NLS2016002, Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.

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Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.
ML16076A433
Person / Time
Site: Cooper Entergy icon.png
Issue date: 03/11/2016
From: Limpias O
Nebraska Public Power District (NPPD)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2016002
Download: ML16076A433 (12)
v • d • e


Text

N Nebraska Public Power District Alwa*ys there when you need us 50.90 NLS201 6002 March 11, 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Application to Revise Technical Specifications to Adopt TSTF-535, "Revise Shutdown Margin Definition to Address Advanced Fuel Designs" Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46

Dear Sir or Madam:

In accordance with the provisions of Title 10 of the Code of Federal Regulations Part 50.90 (10 CFR 50.90), "Application for Amendment of License, Construction Permit, or Early Site Permit," Nebraska Public Power District (NPPD) requests an amendment to Facility Operating License DPR-46 to revise the Cooper Nuclear Station (CNS) Technical Specifications (TS). The proposed amendment would modify the TS definition of "Shutdown Margin" (SDM) to require calculation of the SDM at a reactor moderator temperature of 68°F or a higher temperature that represents the most reactive state throughout the operating cycle. This change is needed to address new Boiling Water Reactor fuel designs which may be more reactive at shutdown temperatures above 68 0 F. provides a description and assessment of the proposed change. Attachment 2 provides existing TS pages marked up to show the proposed change. Attachment 3 provides revised (clean) TS pages.

NPPD requests approval of the proposed amendment by March 11, 2017. Upon receipt of the approved amendment, CNS will implement the change within 60 days.

This proposed TS change has been reviewed by the necessary safety review committees (Station Operations Review Committee and Safety Review and Audit Board). Amendments to the CNS Facility Operating License through Amendment 253 issued January 22, 2016, have been incorporated into this request. This request is submitted under oath or affirmation pursuant to 10 CFR 50.30(b).

P.O. Box 98 /Brownville, NE 6832 1-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 ww.nppd .com

NLS20 16002 Page 2 of 2 By copy of this letter and its attachments, the appropriate State of Nebraska official is notified in accordance with 10 CFR 50.91 (b)(1). Copies are also being provided to the Nuclear Regulatory Commission Region IV office and the CNS Senior Resident Inspector in accordance with 10 CFR 50.4(b)(1).

This letter contains no new regulatory commitments. Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: /t\is (Date)

Vice President-Nuclear and Chief Nuclear Officer

/ho Attachments: 1. Description and Assessment

2. Proposed Technical Specification Changes (Markup)
3. Proposed Technical Specification Pages (Re-Typed) cc: Regional Administrator w/attachments Nebraska Health and Human Services w/attachments USNRC - Region IV Department of Regulation and Licensure Cooper Project Manager w/attachments NPG Distribution w/o attachments USNRC - NRR Project Directorate IV- 1 Senior Resident Inspector w/attachments CNS Records w/attachments USNRC - CNS

NLS201 6002 Page 1 of 4 Attachment 1 Description and Assessment Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 1.0 Description 2.0 Assessment 2.1 Applicability of Published Safety Evaluation 2.2 Optional Changes and Variations 3.0 Regulatory Analysis 3.1 No Significant Hazards Consideration Determination 3.2 Conclusions 4.0 Environmental Consideration 5.0 Reference

NLS2016002 Page 2 of 4

1.0 DESCRIPTION

The proposed amendment modifies the Technical Specifications (TS) definition of "Shutdown Margin" (SDM) to require calculation of the SDM at a reactor moderator temperature of 68°F or a higher temperature that represents the most reactive state throughout the operating cycle. This change is needed to address new Boiling Water Reactor fuel designs which may be more reactive at shutdown temperatures above 68°F.

2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation Nebraska Public Power District (NPPD) has reviewed the model safety evaluation dated February 26, 2013, (Reference) as part of the Federal Register Notice of Availability. This review included a review of the Nuclear Regulatory Commission (NRC) staff's evaluation, as well as the information provided in TSTF-535. NPPD has concluded that the justifications presented in the TSTF-535 proposal and the model safety evaluation prepared by the NRC staff are applicable to Cooper Nuclear Station and justify this amendment for the incorporation of the changes to the Cooper Nuclear Station TS.

