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
Progress Energy Serial: HNP-07-128 SEP 27 2007 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 ADDITIONAL INFORMATION (RAI)
REGARDING THE SPRING 2006 REFUELING OUTAGE 13 STEAM GENERATOR TUBE INSPECTIONS
References:
- 1. Letter from D. H. Corlett to the Nuclear Regulatory Commission (Serial: HNP-06-073), "15-Day Special Report Steam Generator Tube Plugging During RFO- 13," dated May 05, 2006
- 2. Letter from D. H. Corlett to the Nuclear Regulatory Commission (Serial: HNP-06-081), "90-Day Inservice Inspection (ISI) Summary Report," dated August 10, 2006
- 3. Letter from D. H. Corlett to the Nuclear Regulatory Commission (Serial!:,HNP-07-039), "One-Year Special Report Steam Generator Tube Inservice Inspection Results," dated April 20, 2007 Ladies and Gentlemen:
By letter dated September 5, 2007, the Nuclear Regulatory Commission requested additional information to facilitate the review of the above referenced Refueling Outage (RFO) 13 steam generator (SG) tube inspection reports.
The Attachment provides the requested additional information.
This document contains no new regulatory commitment.
Please refer any question regarding this submittal to me at (919) 362-3137.
Sincerely, D. H. Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 A0ooI
HNP-07-128 Page 2 DHC/kms
Attachment:
Response To The Request For Additional Information (RAI) Regarding The Spring 2006 Refueling Outage 13 Steam Generator Tube Inspections cc: Mr. P. B. O'Bryan, NRC Sr. Resident Inspector Ms. B. 0. Hall, N.C. DENR Section Chief Ms. M. G. Vaaler, NRC Project Manager Dr. W. D. Travers, NRC Regional Administrator
Attachment to SERIAL: HNP-07-128 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 SPRING 2006 REFUELING OUTAGE 13 STEAM GENERATOR TUBE INSPECTIONS Request 1:
On Page A1-2 of the letter datedApril 20, 2007,you indicated that 10 tubes with loose part signals at the top of the tubesheet region on the hot-leg side of SG B were examined with a rotatingcoil. Please discuss the results of these rotatingcoil exams (i. e., were loose partspresent, what were the loose parts, and were the loose parts removed), and discuss the results of any visual examinations in this area.
In addition, were all known foreign objects (other than the foreign object wedged between Tube Row 60 Column 45 (R60C45) and Tube R59C46 in SG A) in all three SGs removed? If not, please discuss whatforeign objects were left inservice and the criteria used to determine which foreign objects are acceptableto leave inservice.
Response 1:
The tubes identified by eddy current with the Loose Part Signal calls were presented to the steam generator (SG) secondary inspection personnel. The SG secondary team visually inspected the region around the tubes noted with potential loose parts and observed a few small objects of minimal substance. The foreign matter that could be collected (i.e., that substance that had some mass) reported by eddy current was retrieved.
While various items were retrieved from within the SGs, there were some very small objects with minimal mass that were not retrieved. The decision to leave these objects was based on a retrieval of several objects from the steam generators which allowed a comparison of the relative size of the object being observed in the remote visual inspection probe versus the significance of the objects that were being retrieved. As an example, during the in-bundle visual inspection which used a small diameter probe head, one of the larger items retrieved was approximately 3/8" in length, 1/16" in width, and less than 1/32" in height and had virtually no mass. This item was used as an aid in determining the significance of other small items identified by visual inspection in the in-bundle inspection.
NRC Request 2:
Please confirm that the four tubes inspected with a rotating coil in SG A to bound the wedgedforeign object were adjacent/nearbyto Tubes R60C45 and R59C46 which were plugged.
Page 1 of 3
Attachment to SERIAL: HNP-07-128 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 SPRING 2006 REFUELING OUTAGE 13 STEAM GENERATOR TUBE INSPECTIONS Response 2:
The foreign object was wedged between the tubes R60C45 and R59C46. The object did not appear to extend beyond the diameter of the two tubes. These two tubes and two tubes adjacent to these tubes were inspected with a rotating coil exam. The four tubes examined completely surround the object.
NRC Request 3:
In the letter datedApril 20, 2007, you indicated that one tube with a distorteddent signal around the 9 "hsupportplate on the cold-leg side of SG B was examined with a rotating coil. Please discuss whether the signal at this location has changed since the baseline inspection. If so, discuss the reasonfor the change and the basisfor concluding no tube-wall degradationexisted at this location.
Response 3:
A bobbin inspection reported there was a Distorted Dent Indication near the 9 th support plate for one tube. The region around the reported location then received a rotating coil examination. The results of this examination indicated a "No Defect Found" condition.
A review of bobbin data from the baseline inspection showed no change in the signal amplitude or phase in the region where the Distorted Dent Indication was reported.
NRC Request 4.
Please discuss whether the signal of the one tube examined by rotating coil in a slightly restrictedarea of the tube within the tubesheet in SG B has changed since the baseline inspection. If so, please discuss the reasonfor the change. In addition, what was the nature of the signal?
Response 4:
The tube had been inspected in past inspections with a 0.560 bobbin probe. During this inspection (April 2006), the bobbin probe would not pass a point approximately 22 inches up from the cold leg tube end. The bobbin probe was inserted from both the cold and hot leg sides of the tube and would not past this point. A 0.520 single +PT coil was inserted from the cold leg tube end and successfully examined the restricted area. The analysis of the +PT coil data does not indicate any type of restriction at 22 inches above the tube end.
The results of the bobbin inspection and the rotating coil inspection were "No Detectable Degradation" for this tube. A review of the bobbin data from the preservice inspection Page 2 of 3
Attachment to SERIAL: HNP-07-128 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 SPRING 2006 REFUELING OUTAGE 13 STEAM GENERATOR TUBE INSPECTIONS (June 2001) and the first inspection following SG replacement (April 2003) did not indicate an abnormal transition, dent, or blockage, in the area of the restricted region.
NRC Request 5:
In the letter dated April 20, 2007, you indicated that two tubes on the hot-leg side and three tubes on the cold-leg with dent signals, located by the 8 'h and 9 th tube support plates of SG C, were examined with a rotatingcoil. Please discuss whether the signals at these locations have changed since the baseline inspection. If so, discuss the reason for the changes and the basisfor concluding no tube-wall degradationexisted at these locations..
Response 5:
The dents were new small dents that appeared in the same relative location in the outer region of the upper tube support plates as dents identified during previous inspections. A few of the new dents were selected for examination with a rotating coil. Dents are sampled with a rotating coil exam to ensure tube integrity. There was "No Defect Found" as a result of these examinations. The reason for these new dents is not definitive. A survey was sent to the SG industry and one of the suggestions was the new dents could be potentially due to thermal transients. HNP does perform startup operations with auxiliary feedwater (AFW) fluid, which is colder than feedwater at normal plant operations.
Although the plant did operate with AFW in service slightly longer than is typical while exiting the November 2004 refueling outage due to problems experienced with a feedwater valve, it is not possible to state with certainty that extended operation of AFW caused the new dents.
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