of the Required Actions within the specified Completion Times constitutes compliance with a Specification. The Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore variables to within specified limits. Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering ACTIONS.

Completing the Required Actions is not required when an LCO is met or is no longer applicable within the associated Completion Time, unless otherwise stated in the individual Specifications.

SR Applicability B 3.0 (continued)

Crystal River Unit 3 B 3.0-2 Revision No. 89 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SR 3.0.1 through SR

3.0.4 establish

the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO.

Variables are assumed to be within limits when the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that variables are within limits when the requirements of the Surveillance(s) are known not to be met between required Surveillance performances.

Surveillances do not have to be performed when the specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified.

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per..." interval. SR 3.0.2 permits a 25%

extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers facility conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).

SR Applicability B 3.0 (continued)

Crystal River Unit 3 B 3.0-3 Revision No. 89 BASES SR 3.0.2 The 25% extension does not significantly degrade the (continued) reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

This delay period provides an adequate time limit to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance. The basis for this delay period includes consideration of facility conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs.

Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals. While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified Frequency is provided to perform th e missed Surveillance, it is expected that the missed Surveillance will be performed at the first reasonable opportunity.

SR Applicability B 3.0 Crystal River Unit 3 B 3.0-4 Revision No. 89 BASES SR 3.0.3 If a Surveillance is not completed within the allowed delay (continued) period, then the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable Specification Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable Specification Conditions begin immediately upon the failure of the Surveillance.

Completion of the Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1. SR 3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a specified condition in the Applicability.

This Specification ensures that variable limits are met before entry into specified conditions in the Applicability for which these ensure safe storage of nuclear fuel. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring the specified condition in the Applicability.

The provisions of SR

3.0.4 shall

not prevent entry into specified conditions in the Applicability that are required to comply with ACTIONS.

The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance.

Fuel Storage Pool Water Level B 3.7.13 (continued) Crystal River Unit 3 B 3.7-1 Revision No. 89 B 3.7 PLANT SYSTEMS B 3.7.13 Fuel Storage Pool Water BASES BACKGROUND The water contained in the spent fuel pool provides a medium for removal of decay heat from the stored fuel elements, normally via the spent fuel cooling system. The spent fuel pool water also provides shielding to reduce the general area radiation dose during both spent fuel handling and storage.

Although maintaining adequate spent fuel pool water level is essential to both decay heat removal and shielding effectiveness, the Technical Specification minimum water level limit is based upon maintaining the pool's iodine retention effectiveness consistent with that assumed in the evaluation of a fuel handling accident (FHA). The fuel handling accident described in FSAR Section 14.2.2.3 (Ref. 2), assumes that a minimum of 23 feet of water is maintained above the stored fuel. This assumption allows the use of the pool iodine decontamination factor used in the associated offsite dose calculation.

APPLICABLE The minimum water level in the fuel storage pool meets the SAFETY ANALYSES assumptions of the FHA described in FSAR Section 14.2.2.3. The resultant 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose to a person at the exclusion area boundary and the 30 day dose at the low population zone are much less than 10 CFR 50.67 (Ref. 4) limits.

Although the water level above a damaged assembly lying on top of the fuel storage racks may be less than 23 feet, an extrapolation of the iodine removal efficiency factors indicates that the iodine removal factor used in the dose calculations will still be conservative at water levels as low as 21 feet (Ref. 5). The 23 foot criteria above the fuel in the racks will ensure at least 21 feet above the damaged assembly.

Fuel Storage Pool Water Level B 3.7.13 (continued) Crystal River Unit 3 B 3.7-2 Revision No. 89 BASES APPLICABLE Fuel storage pool water level satisfies Criterion 2 of the SAFETY ANALYSES NRC Policy Statement.

(continued) LCO The specified water level of 23 feet over the top of the irradiated fuel assemblies seated in the storage racks (156 ft plant datum) preserves the assumptions of the FHA analysis (Ref. 2). As such, it is the minimum level allowed during movement of fuel within the fuel storage pool.

APPLICABILITY This LCO is only applicable during movement of irradiated fuel assemblies in the fuel storage pool. This is consistent with the safety analysis which assumes the FHA initiating event to be the drop of an irradiated fuel assembly. Control of heavy loads, i.e., damaging the fuel assembly as a result of dropping a heavy load onto it, is not addressed by the safety analysis or this Technical Specification. Plant procedures are relied upon to prevent the dropping of heavy loads onto spent fuel.

