Text

Current Facility Operating License DPR-43, Tech Specs, Revised 10/07/2015
	ML053040352
Person / Time
Site:	Kewaunee
Issue date:	02/24/2011
From:	Leeds E; Office of Nuclear Reactor Regulation
To:	; Dominion Energy Kewaunee
	Boska J, NRR/DORL, 301-415-2901
References
	Download: ML053040352 (258)
	v • d • e

Renewed Operating License DPR-43 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555-0001 DOMINION ENERGY KEWAUNEE, INC.

DOCKET NO. 50-305 KEWAUNEE POWER STATION RENEWED FACILITY OPERATING LICENSE Renewed License No. DPR-43

1.

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

A.

The application to renew Facility Operating License No. DPR-43, filed by Dominion Energy Kewaunee, Inc. (the licensee) 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, and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Kewaunee Power Station (facility) has been substantially completed in conformity with Provisional Construction Permit No. CPPR-50, as amended, 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 renewed operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; E.

Dominion Energy Kewaunee, Inc., is technically qualified and financially qualified to engage in the activities authorized by this renewed 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; G.

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

After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of Renewed Facility Operating License No. DPR-43 is in accordance with 10 CFR Part 51 (formerly Appendix D of 1 O CFR Part 50) of the Commission's regulations and all applicable requirements have been satisfied; I.

The receipt, possession, and use of byproduct, source, and special nuclear material as authorized by this renewed operating license will be in accordance with the Commission's regulations in 10 CFR Parts 30 and 70, including 10 CFR Sections 30.33, 70.23, and 70.31; and J.

Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging' during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21 (a)(1 ), and (2) time-limited aging analyses that have been identified to require review under 1 O CFR 54.21 (c), such that there is reasonable assurance that the activities authorized by this renewed operating license will continue to be conducted in accordance with the current licensing basis, as definec;f in 1 O CFR 54.3, for the facility, and that any changes made to the facility's current licensing basis in order to comply with 10 CFR.54.29(a) are in accordance with the Act and the Commission's regulations.

2.

Renewed Facility Operating License No. DPR-43 is hereby issued to Dominion Energy Kewaunee, Inc., to read as follows:

A.

This license applies to the Kewaunee Power Station, a pressurized water nuclear reactor and associated equipment (the facility), owned by Dominion Energy Kewaunee, Inc. The facility is located in Kewaunee County, Wisconsin, and is described in the "Final Safety Analysis Report" as supplemented and amended, and in the Environmental Report as supplemented and amended.

8.

Subject to the conditions and requirements incorporated herein, the.Commission hereby licenses Dominion Energy Kewaunee, Inc.:

(1)

Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess and use the facility at the designated location in Kewaunee County, Wisconsin in accordance with the procedures and limitations set forth in this renewed license; (2)

Pursuant to the Act and 1 O CFR Part 70, to possess at any time special nuclear material that was used as reactor fuel in accordance with the limitations for storage, as described in the Final Safety Analysis Report, as supplemented and amended; (3)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed sources for reactor instrumentation and radiation monitoring equipment calibration and as fission detectors in amounts as required; and possess any byproduct, source and special nuclear material as sealed neutron sources that was used for reactor startup; Renewed Operating License DPR-43 Amendment No. 215 (4)

Pursuant.to the Act and 1 o 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; (5)

Pursuant to the Act and 1 O 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.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 1 O CFR Chapter 1:

(1) Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and (2) 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 (3) is subject to the additional conditions specified or incorporated below:

(1)

Deleted (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 216, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3)

Deleted (4)

Physical Protection The licensee shall fully implement and maintain in effect all provisjons 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 combine.d set of plans, which contains Safeguards Information protected under 1 O CFR 73.21 is entitled:

"Nuclear Management Company Kewaunee Nuclear Power Plant Physical Security Plan (Revision O)" submitted by letter dated October 18, 2004, and supplemented by letter dated October 21, 2004, July 26, 2005, and May 15, 2006.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Kewaunee, Millstone, North Anna, and Surry Power Stations Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The CSP was approved by License Amendment No. 210, as supplemented by a change approved by License Amendment No. 216.

