Letter Sequence Response to RAI |
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TAC:ME6169, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARHNP-11-001, Request for License Amendment, Measurement Uncertainty Recapture Power Uprate2011-04-28028 April 2011 Request for License Amendment, Measurement Uncertainty Recapture Power Uprate Project stage: Request ML11165A1862011-06-10010 June 2011 NRR E-mail Capture - FW: Acceptance Review for Harris 1 Measurment Uncertainity Recapture (Mur) TAC ME6169 Project stage: Acceptance Review ML11206A4962011-06-29029 June 2011 NRR E-mail Capture - Draft RAI Questions to Support Harris Mur Review (ME6169) Project stage: Draft RAI ML11181A0162011-07-0101 July 2011 Acceptance for Review of Measurement Uncertainty Recapture Power Uprate License Amendment Request Project stage: Acceptance Review ML11213A0002011-07-29029 July 2011 NRR E-mail Capture - Measurement Uncertainty Recapture Power Uprate - Mur RAI (HP-HPB)(ME6169) Project stage: RAI HNP-11-073, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request2011-08-0303 August 2011 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request Project stage: Response to RAI ML11213A1792011-08-0505 August 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML11214A0792011-08-0505 August 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML11214A1742011-08-0505 August 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI HNP-11-076, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request2011-08-15015 August 2011 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request Project stage: Response to RAI HNP-11-034, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2011-08-16016 August 2011 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Request HNP-11-079, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment2011-08-31031 August 2011 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Project stage: Response to RAI ML11256A0262011-09-0606 September 2011 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request Project stage: Response to RAI HNP-11-082, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request2011-09-0707 September 2011 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request Project stage: Response to RAI ML11272A0652011-09-28028 September 2011 NRR E-mail Capture - Additional Mur RAI (Emcb Part 2)(ME6169) Project stage: RAI ML11271A1652011-09-28028 September 2011 NRR E-mail Capture - Additional Mur RAI (EEB)(ME6169) Project stage: RAI ML1127300822011-09-30030 September 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML11276A1872011-09-30030 September 2011 NRR E-mail Capture - Mur RAI (Cvib)( ME6169) Project stage: RAI ML11276A1052011-10-14014 October 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML11276A1022011-10-14014 October 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML11278A1702011-10-14014 October 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML11276A1072011-10-18018 October 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Project stage: RAI HNP-11-095, Request for License Amendment Measurement Uncertainty Recapture Power Uprate Response to Request for Additional Information (RAI 9)2011-10-21021 October 2011 Request for License Amendment Measurement Uncertainty Recapture Power Uprate Response to Request for Additional Information (RAI #9) Project stage: Response to RAI HNP-11-107, Supplement to Request for License Amendment Measurement Uncertainty Recapture Power Update2011-11-28028 November 2011 Supplement to Request for License Amendment Measurement Uncertainty Recapture Power Update Project stage: Supplement HNP-11-097, Request for License Amendment - Measurement Uncertainty Recapture Power Uprate Supplemental Information2011-12-20020 December 2011 Request for License Amendment - Measurement Uncertainty Recapture Power Uprate Supplemental Information Project stage: Supplement HNP-12-002, Request for License Amendment Measurement Uncertainty Recapture Power Uprate Supplemental Information2012-02-0909 February 2012 Request for License Amendment Measurement Uncertainty Recapture Power Uprate Supplemental Information Project stage: Supplement HNP-12-044, Response to Request for Additional Information on License Amendment Request - Measurement Uncertainty Recapture Power Uprate2012-03-26026 March 2012 Response to Request for Additional Information on License Amendment Request - Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI HNP-12-069, Request for License Amendment Measurement Uncertainty Recapture Power Uprate Comments Re Amendment 1392012-06-0505 June 2012 Request for License Amendment Measurement Uncertainty Recapture Power Uprate Comments Re Amendment 139 Project stage: Request ML12157A2812012-06-11011 June 2012 Correction to Issuance of Amendment No. 139 Measurement Uncertainty Recapture Power Uprate Project stage: Approval 2011-08-16
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Category:Letter type:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
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Text
Christopher L.Burton Progress Energy Vice President Harris Nuclear Plant
$,,*AR 2 6 z
- Progress Energy Carolinas, Inc.
Serial: HNP-12-044 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63
Subject:
REQUEST FOR LICENSE AMENDMENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE REQUEST FOR ADDITIONAL INFORMATION RESPONSE RELATED TO REACTOR CORE SAFETY LIMITS
Reference:
Letter from C. L. Burton to the U.S. NRC, "REQUEST FOR LICENSE AMENDMENT, MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE," Serial HNP-I 1-001 dated April 28, 2011, ADAMS Accession No. ML11124A180 Ladies and Gentlemen:
By letter dated April 28, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., submitted a Request for License Amendment to the U.S.
