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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SERIAL: HNP- 11-082
~j Progress Energy 10 SFP 0 V7 201 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST
References:
- 1. Email from B. Mozafari, Nuclear Regulatory Commission, to J. Caves, "MUR RAI (Mat)(ME6169)," dated August 8, 2011.
- 2. Letter from C. L. Burton to the Nuclear Regulatory Commission (Serial:
HNP-1 1-001), "Shearon Harris Nuclear Power Plant, Unit 1, Docket No.
50-400/Renewed License No. NPF-63, Request for License Amendment, Measurement Uncertainty Recapture Power Uprate," dated April 28, 2011.
(ADAMS Accession ML11124A180)
Ladies and Gentlemen:
On August 8, 2011, the Harris Nuclear Plant (HNP) received a request from the NRC (Reference
- 1) for additional information needed to facilitate the review of the License Amendment Request to increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66 percent. The proposed uprate is characterized as a measurement uncertainty recapture using the Cameron Leading Edge Flow Meter CheckPlus System to improve plant calorimetric heat balance measurement accuracy. This original request was submitted as Serial: HNP- 11-001 (Reference 2).
The Enclosure to this submittal contains HNP's response to the NRC's request for additional information.
This document contains no new Regulatory Commitment.
In accordance with 10 CFR 50.91 (b), HNP is providing the state of North Carolina with a copy of this response.
Please refer any questions regarding this submittal to Mr. David Corlett, Supervisor - HNP Licensing/Regulatory Programs, at (919) 362-3137.
Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 ý. * .
Serial: HNP-11-082 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on Sincerely, Keith Holbrook Manager - Support Services Harris Nuclear Plant RKHikab
Enclosure:
Response to Request for Additional Information cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief, N.C. DENR Mr. V. M. McCree, NRC Regional Administrator, Region II Mrs. B. L. Mozafari, NRC Project Manager, HNP
Enclosure to SERIAL: HNP- 11-082 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Summary By letter dated April 28, 2011, (ADAMS Accession No. ML11124A180), Carolina Power &
Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment will increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification (TS) changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66 percent. 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. The proposed change will revise Renewed Operating License NPF-63 Maximum Power Level; Appendix A, TS definition of RTP; Reactor Core Safety Limits; Reactor Trip System Instrumentation; Minimum Allowable Power Range Neutron Flux high setpoint with Inoperable Steam Line Safety Valves; and TS Bases Section 3/4.7.1 to reflect the uprated reactor core power level.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information submitted by the licensee, and based on this review determined the following information is required to complete the evaluation of the subject amendment request:
Request 1:
Section II.2.40.b, Short-term LOCA Mass andEnergy Release Analysis, page 56, states that
"...HNP is approved for leak-before-break, so Case 1 through 5 breaks [hot and cold leg pipe and pump suction breaks] have been eliminated and only breaks in the largest branch lines (Cases 6 and 7) require evaluation... Since RCS piping breaks have been eliminated by the leak-before-break methodology... the only breaks evaluated for the power uprate are those in the pressurizer subcompartment (pressurizer surge line and pressurizer spray line breaks)..."
The NRC staff notes that the dynamic effects of the LBB pipe break should still be considered in the containment design as stated in the Statement of Consideration of the final rule to modify General Design Criterion 4, dated April 11, 1986 (51 FR 12502). Clarify why the dynamic effect for pipe breaks in Cases I through 5 have been eliminated and not evaluated for the impact of the power uprate on the containment design.
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Enclosure to SERIAL: HNP-1 1-082 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST
Response
Cases 1 through 5 are breaks that were analyzed. for subcompartment analyses prior to the revision to general. design criteria (GDC) 4 that allowed leak-before-break (LBB) technology to be applied to the dynamic effects of high energy line breaks in containment subcompartments.
Please note that large breaks in the reactor ccoolant system (RCS) piping are still used to calculate the global pressure (Reference 1) internal, to: the containment. However, the revision to GDC-4 has allowed application of LBB to breaks within a containment subcompartment if that subcompartment does not provide a containment related function (Reference 2). Dry containments such as the HNP containment do not rely on the subcompartments for long-term containment cooling post loss-of-coolant accident (LOCA). Therefore, application of LBB technology, that limits the break size within a subcompartment, has been accepted by the NRC and has been the industry practice subsequent to revising GDC-4.
Note that the subcompartments at HNP were designed. prior to the -revision to GDC-4 and thus were designed to accommodate breaks in the largest high energy piping within a given subcompartment, including the double ended severance of the main RCS piping. Application of LBB for the MUR continues to meet the recommended margins, which eliminates the need for full reanalysis of the subcompartments.
References:
- 1) Federal Register Notice 53 FR No.66 Page 11311, "Leak Before Break Technology Solicitation of Public Comment on Additional Applications," April 06, 1988.