(5)

Deleted Renewed Operating License DPR-43 Amendment No~ 216 (6)

Deleted (7)

Deleted (8)

Deleted '

(9)

Deleted (10). Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (11)

Seismic Analysis Methodology for Auxiliary Building Crane The licensee shall use the seismic analysis methodology submitted by letter dated July 7, 2008, supplemented on September 19, 2008, and March 17, 2009, and approved by the NRC staff in Amendment No. 205, for analysis of the Auxiliary Building crane. The licensee shall update the USAR to reflect this approval and in accordance with the schedule specified by 1 O CFR 50.71 (e).

(12)

Implementation of New and Revised Surveillance Requirements (a)

For Surveillance Requirements (SRs) that are new in Amendment No. 207, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of that amendment.

Renewed Operating License DPR-43 Amendment No. 215

(b)

(c)

(d) For SRs that existed prior to Amendment No. 207 whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of that amendment.

For SRs that existed prior to Amendment No. 207 that have modified acceptance criteria, the first performance subject to the modified acceptance criteria is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of that amendment.

For SRs that existed prior to Amendment No. 207 whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of that amendment.

(13)

Removed Details and Requirements Relocated to Other Controlled Documents License Amendment No. 207 authorizes the relocation of certain technical specifications and operating license conditions, if applicable, to other licensee-controlled documents. Implementation of that amendment shall include relocation of these requirements to the specified documents.

( 14)

Deleted (15)

Deleted (16)

Spent Fuel Pool Neutron Absorber Material Surveillance Programs If all spent fuel assemblies have not been removed from the spent fuel pool by December 31, 2017, the licensee shall request, prior to that date, an amendment to the license, pursuant to 1 O CFR 50.90, to incorporate boron carbide and Baral surveillance programs (specified as Items 38 and 39 in Appendix A of NUREG-1958, "Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station," dated January 2011) into the Technical Specifications.

D.

The licensee shall comply with applicable effluent limitations and other limitations and monitoring requirements, if any, specified pursuant to Section 401 (d) of the Federal Water Pollution Control Act Amendments of 1972.

E.

Deleted Renewed Operating License DPR-43 Amendment No. 215

3.

On February 25, 2013, Dominion Energy Kewaunee (DEK) certified that operations at Kewaunee Power Station would permanently cease in accordance with 10 CFR 50.82(a)(1 )(i). On May 14, 2013, DEK certified that the fuel had been permanently removed from the reactor vessel in accordance with 10 CFR 50.82(a)(1 )(ii). As a result, the 1 O CFR 50 license no longer authorizes operation of the reactor, or the emplacement or retention of fuel in the reactor vessel.

This license is effective as of the date of issuance and authorizes ownership and possession of Kewaune~ Power Station until the Commission notifies the licensee in writing *that the license is terminated. The licensee shall:

A. Take actions necessary to decommission the plant and continue to maintain the facility, including, where applicable, the storage; control and maintenance of the spent fuel, in a safe condition; and B. Conduct activities in accordance with all other restrictions applicable to the facility in accordance with the NRG regulations and the applicable provisions of the 1 O CFR 50 facility license as defined in Section 2 of this license.

FOR THE NUCLEAR REGULATORY COMMISSION IRA!

Eric J. Leeds, Director Office of Nuclear Reactor Regulation

Attachment:

Appendices A and B-Technical Specifications Date of Issuance: February 24, 2011 Renewed Operating License DPR-43 Amendment No. 215

APPENDIX A TECHNICAL SPECIFICATIONS FOR KEWAUNEE POWER STATION KEWAUNEE, WISCONSIN I

DOMINION ENERGY KEWAUNEE, INC.

I DOCKET NUMBER 50-305

TABLE OF CONTENTS Page Number 1.0 USE ANDAPPLICATION 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 3.7.13 Spent Fuel Pool Water Level.......................................................................... 3.7.13-1

3. 7.14

Spent Fuel Pool Boron Concentration............................................................. 3. 7.14-1 3.7.15 Spent Fuel Pool.Storage................................................................................. 3.7.15-1 4.0 DESIGN FEATURES 4.1 Site Location.......... :................................... :......................................................... 4.0-1 4.3 Fuel Storage................... '..................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility.................................................................................... :................. 5.1-1.

