Letter Sequence Other |
---|
|
|
MONTHYEARHNP-07-119, License Renewal Application, Amendment 2: Changes Resulting from Responses to Site Audit Questions Regarding Time-Limited Aging Analyses2007-08-31031 August 2007 License Renewal Application, Amendment 2: Changes Resulting from Responses to Site Audit Questions Regarding Time-Limited Aging Analyses Project stage: Other ML0808002432008-03-26026 March 2008 Audit Summary Regarding the License Renewal Application for the Shearon Harris Nuclear Power Plant, Unit 1 Project stage: Acceptance Review HNP-08-055, Submittal of Resolution of License Renewal Open Item2008-05-30030 May 2008 Submittal of Resolution of License Renewal Open Item Project stage: Other ML0823409852008-08-21021 August 2008 Safety Evaluation Report Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1 Project stage: Approval ML0829706582008-10-16016 October 2008 G20080710/LTR-08-0546/EDATS: SECY-2008-0599 - Ltr., William J. Shack, Report on the Safety Aspects of the License Renewal Application for the Shearon Harris Nuclear Power Plant, Unit 1 Project stage: Other ML0830302282008-12-0404 December 2008 G20080710/LTR-08-0546/EDATS: SECY- 2008-0599 - William J. Shack Ltr. Report on the Safety Aspects of the License Renewal Application for the Shearon Harris Nuclear Power Plant, Unit 1 Project stage: Other 2008-12-04
[Table View] |
|
---|
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
[Table view] |
Text
Progress Energy MAY 3 0 2008 SERIAL: HNP-08-055 10 CFR 54 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555
Subject:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / LICENSE NO. NPF-63 LICENSE RENEWAL - RESOLUTION OF OPEN ITEM AND LICENSE RENEWAL APPLICATION AMENDMENT 8
References:
- 1. Letter from Cornelius J. Gannon to the U. S. Nuclear Regulatory Commission (Serial: HNP-06-136), "Application for Renewal of Operating License," dated November 14, 2006
- 2. Letter from P. T. Kuo (NRC) to Robert J. Duncan II, "Safety Evaluation Report with Open Items Related to the License Renewal of the Shearon Harris Nuclear Power Plant, Unit 1," dated March 18, 2008 Ladies and Gentlemen:
On November 14, 2006, Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc., requested the renewal of the operating license for the Shearon Harris Nuclear Power Plant, Unit No. 1, also known as the Harris Nuclear Plant (HNP), to extend the term of its operating license an additional 20 years beyond the current expiration date.
By letter dated March 18, 2008, the Nuclear Regulatory Commission (NRC) issued the Safety Evaluation Report with Open Items Related to the License Renewal of the Shearon Harris Nuclear Power Plant, Unit 1. Section 1.5 of the report identified an Open Item for which resolution had not been achieved at the time the report was issued. This letter submits:
(1) information to close the Open Item and (2) changes to the HNP License Renewal Application (LRA) that support closure of the Open Item.
Therefore, this letter contains two enclosures. Enclosure 1 provides the information required to resolve the Open Item. Enclosure 2 is a table that provides the changes to the LRA; the changes constitute LRA Amendment 8. The information provided in this letter does not affect any of the License Renewal Commitments; therefore, any actions identified in this letter should be considered intended or planned actions; they are included for informational purposes but are not considered to be regulatory commitments.
Progress Energy Carolinas, Inc.
Harris Nuclear Plant / (2f P. 0. Box 165 New Hill, NC 27562 O'e4-
Document Control Desk HNP-08-055 / Page 2 Please refer any questions regarding this submittal to Mr. Roger Stewart, Supervisor -
License Renewal, at (843) 857-5375.
I declare, under penalty of perjury, that the foregoing is true and correct (Executed on MAY 3 0 2008)
Sincerely, Christopher L. Burton Director - Site Operations Harris Nuclear Plant CLB/mhf
Enclosures:
- 1. Resolution of License Renewal Open Item
- 2. Amendment 8 Changes to the License Renewal Application cc:
Mr. P. B. O'Bryan (NRC Senior Resident Inspector, HNP)
Ms. B. 0. Hall (Section Chief, N.C. DENR)
Mr. M. L. Heath (NRC License Renewal Project Manager, HNP)
Ms. M. G. Vaaler (NRC Project Manager, HNP)
Mr. L. A. Reyes (NRC Regional Administrator, Region II)
HNP-08-055 Enclosure 1 Page 1 of 2 Resolution of License Renewal Open Item
Background
On November 14, 2006, Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc., submitted a License Renewal Application (LRA) and requested renewal of the operating license for the Shearon Harris Nuclear Power Plant, Unit No. 1, also known as the Harris Nuclear Plant (HNP), to extend the term of its operating license an additional 20 years beyond the current expiration date.
By letter dated March 18, 2008, the Nuclear Regulatory Commission (NRC) issued the Safety Evaluation Report (SER) with Open Items Related to the License Renewal of the Shearon Harris Nuclear Power Plant, Unit 1. Section 1.5 of the report identified an Open Item (01) for which resolution had not been achieved at the time the SER was issued. A statement of the 01 is provided below followed by information required to resolve it.
