Letter Sequence Response to RAI |
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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
[Table view] |
Text
aj Progress Energy FE13 13 2006 Serial: HNP-06-026 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR AD1I1TIONAL INFORMATION (RAI) REGARDING THE ONE-YEAR SPECIAL REPORT FOR THE STEAM GENERATOR TUBE INSERVICE INSPECTION RESULTS Ladies and Gentlemen:
On December 6, 2005, the NRC requested addition information to facilitate the review of the Special Report dated August 1, 2005 (HNP-05-088), which docLImented the results of the steam generator (SG) tube inservice inspections performed during the May 2004 mid-cycle outage.
Attachment 1 provides the requested additional information.
Please refer any question regarding this submittal to Mr. Dave Corlett at (919) 362-3137.
Sincerely, D. H. Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/jpy
Attachment:
- 1. Response to the Request For Additional Information (RAI) Regarding the Special Report dated August 1, 2005 (HNP-05-088) c:
Mr. R. A. Musser, NRC Senior Resident Inspector Mr. C. P. Patel, NRC Project Manager Dr. W. D. Travers, NRC Regional Administrator Progress Energy Carolinas, Inc. p i4 Harris Nuclear Plant P.O.Box 165 New Hill, NC 27562
Attachment 1 to SERIAL: HNP-06-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING THE SPECIAL REPORT DATED AUGUST 1, 2005 (HNP-05-088)
Request 1:
During your 2004 mid-cycle steam generatortube inspections, you re-analyzed all of the steam generator tube bobbin coil eddy current data obtained during refueling outage 11 (RFO 11), which were performed in 2003.
- a. Please clarify the extent of this re-analysis (e.g., from tube-end to tube-end for 100% of the tubes).
- b. In addition, discuss the extent to which you used a turbo mix during this re-analysis effort and whether you performed subsequent rotating probe examination of any indications identified in the turbo-mix. This re-analysis identified one tube which you estimated to be 37% through-wall. An independent analysis of this data by the NRC staff resulted in a size estimate of 40% through-wall. The staff recognizes the potential uncertainties in sizing the indication with the bobbin coil; however, the size of the indication is important in determining the classification of the inspection results which is used in determining the inspection frequency. Please clarify the inspection categorization (i.e., C-1, C-2, and C-3) of your 2003 outage.
- c. In addition, you classified the results of your 2004 inspection as Category C-1. This classification was made based on the results of inspections performed after plugging three tubes that were damaged by a foreign object.
The estimated depths of the degradation in these tubes were in excess of 40% through-wall. The classification of the results from the three tubes plugged during your 2004 outage was not provided (e.g., C-3) in your 2004 inspection summary reports.
- d. The inspection results classification from the 2003 and 2004 outage could affect future inspection intervals. As a result, please discuss your future inspection plans for the steam generator (i.e., do you plan to continue performing inspection at intervals of not less than 12 nor more than 24 calendar months after previous inspection).
- e. ;rhe NRC staff recognizes that inspection categorization is removed from the new standard technical specifications (i.e., TSTF-449, Revision 4). As a result, if you plan to adopt these new technical specifications prior to exceeding 24 months since your prior inspection (i.e., May 2004), the categorization of the 2003 and 2004 inspection results will not affect future inspections. Please discuss yourplans for adopting these new technical specifications.
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Attachment 1 to SERIAL: HNP-06-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING THE SPECIAL REPORT DATED AUGUST 1, 2005 (HNP-05-088)
Response 1.a:
Re-analysis (i.e., secondary analysis) of the RFO-1 1 bobbin coil eddy current data was performed with Computer Data Screening (CDS) analysis software.
During May 2004, the sort parameters for CDS were properly entered, and all of the RFO-1 1 data in the region that had been missed previously (i.e., the 0.5" to 1.0" region above the tubesheet) was reviewed. To ensure adequate overlap, the entire tubesheet region from the tube end through five inches above the tubesheet was reviewed.