5.2 Organization........................................................................................................ 5.2-1 5.3 Facility Staff Qualifications................................................................................... 5.3-1' 5.4 Procedures.......................................................................................................... 5.4-1 5.5 Programs and Manuals................................. :...................................................... 5.5-1 5.6 Reporting Requirements...................................................................................... 5.6-1 5.7 High Radiation Area.............................................................................................. 5.7-1 Kewaunee Power Station Amendment No. 215

1.0 USE AND APPLICATION

1. 1 Definitions Definitions 1.1

~ ------------------------------------------N 0 TE---------~ --------.-----------------------------------------

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

ACTIONS ACTUATION LOGIC TEST CERTIFIED FUEL HANDLER CHANNEL CALIBRATION CHANNEL CHECK Kewaunee Power Station Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

An ACTUATION LOGIC TEST shall be the application of various simulated or actual. input combinations in conjunction with each possible interlock logic state required for OPERABILITY of a logic circuit and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

ACERTIFIED FUEL HANDLER is an individual who complies with provisions of the CERTIFIED FUEL HANDLER training program required by TS 5.3.2.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

1.1-1 Amendment No. 215

CHANNEL OPERATIONAL TEST (COT)

OPERABLE-OPERABILITY STAGGERED TEST BASIS TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)

Kewaunee Power Station Definitions 1; 1 A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to

verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.

A system, subsystem, train, component, or device shall be OPERABLE 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, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

A T ADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of all devices in the channel required for trip actuating device OPERABILITY.

The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy. The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps.

1.1-2 Amendment No. 215.

Logical Connectors 1.2 Kewaunee Power Station 1.2-1 Amendment 207 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 indentations 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.

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

Logical Connectors 1.2 Kewaunee Power Station 1.2-2 Amendment 207 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 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 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 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE BACKGROUND DESCRIPTION The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe management of irradiated 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).

The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of dis,covery 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 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 facility is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or 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.

However, when a subsequent train, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a.

Must exist concurrent with the first inoperability; and

b.

Must remain inoperable or not within limits after the first inoperability.is resolved.

Kewaunee Power Station 1.3-1 Amendment No. 215

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

EXAMPLES The total Completion Time allowed for completing a Required Action to.

address the subsequent inoperability shall be limited to the more restrictive of either:

a.

The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b.

The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery... "

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 Verify....

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Restore....

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Kewaunee Power Station 1.3-2 Amendment No. 215

1.3 Completion Times EXAMPLES (continued)

Completion Times 1.3 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 perform the verification required by ACTION B.1 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND perform the restoration required by ACTION B.2 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for performing ACTION B.1 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for performing ACTION B.2 from the time that Condition B was entered. If ACTION B.1 is completed within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for completing ACTION B.2 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for completing ACTION B.2 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while performing the verification required by ACTION B.1, the time allowed for completing ACTION B.2 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable.

OPERABLE status.

B. Required B.1 Verify....

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Initiate....

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Tf me clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

Kewaunee Power Station 1.3-3 Amendment No. 215

1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-3 ACTIONS CONDITION A. One Function X train inoperable.

B. One Function Y train inoperable.

C. One Function X train inoperable.

AND*

One Function Y train inoperable.

REQUIRED ACTION A.1 Restore Function X train to OPERABLE status.

B.1 Restore Function Y train to OPERABLE status.

C.1 Restore Function X train to OPERABLE status.

OR C.2 Restore Function Y train to OPERABLE status.

Completion Times 1.3 COMPLETION TIME 7 days 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

Kewaunee Power Station 1.3-4 Amendment No. 215

1.3 Completion Times EXAMPLES (continued)

Completion Times 1.3 If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A.

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required 8.1 Verify....