ACTIONS A.1 With the fuel storage pool level less than the minimum required level, the movement of fuel assemblies in the fuel storage pool is immediately suspended. This effectively precludes the occurrence of a fuel handling accident.

Fuel Storage Pool Water Level B 3.7.13 Crystal River Unit 3 B 3.7-3 Revision No. 89 BASES SURVEILLANCE SR 3.7.13.1 REQUIREMENTS The water level in the fuel storage pool must be checked periodically. Since there is no mechanism for inadvertently lowering the level during normal operations (changes in level are procedurally controlled) and there is a low level alarm should pool level drop to approximately 24 feet above the stored fuel assemblies, a 7 day Frequency is sufficient to provide assurance of adequate water level. The Frequency is based on engineering judgment and industry

-accepted practice. REFERENCES

1. Deleted. 2. FSAR, Section 14.2.2.3. 3. Deleted. 4. 10 CFR 50.67. 5. FPC Calculation N 0001.

Spent Fuel Pool Boron Concentration B 3.7.14 (continued)

Crystal River Unit 3 B 3.7-4 Revision No. 89 B 3.7 PLANT SYSTEMS B 3.7.14 Spent Fuel Pool Boron Concentration BASES BACKGROUND As described in the Bases for LCO 3.7.15, "Spent Fuel Assembly Storage," fuel assemblies are stored in the high density region of the spent fuel pool storage racks in accordance with criteria based on initial weight

-percent enrichment and discharge burnup. Although the water in the spent fuel pool is normally borated to 2000 ppm, the criteria that limit the storage of a fuel assembly to specific rack locations (criticality analysis) are conservatively developed without taking credit for the boron in the pool water.

APPLICABLE The acceptance criteria for the fuel storage pool SAFETY ANALYSIS criticality analyses is that a k eff of < 0.95 must be maintained for all postulated events. The storage racks are capable of maintaining this k eff with unborated pool water at a temperature yielding the highest reactivity (assuming the storage restrictions of LCO 3.7.15 are met).

Most abnormal storage locations will not result in an increase in the k eff of the racks.

However, it is possible to postulate events, such as the mis-loading of an assembly with a burnup and enrichment combination outside the acceptable area in Figure 3.7.

15-1 and 3.7.15

-2, or dropping an assembly between the pool wall and the fuel racks, which could lead to an increase in reactivity.

For such events, credit is taken for the presence of boron in the pool water since the NRC does not require the assumption of two unlikely, independent, concurrent events to ensure protection against a criticality accident (double contingency principle).

The reduction in k eff, caused by the boron more than offsets the reactivity addition caused by credible accidents.

The concentration of dissolved boron in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statement.

Spent Fuel Pool Boron Concentration B 3.7.14 (continued)

Crystal River Unit 3 B 3.7-5 Revision No. 89 BASES LCO The required concentration of dissolved boron in the fuel storage pool of 1925 ppm preserves the assumption used in the analyses of the potential accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel assembly storage and movement within the fuel storage pool.

APPLICABILITY This LCO is applicable whenever fuel assemblies are stored in the spent fuel pool, until a complete spent fuel pool verification has been performed following the last movement of fuel assemblies in the spent fuel pool. This LCO does not apply following the verification since the verification would confirm that there are no misloaded fuel assemblies.

With no further fuel assembly movement in progress, there is no potential for a misloaded fuel assembly or a dropped fuel assembly and the reactivity of the racks alone is adequate to preserve assumptions of the criticality analysis.

ACTIONS A.1, A.2.1, and A.2.2 When the concentration of boron in the fuel storage pool is less than required, immediate action must be taken to preclude the occurrence of an accident. This is most efficiently achieved by immediately suspending the movement of fuel assemblies within the pool. This Action does not preclude movement of a fuel assembly to a safe position.

Additionally, action must be initiated immediately to restore pool boron concentration to within the LCO limit or a pool verification performed. Either of these Actions will restore compliance with the LCO or demonstrate the need for the LCO does not currently exist.

SURVEILLANCE SR 3.7.14.1 REQUIREMENTS This SR verifies that the concentration of boron in the fuel storage pool is within the required limit. This is accomplished by sampling representative samples of the pool.

Spent Fuel Pool Boron Concentration B 3.7.14 Crystal River Unit 3 B 3.7-6 Revision No. 89 BASES SURVEILLANCE SR 3.7.14.1 (continued)

REQUIREMENTS Operating experience has shown significant differences between boron measured near the top of the pool and that measured elsewhere. As long as this SR is met, the analyzed events are fully bounded.