- 2) NRC Inspection Manual, Part 9900: 10 CFR Guidance, "Definition of Leak-Before-Break Analysis and its Application to Plant Piping Systems," Change Notice 96-020, September 26, 1996.
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Enclosure to SERIAL: HNP-1 1-082 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Request 2:
Section IV. 1 .B.vii.2, Leak-Before-Break Evaluation, page 94, states that "... [t]he leak-before-break acceptance criteria are based on SRP Section 3.6.3. The acceptance criteria are satisfied for primary loop piping at power uprate conditions. The recommended margins are satisfied, and the existing analyses conclusions !remainvalid. Therefore, the dynamic effects of RCS primary loop piping breaks are not consideriedin: the structural design basis at-MUR power uprate conditions..."
(a) Discuss in detail exactly how the acceptance 'criteria and the recommended margins are shown to be satisfied, and how the existing analyses conclusions remain Valid for primary loop piping at power uprate conditions.
(b) Clarify which structural design basis will not include the dynamic effects of RCS primary loop piping breaks at MUR power uprate conditions and for what components.
Response:.
(a) A Leak-Before-Break (LBB) evaluation for the HNP primary loop piping due to the MUR power uprate was performed using the recommendations and criteria proposed in NRC Standard Review Plan (SRP) Section 3.6.3, "Leak-Before-Break Evaluation Procedures."
The applicable pipe loadings, normal operating pressure, and temperature parameters at MUR power uprate conditions were used to evaluate LBB. The evaluation result shows that the LBB acceptance criteria (margin of 10,on Leak Rate, margin of 2.0 on Flaw Size and margin of 1.0 on Loads, using absolute summation method for faulted load combination) are satisfied at MUR power uprate conditions. The LBB acceptance criteria are satisfied and therefore, the existing analyses conclusion to eliminate the dynamic effects of reactor coolant system (RCS) primary loop piping breaks from the structural design basis remain valid at MUR power uprate conditions.
(b) The structural design basis of RCS primary loop piping breaks at MUR power uprate conditions has been eliminated for all applicable components.
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Enclosure to SERIAL: HNP-11-082 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO:. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Request 3:
(a) List all piping that have been approved for LBB (LBB piping).
(b) List all approved LBB piping that contain nickel-basedAlloy 82/182 dissimilar metal welds which are susceptible to primary water stress corrosion cracking.
(c) If mitigation has been implemented on the: subject welds, discuss whether the original LBB evaluation has been updated per NRC Regulatory Issue Summary 2010-07.
(d) If the mitigation has not been implemented, discuss plans to mitigate the subject welds. If mitigation is not planned, provide justification.
Response
(a) Leak-Before-Break (LBB) only impacts the HNP reactor coolant system (RCS) primary loop piping.
(b) Alloy 82/182 dissimilar metal (DM) welds are present in the RCS primary loop piping at the reactor vessel (RV) hot leg and cold leg nozzle connections to the reactor coolant loop piping.
(c) During Refueling Outage 16 (RFO-16) in the fall of 2010, HNP mitigated the RV nozzle hot leg Alloy 82/182 DM welds via the mechanical stress improvement process (MSIP).
Regulatory Issue Summary 2010-07 (RIS 2010-07) states that "Licensees may install mechanical stress improvement without NRC authorization since it does not affect the Code design or inspection requirements." RIS 2010-07 also states that "Mechanical stress improvement and Alloy 52 inlays and onlays would not substantially change the weld geometry or the original design-basis assumptions of the weld and, therefore, likely would not invalidate the original LBB analyses submitted to the NRC for approval." The original HNP LBB evaluation has been updated to show that all LBB margins are satisfied in the HNP primary loop including the Alloy 82/182 weld locations after the MSIP application and that the LBB evaluation continues to be valid.
(d) HNP mitigated the three hot leg nozzle DM welds during RFO-16. The three cold leg nozzle DM welds are mandated to be inspected during RFO-17 (spring 2012).
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I I I Enclosure to SERIAL: HNP- 11-082 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST There is no requirement to mitigate either the hot leg or cold leg DM welds during either outage. HNP decided to mitigate the hot leg DM welds during RFO-16 to reduce the risk of a future unplanned outage due to primary water stress corrosion cracking (PWSCC), which is prevalent in DM welds at hot leg temperatures. To date the PWR Industry has not experienced PWSCC in the RV nozzle cold leg I)M welds.
The experience gained during the RFO-16 hot leg~mitigation will become useful if-it is decided to mitigate the cold leg nozzle DM welds in the future. It isrecognized ,that the cold legs are more challenging to mitigate due to existing interferences in the RV Gallery.
This RFO-16 MSIP experience will: be used to plan a successf a nf o g mitiatioful and effirioj idcf lege.itf mitigation project if implemented in the futuire!". .. °-"' .. "
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