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

8.2 Initiate....

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Kewaunee Power Station 1.3-5 Amendment No. 215

1.3 Completion Times EXAMPLES (continued)

Completion Times 1.3 Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (including the extension) expires while one or more valves are still inoperable, Condition B is entered.

EXAMPLE 1.3-5 ACTIONS

N 0 TE -------------------------------------------

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Verify....

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Initiate....

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.

Kewaunee Power Station 1.3-6 Amendment No. 215

1.3 Completion Times EXAMPLES (continued)

Completion Times 1.3 The Note allows Condition A to be entered separa~ely for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition Bis entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition Bis exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform SR 3.x.x.x.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

OR A.2 Verify....

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months B. Required B.1 Initiate....

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated Completion Time not met.

Kewaunee Power Station 1.3-7 Amendment No. 215

1.3 Completion Times EXAMPLES (continued)

Completion Times 1.3 Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2),

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem isolated.

inoperable.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required B.1 Verify....

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND

. Completion Time not met.

B.2 Initiate....

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Kewaunee Power Station 1.3-8 Amendment No. 215

1.3 Completion Times EXAMPLES (continued)

Completion Times 1.3 Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per B hours thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition Bis entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

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

Kewaunee Power Station 1.3-9 Amendment No. 2.15

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 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 as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance or both.

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.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requiremenno specifically determine the ability to meet the acceptance criteria.

Kewaunee Power Station 1.4-1 Amendment No. 215

1.4 Frequency EXAMPLES Frequency 1.4 The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is the applicable specified condition.

EXAMPLE 1.4-1

/

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated 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 is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval spedfied by SR 3.0.2 is exceeded while the unit is in a specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

Kewaunee Power Station 1.4-2 Amendment No. 215

1.4 Frequency Frequency 1.4 EXAMPLES (continued)

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3,.prior to entry into the specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE Verify flow is within limits.

FREQUENCY Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entry into the applicable condition 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 applicable condition is entered, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type cif 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 applicable condition is exited, the measurement of both intervals stops. New intervals start upon entering the applicable condition.

Kewaunee Power Station 1.4-3 Amendment No. 215

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCO 3.0.2 LCO 3.0.3 LCO 3.0.4 LCO 3.0.5 LCOs shall be met during the specified conditions in the Applicability, except as provided in LCO 3.0.2.

Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5.

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.

Deleted.

When an LCO is not met, entry into a specified condition in the Applicability shall only be made:

a.

When the associated ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time;

b.

After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the specified condition in the Applicability, and establishment of risk management actions, if

appropriate; exceptions to this Specification are stated in the individual Specifications; or

c.

When an allowance is stated in the individual value, parameter, or other Specification.

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

Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate. OPERABILITY.

Kewaunee Power Station 3.0-1 Amendment No. 215

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SR 3.0.2 SR 3.0.3 SR 3.0.4 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 inoperable equipment or variables outside specified limits.

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.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

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. When an LCO is not met due to Surveillances not having b~en met, entry into a specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

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

Kewaunee Power Station 3.0-2 Amendment No. 215

3. 7 PLANT SYSTEMS 3.7.13 Spent Fuel Pool Water Level Spent Fuel Pool Water Level 3.7.13 LCO 3.7.13 The spent fuel pool water level shall be ~ 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY:

During movement of irradiated fuel assemblies in the spenJ fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water level not within limit.

A.1 Suspend movement of Immediately irradiated fuel assemblies in the spent fuel pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify the spent fuel pool water level is ~ 23 ft above 7 days the top of the irradiated fuel assemblies seated in the storage racks.

Kewaunee Power Station 3.7.13-1 Amendment No. 215

Spent Fuel Pool Boron Concentration 3.7.14

3. 7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Boron Concentration LCO 3.7.14 The spent fuel pool boron concentration shall be ~ 240 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 A. Spent fuel pool boron A.1 Suspend movement of fuel concentration not within assemblies in the spent fuel limit.

pool.

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

OR A.2.2 Initiate action to perform a spent fuel pool verification.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.14.1 Verify the spent fuel pool boron concentration is within limit.