The 7 day Frequency is acceptable because no major replenishment of pool water is expected to take place over this period of time. REFERENCES

1. Criticality Safety Evaluation of the Pool A Spent Fuel Storage Racks in Crystal River Unit 3 With Fuel of 5.0% Enrichment, S. E. Turner, Holtec Report HI-931111, December 1993.

2.Criticality Safety Analysis of the Westinghouse Spent Fuel Storage Racks in Pool B of Crystal River Unit 3, S. E. Turner, Holtec Report HI

-992128, May 1999.

3.Criticality Safety Analysis of the Crystal River Unit 3 Pool A for Storage of 5% Enriched Mark B

-11 Fuel in Checkerboard Arrangement with Water Holes, Holtec Report HI-992285, August 1999.

4.Criticality Evaluation of CR3 Spent Fuel Pool Storage Racks with Mark B

-12 Fuel, Holtec Report HI

-2022907, September 2002.

5.Progress Energy Engineering Change EC No. 52456, "Documentation of Acceptability to Receive and Store Mk-B/HTP Fuel". 6.Criticality Analysis of Additional Patterns for Crystal River 3 Pools A and B, Holtec Report HI-2063559, September 2006.

Spent Fuel Assembly Storage B 3.7.15 (continued)

Crystal River Unit 3 B 3.7-7 Revision No. 89 B 3.7 PLANT SYSTEMS B 3.7.15 Spent Fuel Assembly Storage BASES BACKGROUND This document describes the Bases for the Spent Fuel Assembly Storage which imposes storage requirements upon irradiated and unirradiated fuel assemblies stored in the fuel storage pools containing high density racks.

The storage areas, which are part of the Spent Fuel System, governed by this Specification are: a.Fuel storage pool "A" and b.Fuel storage pool "B".

In general, the function of the storage racks is to support and protect new and spent fuel from the time it is placed in the storage area until it is shipped offsite.

Spent fuel is stored underwater in either fuel storage pool A or B. Only fuel pool A has the capability to store failed fuel in containers.

Spent fuel pool A features high density poison storage racks with a 10 1/2 inch center

-to-center distance capable of storing 542 assemblies.

Fuel pool A is capable of storing fuel with enrichments up to 5.0 weight percent U

-235 (Ref. 1, 6, 7, 8 and 9) without exceeding the criticality criteria of Reference 3 providing the fuel has sufficient burnup and required storage configuration.

Spent fuel pool B also contains high density racks having a 9.11 inch center

-to-center distance capable of storing 932 assemblies. Fuel pool B is capable of storing fuel with enrichments up to 5.0 weight percent U

-235 (Ref. 2, 7, 8 and 9) without exceeding the criticality criteria of Reference 3, providing the fuel has sufficient burnup and required storage configuration. New and low burnup fuel may be placed into pool B if surrounded by empty storage cells. This is primarily for, but not restricted to, fuel inspection and reconstitution activities (Ref. 9).

Spent Fuel Assembly Storage B 3.7.15 (continued)

Crystal River Unit 3 B 3.7-8 Revision No. 89 BASES BACKGROUND Both of the spent fuel pools are constructed of reinforced (continued) concrete and lined with stainless steel plate. They are located in the fuel handling area of the auxiliary building. New fuel storage requirements are addressed in Section 4.0, "Design Features".

APPLICABLE The function of the spent fuel storage racks is to support SAFETY ANALYSES and protect spent fuel assemblies from the time they are placed in the pool until they are shipped offsite. The spent fuel assembly storage LCO was derived from the need to establish limiting conditions on fuel storage to assure sufficient safety margin exists to prevent inadvertent criticality. The spent fuel assemblies are stored entirely underwater in a configuration that has been shown to result in a reactivity of less than or equal to 0.95 under worse case conditions (Ref. 1, 2, 6, 7, 8 and 9).

The spent fuel assembly enrichment requirements in this LCO are required to ensure inadvertent criticality does not occur in the spent fuel pool. Inadvertent criticality within the fuel storage area could result in offsite radiation doses exceeding 10 CFR 50.67 limits. The spent fuel assembly storage satisfies Criterion 2 of the NRC Policy Statement.

LCO Limits on the new and irradiated fuel assembly storage in high density racks were established to ensure the assumptions of the criticality safety analysis of the spent fuel pools is maintained.

