Letter Sequence Request |
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MONTHYEARHNP-11-055, Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2011-06-0606 June 2011
Day Response to NRC Bulletin 2011-01, Mitigating Strategies.
Project stage: Request
HNP-11-061, 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2011-07-11011 July 2011
60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.
Project stage: Request
ML11334A0262011-12-0505 December 2011
Request for Additional Information Regarding 60-Day Response to Bulletin 2011 01, Mitigating Strategies
Project stage: RAI
HNP-12-001, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies,2012-01-0303 January 2012
Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies,
Project stage: Response to RAI
ML12174A2702012-07-0505 July 2012
Closeout of Bulletin 2011-01, Mitigating Strategies
Project stage: Other
2011-07-11
[Table View] |
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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 Christopher L.Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.
JUN 0 8 2011 Serial: HNP-11-055 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 30-DAY RESPONSE TO NRC BULLETIN 2011-01, "MITIGATING STRATEGIES"
Reference:
NRC Bulletin 2011-01, "Mitigating Strategies," dated May 11, 2011 Ladies and Gentlemen:
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(f), Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc. (PEC),
hereby submits the Harris Nuclear Plant, Unit 1 (HNP), required 30-day response to NRC Bulletin 2011-01, "Mitigating Strategies." The Bulletin required licensees to provide information within 30-days of the date of the Bulletin confirming continued compliance with 10 CFR 50.54(hh)(2) regarding: (1) the availability and capability of equipment to perform its intended function as necessary to execute mitigating strategies, as described in licensee submittals to the NRC, and (2) the capability of the guidance and strategies implemented to be executed considering the current facility configuration and current staffing and skill levels of staff.
The Enclosure to this letter provides the information requested in Bulletin 2011-01 for the required 30-day response.
This document contains no new Regulatory Commitment.
Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
P.O.
Box 165 New Hill, NC 27562 A141P T> 919.362.2502 F> 919.362.2095
Serial: HNP-11-055 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on JUN a 6 2011 1 Sincerely, Christopher L. Burton Vice President Harris Nuclear Plant CLB/kab
Enclosure:
Required 30-Day Response to NRC Bulletin 2011-01 cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief, N.C. DENR Mrs. B. L. Mozafari, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
Enclosure to SERIAL: HNP- 11-055 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 30-DAY RESPONSE TO NRC BULLETIN 2011-01 By letter dated May 11, 2011, the Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating Strategies" to achieve the following objectives:
- 1. To require that addressees provide a comprehensive verification of their compliance with the regulatory requirements of Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.54(hh)(2),
- 2. To notify addressees about the NRC staff's need for information associated with licensee mitigating strategies under 10 CFR 50.54(hh)(2) in light of the recent events at Japan's Fukushima Daiichi facility in order to determine if 1) additional assessment of program implementation is needed, 2) the current inspection program should be enhanced, or 3) further regulatory action is warranted, and
- 3. To require that addressees provide a written response to the NRC in accordance with 10 CFR 50.54(f).
In order to confirm continued compliance with 10 CFR 50.54(hh)(2), the NRC Bulletin required the licensee provide, within 30 days of the date of Bulletin 2011-01, information on licensee mitigating strategies programs. The Bulletin questions required for the 30-day response are restated below followed by the Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., response for the Harris Nuclear Plant, Unit 1 (HNP).
- 1. Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
Response
CP&L has confirmed that the equipment necessary to execute the mitigating strategies, as described in submittals to the NRC (References 1 through 7) and as reviewed and approved by the NRC (Reference 8), is available and capable of performing its intended function at HNP.
- 2. Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?.
Response
CP&L has confirmed that the guidance and strategies implemented are capable of being executed considering the current configuration of HNP and the current staffing and skill levels of the staff at HNP.
Page 1 of 2
Enclosure to SERIAL: HNP- 11-055 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 30-DAY RESPONSE TO NRC BULLETIN 2011-01
References:
I. Letter from T. Morton to the NRC, "Response to February 25, 2005, NRC Letter,
Subject:
NRC Staff Guidance for Use in Achieving Satisfactory Compliance with February 25, 2002, Order Section B.5.b," dated May 31, 2005.