Kewaunee Power Station 3.7.14-1 COMPLETION TIME Immediately Immediately Immediately FREQUENCY 7 days Amendment No. 215

Spent Fuel Pool Storage 3.7.15

3. 7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool Storage LCO 3.7.15 APPLICABILITY:

ACTIONS The combination of initial enrichment and burnup oLeach fuel assembly stored in the spent fuel pool shall be in accordance with the following: *

a.

Irradiated fuel assemblies discharged prior to or during the 1984 refueling outage with a combination of burnup and initial nominal enrichment in the "Acceptable Domain" of Figure 3. 7.15-1 shall be stored in the transfer canal spent fuel pool or the north and south combined spent fuel pools; and

b.

Irradiated fuel assemblies discharged after the 1984 refueling outage, and irradiated fuel assemblies discharged prior to or during the 1984 refueling outage with a combination of burnup and initial nominal enrichment in the "Unacceptable Domain" of Figure 3. 7.15-1, shall be stored in the north and south combined spent fuel pools.

Whenever any fuel assembly is stored in the spent fuel pool.

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

A.1 Initiate action to move the

. Immediately noncomplying fuel assembly to an acceptable location.

SURVEILLANCE REQUIREMENTS SR 3.7.15.1 SURVEILLANCE Verify by administrative means the initial enrichment and burnup of the fuel assembly is in accordance with Figure 3. 7.15-1.

Kewaunee Power Station 3.7.15-1 FREQUENCY Prior to storing the fuel assembly in the spent fuel pool Amendment No. 215

Spent Fuel Pool Storage 3.7.15 35.0 -~---------~-----~---~----~!

Acceptable Domain,

I.

I I

(3.411, 30) I 30.0 *------1----1 1----i-------i----t----- -

I I I

I I

5 25.0.

B = 1.29731 x E 1

- 1\\66621xFI~48.6~_06.x E-51~~2~~ ---!----!--

~

I l I

I (3 0, 24 t I

~ 200 i

1-*--1 *------

1---l-5 I

I (2;,17.21) I I

I I

~ 15*0 ---1-- ----'----1----Unaccepta~le--Doma~----I

~

(2.25, 13.37)

I i

I

~

l I

I I

I 10.0 - --,---[ ___ l ___, _______ l _____ l __ _

(2.0, 9.24)

I I

I 5.0. ----------*-------------------L----*---1 I

I I

I I'

I I

0.0 *'-----;----~---.;-----;-----;-----.;------,.-~

Bounding Cun~ :

2 2.2 2.4 2.6 2.8 3

3.2 3.4 Initial Enrichment (wt% U-235)

Figure 3.7.15-1(page1of1)

Fuel Assembly Burnup Limits in the Spent Fuel Pools Kewaunee Power Station 3.7.15-2 Amendment No. 215

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Kewaunee Power Station is located on property owned by Dominion Energy Kewaunee Inc. at a site on the west shore of Lake Michigan, approximately 30 miles east-southeast of the city of Green Bay, Wisconsin.

The minimum distance from the center line of the reactor containment to the site exclusion radius as defined in 10 CFR 100.3 is 1200 meters.

4.2 Deleted 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 4.9776 weight percent;

b.

keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.5 of the USAR;

c.

A nominal 8.3 inch rack cell lattice spacing between fuel assemblies placed in the canal pool;

d.

A minimum 1 O inch center to center distance between fuel assemblies placed in the north and south pools; and

e.

New and spent fuel assemblies stored in the north and south pools and the canal pool in accordance with LCO 3.7.15, "Spent Fuel Pool Storage."

4.3.1.2 Deleted 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 645 ft 2 inches (mean sea level).

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1205 fuel assemblies.

Kewaunee Power Station 4.0-1 Amendment No. 215

5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility Responsibility 5.1 5.1.1 The plant manager shall be responsible for overall plant operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

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

Kewaunee Power Station 5.1-1 Amendment No. 215

5.0 ADMINISTRATIVE CONTROLS

. 5.2 Organization 5.2.1 Onsite and Offsite Organizations Organization 5.2 Onsite and offsite organizations shall be established for plant and corporate.

management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear fuel.

a.

Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the quality.

assurance program. The plant specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be maintained in appropriate plant documents.

b.

The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe storage and maintenance of the nuclear fuel.

c.

A specified corporate officer shall have corporate responsibility for overall plant nuclear safety 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 safe management of nuclear fuel.

\\,

d.

The individuals who train CERTIFIED FUEL HANDLERS, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.

5.2.2 Facility Staff The facility staff organization shall include the following:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 5.2.2-1.

b.

Shift crew composition may be less than the minimum requirement of Table 5.2.2-1 for a period of tim~ not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , except in severe weather conditions, 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.

I Kewaunee Power Station 5.2-1 Amendment No. 215

5.2 Organization 5.2.2 Facility Staff (continued)

Organization 5.2

c.

All fuel handling operations shall be directly supervised by a qualified individual.

d.

The shift manager sha]I be a CERTIFIED FUEL HANDLER.

e.

An individual qualified in radiation protection procedures shall be onsite during fuel handling operations or movements of loads over storage racks containing fuel.

Kewaunee Power Station 5.2-2 Amendment No. 215

Table 5.2.2-1 (page 1 of 1)

Minimum Shift Crew Composition Organization 5.2 POSITION MINIMUM STAFFING CERTIFIED FUEL HANDLER Non-Certified Operator, Note: The Non-Certified Operator position may be filled by a CERTIFIED FUEL HANDLER.

Kewaunee Power Station 5.2-3 Amendment No. 215

5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications Facility Staff Qualifications 5;3 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for:

a.

The radiation protection manager who shall meet or exceed the recommendation of Regulatory Guide 1.8, Revision 1-R, September 1975, or their equivalent as further clarified in Attachment 1 to the NRG Safety Evaluation Report enclosed with Amendment No. 46, dated July 12, 1982.

5.3.2 An NRG approved training and retraining program for the CERTIFIED FUEL HANDLERS shall be maintained.

Kewaunee Power Station 5.3-1 Amendment No. 215

5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures Procedures 5.4 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a.

The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b.

Deleted;

c.

Quality assurance for effluent and environmental monitoring;

d.

Fire Protection Program implementation; and

e.

All programs specified in Specification 5.5.

Kewaunee Power Station 5.4-1.

Amendment No. 215

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a.

The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b.

The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.1 and Specification 5.6.2.

c.

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(s) together with.the appropriate analyses or evaluations justifying the change(s); and b)

A determination that the change(s) maintain the levels of radioactive effluent control required by 1 O CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

2.

Shall become effective after the approval of the plant manager; and

3.

Shall be submitted to the NRG 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 in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2 Deleted Kewaunee Power Station 5.5-1 Amendment No. 215

5.5 Programs and Manuals (continued) 5.5.3 Radioactive Effluent Controls Program Programs and Manuals 5.5 This program conforms to 1 O CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents

. as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a.

limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration*

values in Appendix B, Table 2, Column 2 to 1 O CFR 20.1001-20.2402;

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d.

Limitations on the annual and quarterly doses or dose 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 dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

Determination of projected dose contribUtions from radioactive effluents in accordance with the methodology in the ODCM 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 in accordance with the following:.

1.

For noble gases: a dose rate::;; 500 mrem/yr to the whole body and a dose rate::;; 3000 mrem/yr to the skin; and

2.

For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate::;; 1500 mrem/yr to any organ; Kewaunee Power Station 5.5-2 Amendment No. 215

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.3 Radioactive Effluent Controls Program (continued) 5.5.4 5.5.5 5.5.6 5.5.7 5.5.8 5.5.9 5.5.10.

h.*

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit fo 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 iodine-131, iodine-133, 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.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program Surveillance Frequencies.

Deleted Deleted Deleted Deleted Deleted Deleted Storage Tank Radioactivity Monitoring Program This program provides controls for the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures."

The program shall include:

a.