Limits on initial fuel enrichment and burnup for both new and for spent fuel stored in pool A have been established. Two limits are defined:

1. Initial fuel enrichment must be less than or equal to

5.0 weight

percent U

-235, and Spent Fuel Assembly Storage B 3.7.15 (continued)

Crystal River Unit 3 B 3.7-9 Revision No. 89 BASES LCO 2. For new, low irradiation, and spent fuel with initial (continued) enrichment less than or equal to 5.0 weight percent and greater than or equal to 3.5 weight percent, fuel burnup must be within the limits specified in Figure 3.7.15

-1. Figure 3.7.15-1 presents three areas of required fuel assembly burnup as a function of initial enrichment.

a.Category B: Fuel with enrichment

-burnup combinations in the area above the upper curve can be stored with no restrictions except as noted below. That is, this fuel can be stored next to fuel with enrichment

-burnups that fall into Categories A, B or F provided there are no restrictions on that fuel type preventing it. Category B has the same burnup

-enrichment requirements for Pools A and B. b.Category A: Fuel with enrichment

-burnup between the curves can be stored in any configuration with fuel above the lower curve. That is, this fuel may be stored next to fuel with enrichment

-burnups that fall into Categories A or B. c.Category F:

Fuel with enrichment

-burnup combinations below the lower curve must be stored in a one-out-of-two checkerboard configuration with fuel that has enrichment

-burnup combinations above the upper curve (Category B) or with empty watercells that contain no fuel. Areas of Category F fuel stored in the checkerboard combination with Category B fuel or empty water cells must be separated from areas of Category A fuel by a transition row of Category B cells. The acceptability of storing this fuel in the checkerboard configuration is documented in References 6, 7, 8 and 9. Fuel enrichment limits are based on avoiding inadvertent criticality in the spent fuel pool. The CR

-3 spent fuel storage system was initially designed to a maximum enrichment of 3.5 weight percent.

Enrichments of up to 5.0 weight percent are permissible for storage in spent fuel pool A as long as the fuel burnup is sufficient to limit the worst case reactivity in the storage pool to less than or equal to 0.95.

Fuel burnup reduces the reactivity of the fuel due to the accumulation of fission product poisons.

Reference 1

Spent Fuel Assembly Storage B 3.7.15 (continued)

Crystal River Unit 3 B 3.7-10 Revision No. 89 BASES LCO documents that the required burnup varies linearly as a (continued) function of enrichment with 10500 megawatt days per metric ton uranium (Mwd/mtU) required for fuel with 5.0 weight percent enrichment and 0 burnup required for 3.5 weight percent enriched fuel.

Similar types of restrictions have been established for Pool B. 1. Initial fuel enrichment must be 5.0 weight percent U-235, and 2. For fuel with initial enrichment 5.0 weight percent and 2.0 weight percent, fuel burnup must be within the limits specified in Figure 3.7.15-2. a. Category B: Fuel with burnup

-enrichment combinations in the area above the upper curve can be stored with no restrictions except as noted below. That is, this fuel can be stored next to fuel with burnup

-enrichments that fall into Categories B or BP. Category B has the same burnup

-enrichment requirements for Pools A and B.

b. Category BP: Fuel with burnup

-enrichment combinations in the area between the lower and upper curves must be stored in the peripheral cells of the pool. A peripheral cell is defined as the outermost of the first two storage cells closest to the spent fuel pool wall that has a fuel assembly located in it. If the storage cell closest to the spent fuel pool wall is kept empty of fuel, then the second storage cell from the spent fuel pool wall may be filled with lower burnup fuel meeting the requirements of Category BP fuel. c. Category BE: Fuel of any burnup with an enrichment fuel, fuel from Category BP or fuel with burnup

-enrichment combinations in the area below the lower curve can be placed in Pool B, but must be surrounded by eight empty water cells. Category BE fuel assemblies must be separated by two adjacent empty cells in Pool B.

Spent Fuel Assembly Storage B 3.7.15 (continued)

Crystal River Unit 3 B 3.7-11 Revision No. 89 BASES APPLICABILITY In general, limiting fuel enrichment of stored fuel prevents inadvertent criticality in the storage pools. Inadvertent criticality is dependent on whether fuel is stored in the pools and is completely independent of plant MODE.

Therefore, this LCO is applicable whenever any fuel assembly is stored in high density fuel storage locations.

ACTIONS A.1 When the configuration of fuel assemblies stored in the spent fuel pool is not in accordance with Figure 3.7.15

-1 or Figure 3.7.15

-2, immediate action must be taken to make the necessary fuel assembly movement(s) to bring the configuration into compliance. The Immediate Completion Time underscores the necessity of restoring spent fuel pool fuel loading to within the initial assumptions of the criticality analysis.