2.2 Optional Changes and Variations NPPD is not proposing any variations or deviations from the TS changes described in the TSTF-535, Revision 0, or the applicable parts of the NRC staff's model safety evaluation dated February 26, 2013.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Nebraska Public Power District (NPPD) requests adoption of TSTF-535, Revision 0, "Revise Shutdown Margin Definition to Address Advanced Fuel Designs," which is an approved change to the standard technical specifications, into the Cooper Nuclear Station Technical Specifications (TS). The proposed amendment modifies the TS definition of "Shutdown Margin" (SDM) to require calculation of the SDM at a reactor moderator temperature of 680 F or a higher temperature that represents the most reactive state throughout the operating cycle.

NLS2016002 Page 3 of 4 NPPD has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed change revises the definition of SDM. SDM is not an initiator to any accident previously evaluated. Accordingly, the proposed change to the definition of SDM has no effect on the probability of any accident previously evaluated. SDM is an assumption in the analysis of some previously evaluated accidents and inadequate SDM could lead to an increase in consequences for those accidents. However, the proposed change revises the SDM definition to ensure that the correct SDM is determined for all fuel types at all times during the fuel cycle. As a result, the proposed change does not adversely affect the consequences of any accident previously evaluated.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change revises the definition of SDM. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operations. The change does not alter assumptions made in the safety analysis regarding SDM.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed change revises the definition of SDM. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The proposed change ensures that the SDM assumed in determining safety limits, limiting safety system

NLS2016002 Page 4 of 4 settings or limiting conditions for operation is correct for all Boiling Water Reactor fuel types at all times during the fuel cycle.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, NPPD concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

3.2 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4.0 ENVIRONMENTAL CONSIDERATION

The proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

5.0 REFERENCE Federal Register Notice, Notice of Availability, dated February 26, 2013 (Volume 78 /

Number 38)

NLS2016002 Page 1 of 3 Attachment 2 Proposed Technical Specification Changes (Markup)

Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Technical Specification Pages 1.1-4 1.1-5

Definitions 1.1 1.1 Definitions LOGIC SYSTEM FUNCTIONAL from as close to the sensor as practicable up to, TEST but not including, the actuated device, to verify (continued) OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio (CPR)

RATIO (MCPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY A system, subsystem, division, 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, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2419 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time segment SYSTEM (RPS) RESPONSE from the time the sensor contacts actuate to the time the TIME scram solenoid valves deenergize.

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritica asmigthat:

a. The reactor is xenon free; tthroughout the operating cycle[

(continued)

Amcndmeont 231 1.1-4 Gn7/9 8/N IAmendment No.

Definitions 1.1

/._,corresponding to theI 1.1 Definitions most reactive state SHUTDOWN MARGIN (SDM) b. The moderator temperaturji_*68°o, and (continued)

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM.

STAGGERED TEST BASIS 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.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME consists RESPONSE TIME of two components:

a. The time from initial movement of the main turbine stop valve or control valve until 80%

of the turbine bypass capacity is established; and

b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

Cooper 1.1-5 Coopr 11-5Amendment No. 1-}7-

NLS201 6002 Page 1 of 3 Attachment 3 Proposed Technical Specification Pages (Re-Typed)

Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Technical Specification Pages 1.1-4 1.1-5

Definitions 1.1 1.1 Definitions LOGIC SYTEM FUNCTIONAL from as close to the sensor as practicable up to, TEST but not including, the actuated device, to verify (continued) OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio (CPR)

RATIO (MCPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY A system, subsystem, division, 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, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2419 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time segment from SYSTEM (RPS) RESPONSE the time the sensor contacts actuate to the time the scram TIME solenoid valves deenergize.

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:

a. The reactor is xenon free; (continued)

Cooper 1.1-4 Cooper1.1-4Amendment No.

Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN (SDM) b. The moderator temperature is > 68°F, corresponding to (continued) the most reactive state; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED TEST BASIS 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.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME RESPONSE TIME consists of two components:

a. The time from initial movement of the main turbine stop valve or control valve until 80% of the turbine bypass capacity is established; and
b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

Cooper 1.1-5 Cooper1.1-5Amendment No.