Nuclear Regulatory Commission (NRC). The proposed amendment would increase the rated thermal power of Shearon Harris Nuclear Power Plant, Unit No. 1 (HNP) from 2,900 megawatts thermal (MWt) to 2,948 MWt, an increase of approximately 1.66 percent, and change the Technical Specifications (TS) accordingly. The proposed uprate is characterized as a measurement uncertainty recapture (MUR) using the Cameron Leading Edge Flow Meter (LEFM) CheckPlus System to improve plant calorimetric heat balance measurement accuracy.
In a telephone discussion with the NRC staff, the staff provided a request for additional information (RAI) related to proposed changes to the TS Reactor Core Safety Limits shown in Figure 2.1-1. The response to the request for additional information is provided in the enclosure to this letter.
This RAI response provides additional information to clarify the application, does not expand the scope of the application, and does not impact either the significant hazards consideration or the environmental consideration in the Request for License Amendment.
In accordance with 10 CFR 50.91(b), CP&L is providing the state of North Carolina with a copy of this response.
PO. Box 165 New Hill, NC 27562 T> 919.362.2502 F> 919.362.2095
U.S. Nuclear Regulatory Commission Page 2 HNP-12-044 This document contains no new regulatory commitments.
Please refer any questions regarding this submittal to Mr. David Corlett, Supervisor - HNP Li-cbnsing/Regulatory Programs, at (919) 362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on I[ 2 U 2017 1.
Sincerely,
Enclosure:
REQUEST FOR ADDITIONAL INFORMATION RESPONSE RELATED TO REACTOR CORE SAFETY LIMITS cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N.C. DENR Ms. A. T. Billoch Col6n, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
HNP-12-044 Enclosure SHEARON HARRIS NUCLEAR POWER PLANT / UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE REQUEST FOR ADDITIONAL INFORMATION RESPONSE RELATED TO REACTOR CORE SAFETY LIMITS
U.S. Nuclear Regulatory Commission Page 1 of 2 HNP- 12-044 Enclosure By letter dated April 28, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., submitted a Request for License Amendment to the U.S.
Nuclear Regulatory Commission (NRC). The proposed amendment would increase the rated thermal power of Shearon Harris Nuclear Power Plant, Unit No. 1 (HNP) from 2,900 megawatts thermal (MWt) to 2,948 MWt, an increase of approximately 1.66 percent, and change the Technical Specifications (TS) accordingly. The proposed uprate is characterized as a measurement uncertainty recapture (MUR) using the Cameron Leading Edge Flow Meter (LEFM) CheckPlus System to improve plant calorimetric heat balance measurement accuracy.
In a telephone discussion with the NRC staff, the staff provided a request for additional information related to proposed changes to the TS Reactor Core Safety Limits shown in Figure 2.1-1. The response to the request for additional information is provided below.
Question No. 1: What are the current and proposed (post-uprate) breakpoints for the three Reactor Core Safety Limit curves?
Response No. 1:
Technical Specification Figure 2.1-1 RCS Tave ('F)
Pressure (psig)
Fraction of Rated Power Proposed Current (Post-Uprate) 0 654.75 654.75 2375 0.96 626.91 625 1.2 604.59 599 0 645.25 645.25 2235 0.96 617.41 613 1.2 595.09 589 0 627 627 1960 0.96 599.16 598 1.2 576.84 575
U.S. Nuclear Regulatory Commission Page 2 of 2 HNP-12-044 Enclosure Question No.2: Describe the methodology for developing the new values.
Response No. 2:
The Reactor Core Safety Limit (RCSL) curves are a series of isobars in power and core average temperature (Tave) that establish the operating regions for these parameters, such that both Departure from Nucleate Boiling (DNB) in the core and hot leg saturation are avoided. The lower power or flatter region of the RCSL is established by the requirement that hot leg saturation must be prevented. The steeply-sloped, higher-power region is established by the requirement that the DNB limit must not be exceeded.
The lines are confirmed by a process that tests a sample of cases that vary pressure, power and Tave. A limiting axial power shape is used for the DNB calculation. The lines are drawn so that positive margin exists for the cases analyzed. Statistical combination of uncertainties for reactor coolant system temperature, power and pressure are in accordance with AREVA NP methodology EMF-92-08 1(P)(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors."
To create the proposed measurement uncertainty recapture (MUR) RCSLs, the process extrapolated the flatter line segment to the MUR 0.96 fractional power. Some cases failed due to DNB and the 0.96 fraction of rated power points were adjusted until a successful, positive margin was achieved.