The ACTIONS do not specify a time limit for completing movement of the affected fuel assemblies to their correct location. This is not meant to allow an unnecessary delay in resolution, but is a reflection of the fact that the complexity of the corrective actions is unknown.

SURVEILLANCE SR 3.7.15.1 REQUIREMENTS Verification by administrative means that initial enrichment and burnup of fuel assemblies in accordance with Figure 3.7.15-1 and Figure 3.7.15

-2 is required prior to storage of spent fuel in storage pool A or pool B (as applicabl e). This surveillance ensures that fuel enrichment limits, as specified in the criticality safety analyses (Ref. 1, 2, 6, 7 and 8), are not exceeded.

The surveillance Frequency (prior to storage in high density region of the fuel storage pool) is appropriate since the initial fuel enrichment and burnup cannot change after removal from the core.

Spent Fuel Assembly Storage B 3.7.15 Crystal River Unit 3 B 3.7-12 Revision No. 89 BASES REFERENCES

1. Criticality Safety Evaluation of the Pool A Spent Fuel Storage Racks in Crystal River Unit 3 with Fuel of 5.0% Enrichment, S. E. Turner, Holtec Report HI 931111, December 1993.

2. Criticality Safety Analysis of the Westinghouse Spent Fuel Storage Racks in Pool B of Crystal River Unit 3, S. E. Turner, Holtec Report HI

-992128, May 1999.

3.NUREG 0800, Standard Review Plan, Section 9.1.1 and 9.1.2, Rev. 2, July 1981.

4.10 CFR 50.67.

5.CR-3 FSAR, Section 9.6.

6.Criticality Safety Analysis of the Crystal River Unit 3 Pool A for Storage of 5% Enriched Mark B

-11 Fuel in Checkerboard Arrangement With Water Holes, S. E. Turner, Holtec Report HI

-992285, August 1999.

7.Criticality Evaluation of CR3 Spent Fuel Pool Storage Racks with Mark B

-12 Fuel, Holtec Report HI

-2022907, September 2002.

8.Progress Energy Engineering Change EC No. 52456, "Documentation of Acceptability to Receive and Store Mk-B/HTP Fuel".

9.Criticality Analysis of Additional Patterns for Crystal River 3 Pools A & B for Progress Energy, Holtec Report No. HI-2063579, September 2006

Amendment Nos. 159, 164, 166, 171, 173, 181, 189, 190, 226, 235, 238 , 239, 242 , 24 3 , 245 and 246 amended the CR

-3 Operating License, only, and did not effect changes to the ITS LCOs or Bases.

Crystal River Unit 3 i Amendment No. 247 TABLE OF CONTENTS

4.0 DESIGN

FEATURES

........................................

4.0-1 5.0 ADMINISTRATIVE CONTROLS

................................

5.0-1 Crystal River Unit 3 ii Amendment No. 247 Design Features

4.0 Crystal

River Unit 3 4.0-1 Amendment No.

4.0DESIGN FEATURES

4.1 Site The 4,738 acre site is characterized by a 4,400 foot minimum exclusion radius centered on the Reactor Building; isolation from nearby population

centers; sound foundation for structures; an abundant supply of cooling water; an ample supply of power; and favorable conditions of hydrology, geology, seismology, and meteorology.

4.2 Not Used 4.3 Fuel Storage

Spent fuel shall not be stored in the spent fuel pool.

High Radiation Area 5.8 (continued)

Crystal River Unit 3 5.0-1 Amendment No.

5.0 ADMINISTRATIVE

CONTROLS 5.8 High Radiation Area

5.8.1 Pursuant

to 10 CFR 20, paragraph 20.1601(c), alternative methods are used to control access to high radiation areas. Each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation (measured at 30 cm) is >

100 mrem/hr but <

1000 mrem/hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates the radiation dose in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance.

5.8.2 In addition to the requirements of Specification 5.8.1, areas with radiation levels 1000 mrem/hr at 30 cm from the radiation source or from any surface penetrated by the radiation but less than 500 rads/hr at 1 meter from the radiation source or from any surface penetrated by the radiation shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Shift Supervisor or health physics supervision. Doors shall remain locked except during periods of access by personnel.

Direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

High Radiation Area

5.8 Crystal

River Unit 3 5.0-2 Amendment No.

5.8 High Radiation Area (continued) 5.8.3 For individual high radiation areas with radiation levels of > 1000 mrem/hr at 30 cm from the radiation source or from any surface penetrated by the radiation but less than 500 rads/hr at 1 meter from the radiation source or from any surface penetrated by the radiation, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that are not continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.