N Nebraska Public Power District Alwa*ys there when you need us 50.90 NLS201 6002 March 11, 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Application to Revise Technical Specifications to Adopt TSTF-535, "Revise Shutdown Margin Definition to Address Advanced Fuel Designs" Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46

Dear Sir or Madam:

In accordance with the provisions of Title 10 of the Code of Federal Regulations Part 50.90 (10 CFR 50.90), "Application for Amendment of License, Construction Permit, or Early Site Permit," Nebraska Public Power District (NPPD) requests an amendment to Facility Operating License DPR-46 to revise the Cooper Nuclear Station (CNS) Technical Specifications (TS). The proposed amendment would modify the TS definition of "Shutdown Margin" (SDM) to require calculation of the SDM at a reactor moderator temperature of 68°F or a higher temperature that represents the most reactive state throughout the operating cycle. This change is needed to address new Boiling Water Reactor fuel designs which may be more reactive at shutdown temperatures above 68 0 F. provides a description and assessment of the proposed change. Attachment 2 provides existing TS pages marked up to show the proposed change. Attachment 3 provides revised (clean) TS pages.

NPPD requests approval of the proposed amendment by March 11, 2017. Upon receipt of the approved amendment, CNS will implement the change within 60 days.

This proposed TS change has been reviewed by the necessary safety review committees (Station Operations Review Committee and Safety Review and Audit Board). Amendments to the CNS Facility Operating License through Amendment 253 issued January 22, 2016, have been incorporated into this request. This request is submitted under oath or affirmation pursuant to 10 CFR 50.30(b).

P.O. Box 98 /Brownville, NE 6832 1-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 ww.nppd .com

NLS20 16002 Page 2 of 2 By copy of this letter and its attachments, the appropriate State of Nebraska official is notified in accordance with 10 CFR 50.91 (b)(1). Copies are also being provided to the Nuclear Regulatory Commission Region IV office and the CNS Senior Resident Inspector in accordance with 10 CFR 50.4(b)(1).

This letter contains no new regulatory commitments. Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: /t\is (Date)

Vice President-Nuclear and Chief Nuclear Officer

/ho Attachments: 1. Description and Assessment

2. Proposed Technical Specification Changes (Markup)
3. Proposed Technical Specification Pages (Re-Typed) cc: Regional Administrator w/attachments Nebraska Health and Human Services w/attachments USNRC - Region IV Department of Regulation and Licensure Cooper Project Manager w/attachments NPG Distribution w/o attachments USNRC - NRR Project Directorate IV- 1 Senior Resident Inspector w/attachments CNS Records w/attachments USNRC - CNS

NLS201 6002 Page 1 of 4 Attachment 1 Description and Assessment Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 1.0 Description 2.0 Assessment 2.1 Applicability of Published Safety Evaluation 2.2 Optional Changes and Variations 3.0 Regulatory Analysis 3.1 No Significant Hazards Consideration Determination 3.2 Conclusions 4.0 Environmental Consideration 5.0 Reference

NLS2016002 Page 2 of 4

1.0 DESCRIPTION

The proposed amendment modifies the Technical Specifications (TS) definition of "Shutdown Margin" (SDM) to require calculation of the SDM at a reactor moderator temperature of 68°F or a higher temperature that represents the most reactive state throughout the operating cycle. This change is needed to address new Boiling Water Reactor fuel designs which may be more reactive at shutdown temperatures above 68°F.

2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation Nebraska Public Power District (NPPD) has reviewed the model safety evaluation dated February 26, 2013, (Reference) as part of the Federal Register Notice of Availability. This review included a review of the Nuclear Regulatory Commission (NRC) staff's evaluation, as well as the information provided in TSTF-535. NPPD has concluded that the justifications presented in the TSTF-535 proposal and the model safety evaluation prepared by the NRC staff are applicable to Cooper Nuclear Station and justify this amendment for the incorporation of the changes to the Cooper Nuclear Station TS.