Response 1.b:
The turbo-mix approach was not used during the CDS review of the RFO-1 1 data. The re-analysis identified the indication using the bobbin coil data. As stated in the request, potential uncertainties exists in sizing the indication with bobbin coil since this technique is nol qualified for sizing small volumetric indications due to the large uncertainties involved. The 37% through-wall value is an estimate provided by the company's Eddy Current Testing (ECT) Level IlIl by simple comparison to the flat bottom holes in the calibration standard. Based on the results of the RFO-1 1 data considering the estimated 37% through-wall indication, the inspection category would have been C-1.
Response 1.c:
The three tubes plugged during the 2004 outage were inspected to bound the repair, so classification of the results from the inspection and repair of these tubes was not required. Subsequent to the tube repair inspection, a SG tube ISI was performed, and the results of this SG tube ISI were categorized as C-1.
Response 1.d:
The next SG tube ISI will be performed during the Spring 2006 outage (RFO-13),
which is scheduled to start on April 8 and is within the interval noted as being not less than 12 nor more than 24 calendar months after the previous inspection.
Response I.e:
Due to timing, HNP does not plan to adopt the new standard Technical Specifications (i.e., TSTF-449, Revision 4) prior to the next scheduled inspection (i.e., Spring 2006). However, Harris plans to submit a request to modify the SG portion of HNP TS consistent with these new standard Technical Specifications by May 31, 2006 as requested by GL 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications dated January 20, 2006.
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A -k Attachment 1 to SERIAL: HNP-06-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 RESPONSE TO THE REQUEST l-OR ADDITIONAL INFORMATION (RAI)
REGARDING THE SPECIAL REPORT DATED AUGUST 1, 2005 (HNP-05-088)
Request 2:
During your secondary side pressure test in 2004, pressures were limited to approximately 60 pounds per square inch gage (psig) because of a nitrogen leak.
Please discuss the source of the leak.
Response 2:
The source of the leak was not discovered. However, the pressure was sufficient to identify the leaking tube that was subsequently repaired.
Request 3:
Please discuss the source of the loose part that resulted in the primary-to-secondary leak in 2004.
Response 3:
Material from the seat ring of a Main Feedwater Isolation Valve was identified as the likely source of the loose part. The valve disc chipped the upper portion of the valve's seat ring introducing a piece of this material into the feedwater system. Subsequently, a piece of material, consistent with the material composition of the valve seat ring, was found lodged against the SG tubes on top of the secondary tubesheet.
Request 4:
During the first inservice inspection, small changes in the eddy current data (when compared to the preservice inspection) were observed for several benign indications. These changes were primarily attributed to the first heat cycle.
Please discuss whether any similar changes in the benign signals (manufacturing marks, dents, dings, etc) were observed during your 2004 inspections. If so, discuss the cause.
Response 4:
No further change in benign signals were noted in the 2004 SG tube ISI.
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Attachment 1 to SERIAL: HNP-06-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING THE SPECIAL REPORT DATED AUGUST 1, 2005 (HNP-05-088)
Request 5:
Please discuss whether any rotating probe examinations were performed at dents, dings, or the U-bend regions of your tubes. If so, discuss the results.
Response 5:
No rotating probe examinations were performed at dents, dings, or the U-bend regions of the tubes during the 2004 SG tube ISI.
Request 6:
- a. It is the NRC staff's understanding that a foreign object search and retrieval was performed at the top of the tubesheet in steam generators A and C during your 2004 inspections. Please confirm that all loose parts were removed from the steam generators.
- b. In addition, please discuss whether any potential loose part signals were observed in your eddy current data. If the parts were not removed or the locations (where eddy current indicated a potential loose part) were not visually inspected, please discuss the results of any evaluations performed to ensure these parts (or suspected parts) would not result in a loss of tube integrity for the period of time between inspections.
Response 6.a:
A Foreign Object Search and Retreival (FOSAR) was performed at the top of the tube sheet in SG's "A" and "C"with the assistance of a vendor that specializes in these types of inspections. All loose parts found during the FOSAR were removed from SG's "AH and "C."
Response 6.b:
No additional loose part signals were identified in the eddy current data other than the signal of the loose part removed from SG "C."
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