Open Item 2.2 (Section 2.2 Plant Level Scoping Results)
In LRA Section 2.3.4.6, Feedwater System, the applicant did not identify the feedwater isolation function in scope for license renewal under 10 CFR 54.4 (a)(1). In Section 15.1.5 of the applicants FSAR, it states that the feedwater isolation valves and regulating valves provide a safety-related function, isolation of feedwater in the event of a main steam line break. The staff s position is that the FSAR description of the feedwater isolation and regulating valves meet the criteria defined by 10 CFR 54.4(a)(1). In response to RAI 2.1.1.2-1, the applicant stated that based on their evaluation the feedwater regulating and bypass valves, these valves do not meet the license renewal definition of safety-related as stated in 10 CFR 54.4(a)(.1); however, the components are included within the scope of license renewal for 10 CFR 54.4(a)(2). The staff found the applicants answer to RAI response 2.1.1.2-1 inconsistent with 10 CFR 54.4 (a)(1).
In RAI 2.3.4.6-2 the staff asked the applicant to further evaluate the classification of this equipment and justify their position. The applicant's response, dated January 22, 2008, maintains that these valves are important to safety, but are not safety-related; therefore, they only meet the criteria of 10 CFR 54.4(a)(2). The staff s position remains that the main feedwater regulating and bypass valves, by definition, fulfill a safety-related function; therefore, they should be included in scope under 10 CFR 54.4(a)(1). In addition, the function to provide main feedwater isolation should be included in scope under 10 CFR 54.4(a)(1) for Section 2.3.4.6, to include the main feedwater isolation valves and the regulating and bypass valves. This is 01 2.2.
Response to Open Item 2.2 In the previous response to this issue, provided by Progress Energy letter to the NRC (Serial:
HNP-08-006), dated January 22, 2008, the function and qualifications of the Feedwater Regulating Valves (FRVs) and FRV Bypass Valves within the HNP Current Licensing Basis (CLB) were recounted. The HNP CLB permits the backup isolation of main feedwater flow to steam generators, under certain assumed conditions following a postulated main steam line
HNP-08-055 Enclosure 1 Page 2 of 2 rupture, to be accomplished by non-safety grade components. This aspect of the CLB is based on guidance provided by the HNP Nuclear Steam System Supplier (Westinghouse) and regulatory guidance documented in the Acceptance Criteria of Section 15.1.5 of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants."
Application of this guidance to system design is more fully discussed in Issue No. 1 of NUREG-0138, "Staff Discussion of Fifteen Technical Issues Listed in Attachment to November 3, 1976 Memorandum from Director, NRR to NRR Staff." NUREG-0800 was used by the NRC staff in the licensing review of 1{NP, and Section 10.4.7 of NUREG-1038, "Safety Evaluation Report Related to the Operation of Shearon Harris Nuclear Power Plant Units 1 and 2," November 1983, states that the FRVs are Quality Group D components, i.e., not fully safety grade.
Based on the functions and qualifications of the FRVs and FRV Bypass Valves in the HNP CLB, the License Renewal scoping evaluation for these components concluded that they were properly included in scope under 10 CFR 54.4(a)(2), that is, non-safety related systems, structures, and components (SSCs) whose failure could prevent the satisfactory accomplishment of any safety related functions.
The HNP License Renewal Application states that the License Renewal methodology used at HNP is consistent with the approach recommended in NEI 95-10, "Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule," Revision 6.
When applying the guidance for scoping safety related SSCs of NEI 95-10, the HNP scoping methodology focused on: (1) assuring that the definition used during design and operation of HNP to identify safety related SSCs was consistent with the definition provided in 10 CFR Part 54 and (2) identifying cases where SSCs had been classified safety related but did not actually perform a safety related function in accordance with 10 CFR 54.4(a)(1). Guidance for these activities is provided in NEI 95-10; however, guidance is not provided for the situation where a safety related function could be accomplished by non-safety grade components as permitted by the HNP CLB. Therefore, the HNP scoping process relied on the CLB and not on the guidance provided in NEI 95-10 to make a final determination that these SSCs were not safety related under 10 CFR 54.4(a)(1). This is considered to be an exception to the scoping methodology described in Section 3.1.1 of NEI 95-10.
Based on the preceding discussion, the License Renewal conclusion that these non-safety grade components meet the criteria of 10 CFR 54.4(a)(2) is consistent with the HNP CLB.
Based on the above response, a License Renewal Application amendment is required to include the feedwater isolation function in the discussion of the Feedwater System and to note that the scoping methodology for HNP takes an exception to the guidance of NEI 95-10.
HNP-08-055 Enclosure 2 Page 1 of 1 Amendment 8 Changes to the License Renewal Application Source of License Renewal Application (LRA) Amendment 8 Changes Change Resolution of Add the following sentence after the first sentence of paragraph two of LRA Section 2.0:
Open Item-2.2 Exceptions to the scoping guidance of NEI 95-10 has been taken consistent with the I-INP Current Licensing Basis.
Revise LRA Subsection 2.3.4.6 on Page 2.3-248 by revising the first full paragraph to read:
The system serves no safety function, with the exceptions of containment isolation integrity and termination of feedwater flow following certain main steam line break accidents; and is therefore generally classified as non-safety related. The portion of the system classified as safety related is the portion from the feedwater header check valves to the Steam Generators.
Also, revise the first row of the table of intended functions in the fourth paragaph to read:
10 CFR54.4(a)(1)
- Supports the containment isolation function, and
- Supports post-accident monitoring.