2.2 Optional Changes and Variations NPPD is not proposing any variations or deviations from the TS changes described in the TSTF-535, Revision 0, or the applicable parts of the NRC staff's model safety evaluation dated February 26, 2013.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Nebraska Public Power District (NPPD) requests adoption of TSTF-535, Revision 0, "Revise Shutdown Margin Definition to Address Advanced Fuel Designs," which is an approved change to the standard technical specifications, into the Cooper Nuclear Station Technical Specifications (TS). The proposed amendment modifies the TS definition of "Shutdown Margin" (SDM) to require calculation of the SDM at a reactor moderator temperature of 680 F or a higher temperature that represents the most reactive state throughout the operating cycle.

NLS2016002 Page 3 of 4 NPPD has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed change revises the definition of SDM. SDM is not an initiator to any accident previously evaluated. Accordingly, the proposed change to the definition of SDM has no effect on the probability of any accident previously evaluated. SDM is an assumption in the analysis of some previously evaluated accidents and inadequate SDM could lead to an increase in consequences for those accidents. However, the proposed change revises the SDM definition to ensure that the correct SDM is determined for all fuel types at all times during the fuel cycle. As a result, the proposed change does not adversely affect the consequences of any accident previously evaluated.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change revises the definition of SDM. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operations. The change does not alter assumptions made in the safety analysis regarding SDM.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed change revises the definition of SDM. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The proposed change ensures that the SDM assumed in determining safety limits, limiting safety system

NLS2016002 Page 4 of 4 settings or limiting conditions for operation is correct for all Boiling Water Reactor fuel types at all times during the fuel cycle.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, NPPD concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

3.2 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4.0 ENVIRONMENTAL CONSIDERATION

The proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

5.0 REFERENCE Federal Register Notice, Notice of Availability, dated February 26, 2013 (Volume 78 /

Number 38)

NLS2016002 Page 1 of 3 Attachment 2 Proposed Technical Specification Changes (Markup)

Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Technical Specification Pages 1.1-4 1.1-5

Definitions 1.1 1.1 Definitions LOGIC SYSTEM FUNCTIONAL from as close to the sensor as practicable up to, TEST but not including, the actuated device, to verify (continued) OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio (CPR)

RATIO (MCPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY A system, subsystem, division, 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, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2419 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time segment SYSTEM (RPS) RESPONSE from the time the sensor contacts actuate to the time the TIME scram solenoid valves deenergize.

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritica asmigthat:

a. The reactor is xenon free; tthroughout the operating cycle[

(continued)

Amcndmeont 231 1.1-4 Gn7/9 8/N IAmendment No.

Definitions 1.1

/._,corresponding to theI 1.1 Definitions most reactive state SHUTDOWN MARGIN (SDM) b. The moderator temperaturji_*68°o, and (continued)

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM.

STAGGERED TEST BASIS 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.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME consists RESPONSE TIME of two components:

a. The time from initial movement of the main turbine stop valve or control valve until 80%

of the turbine bypass capacity is established; and

b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

Cooper 1.1-5 Coopr 11-5Amendment No. 1-}7-

NLS201 6002 Page 1 of 3 Attachment 3 Proposed Technical Specification Pages (Re-Typed)

Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Technical Specification Pages 1.1-4 1.1-5

Definitions 1.1 1.1 Definitions LOGIC SYTEM FUNCTIONAL from as close to the sensor as practicable up to, TEST but not including, the actuated device, to verify (continued) OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio (CPR)

RATIO (MCPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY A system, subsystem, division, 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, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2419 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time segment from SYSTEM (RPS) RESPONSE the time the sensor contacts actuate to the time the scram TIME solenoid valves deenergize.

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:

a. The reactor is xenon free; (continued)

Cooper 1.1-4 Cooper1.1-4Amendment No.

Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN (SDM) b. The moderator temperature is > 68°F, corresponding to (continued) the most reactive state; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED TEST BASIS 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.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME RESPONSE TIME consists of two components:

a. The time from initial movement of the main turbine stop valve or control valve until 80% of the turbine bypass capacity is established; and
b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

Cooper 1.1-5 Cooper1.1-5Amendment No.

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