A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Waste Disposal

System is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

Kewaunee Power Station 5.5-3 Amendment No. 215

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 5.5.11 5.5.12 5.5.13 5.5.14 5.5.15 5.5.16 Storage Tank Radioactivity Monitoring Program (continued)

The provisions of SR 3.0.2 are applicable to the Storage Tank Radioactivity Monitoring Program Surveillance Frequencies.

Deleted Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a.

Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1.

A change in the TS incorporated in the license; or

2.

A change to the updated USAR or Bases that requires NRC approval pursuant to 1 O CFR 50.59.

c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.

d.

Proposed changes that meet the criteria of Specification 5.5.12.b above shall.be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

Deleted Deleted Deleted Deleted Kewaunee Power Station 5.5-4 Amendment No. 215

5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements Reporting Requirements 5.6 The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the facility during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

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, as 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 th_e missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the facility in the previous year shall be submitted by May 1 of each year in accordance with 1 O CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

5.6.3 Deleted 5.6.4 Deleted 5.6.5 Deleted Kewaunee Power Station 5.6-1 Amendment No. 215

High Radiation Area 5.7 Kewaunee Power Station 5.7-1 Amendment 207 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a.

Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b.

Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess one of the following:

1.

A radiation monitoring device that continuously displays radiation dose rates in the area;

2.

A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint;

3.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area; or

4.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or

High Radiation Area 5.7 Kewaunee Power Station 5.7-2 Amendment 207 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

(ii)

Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a.

Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1.

All such door and gate keys shall be maintained under the administrative control of the shift manager, radiation protection manager, or his or her designees; and

2.

Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b.

Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

High Radiation Area 5.7 Kewaunee Power Station 5.7-3 Amendment 207 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

d.

Each individual group entering such an area shall possess one of the following:

1.

A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint;

2.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area; or

3.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i)

Be under surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area; or (ii)

Be under surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4.

In those cases where Specifications 5.7.2.d.2 and 5.7.2.d.3, above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

High Radiation Area 5.7 Kewaunee Power Station 5.7-4 Amendment 207 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

f.

Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

APPENDIX B ENVIRONMENTAL TECHNICAL SPECIFICATIONS FOR KEWAUNEE POWER STATION KEWAUNEE, WISCONSIN DOMINION ENERGY KEWAUNEE, INC.

DOCKET NUMBER 50-305 I

I

ENVIRONMENTAL TECHNICAL SPECIFICATIONS AND BASES APPENDIX B Section Title 1.0 Definitions 2.0 Environmental Protection Condition Page ES Deleted Deleted Deleted Deleted Deleted 2.2 Chemicals 2.2.1 Chlorination of Cirtulating Water Systems 2.2.2 Suspended and Diss6lved Solids 2.2.3 -Treatment Chemicals Monitoring Requirements Chemicals 3.2.1 Chlorination of Circulating Water System 3.2.2 Suspended and Dissolved Solids 3.2.3 Treatment Chemicals Deleted Deleted Deleted Deleted Deleted 4.0 Environmental Surveillance & Special Studies

4.1 Biological 4.1.1 Aquatic 4.2.2 De-icing Operation Deleted Deleted Deleted Deleted 5.0 Administrative Controls 5.1 Organization, Review and Audit 5.1.a Organization 5.1.b Review and Audit Deleted

'Deleted Deleted 5.2 Actions to be Taken in the Event of Violation of.the Environmental Technical Specifications Deleted Deleted 5.3 Operating Procedures Deleted 5.4 Plant 5.4.a 5.4.b 5.4.c 5.4.d 5.4.e Reporting Requirements.

Annual Environmental Operating Report Reporting Requirement -

24 Hours and Subsequent Two-Week Followup Repqrtl Reporting Requirement -

30 Days Changes to the Plant or Procedures General Reporting Requirements Deleted Deleted Deleted Deleted Deleted Deleted Deleted 5.5 Record 5.5.a 5.5.b Retention Record Retention -

5 Years Record Retention -

Life of Plant Deleted Deleted ES i Amendment No. 47

ML053040352

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