- 2. Letter from C. Kamilaris to the NRC, "Harris Nuclear Plant - Response to NRC Letter dated November 2, 2005, 'Request for Additional Information Regarding the February 2002, Order Section B.5.b, for Brunswick, Crystal River, Shearon Harris, and Robinson Nuclear Plants'," dated December 14, 2005
- 3. Letter from C. Gannon to the NRC, "Harris Nuclear Plant - Response to NRC Letter dated December 2, 2005, 'Demand for Information: Shearon Harris Nuclear Plant',"
dated January 19, 2006.
- 4. Letter from R. Duncan to the NRC, "Shearon Harris Nuclear Power Plant - Report of Inspection of Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b, Temporary Instruction 2515/164 NRC Inspection Report 05000400/2005008,"
dated February 24, 2006.
- 5. Letter from C. Gannon to the NRC, "Harris Nuclear Plant - Supplemental Response to NRC Letter Dated January 25, 2006, 'Shearon Harris Nuclear Plant - Report of Inspection of Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b, Temporary Instruction 2515/164 -NRC Inspection Report 05000400/2005008',"
dated August 2, 2006.
- 6. Letter from R. Duncan to the NRC, "Shearon Harris Nuclear Power Plant, Unit No. 1, Docket No. 50-400/License No. NPF-63, Response Providing Information Regarding Implementation Details for the Phase 2 and 3 Mitigation Strategies," dated February 12, 2007.
- 7. Letter from R. Duncan to the NRC, "Response to Verbal Request for Additional Information Regarding Harris Nuclear Plant Letter HNP-07-003 Dated February 12, 2007," dated April 27, 2007.
- 8. Letter from the NRC to Carolina Power & Light Company, "Shearon Harris Nuclear Power Plant, Unit 1 - Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 (TAC NO.
MD4537)," dated July 26, 2007.
Page 2 of 2
Text
Progress Energy Christopher L.Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.
JUN 0 8 2011 Serial: HNP-11-055 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 30-DAY RESPONSE TO NRC BULLETIN 2011-01, "MITIGATING STRATEGIES"
Reference:
NRC Bulletin 2011-01, "Mitigating Strategies," dated May 11, 2011 Ladies and Gentlemen:
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(f), Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc. (PEC),
hereby submits the Harris Nuclear Plant, Unit 1 (HNP), required 30-day response to NRC Bulletin 2011-01, "Mitigating Strategies." The Bulletin required licensees to provide information within 30-days of the date of the Bulletin confirming continued compliance with 10 CFR 50.54(hh)(2) regarding: (1) the availability and capability of equipment to perform its intended function as necessary to execute mitigating strategies, as described in licensee submittals to the NRC, and (2) the capability of the guidance and strategies implemented to be executed considering the current facility configuration and current staffing and skill levels of staff.
The Enclosure to this letter provides the information requested in Bulletin 2011-01 for the required 30-day response.
This document contains no new Regulatory Commitment.
Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
P.O.
Box 165 New Hill, NC 27562 A141P T> 919.362.2502 F> 919.362.2095
Serial: HNP-11-055 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on JUN a 6 2011 1 Sincerely, Christopher L. Burton Vice President Harris Nuclear Plant CLB/kab
Enclosure:
Required 30-Day Response to NRC Bulletin 2011-01 cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief, N.C. DENR Mrs. B. L. Mozafari, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
Enclosure to SERIAL: HNP- 11-055 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 30-DAY RESPONSE TO NRC BULLETIN 2011-01 By letter dated May 11, 2011, the Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating Strategies" to achieve the following objectives:
- 1. To require that addressees provide a comprehensive verification of their compliance with the regulatory requirements of Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.54(hh)(2),
- 2. To notify addressees about the NRC staff's need for information associated with licensee mitigating strategies under 10 CFR 50.54(hh)(2) in light of the recent events at Japan's Fukushima Daiichi facility in order to determine if 1) additional assessment of program implementation is needed, 2) the current inspection program should be enhanced, or 3) further regulatory action is warranted, and
- 3. To require that addressees provide a written response to the NRC in accordance with 10 CFR 50.54(f).
In order to confirm continued compliance with 10 CFR 50.54(hh)(2), the NRC Bulletin required the licensee provide, within 30 days of the date of Bulletin 2011-01, information on licensee mitigating strategies programs. The Bulletin questions required for the 30-day response are restated below followed by the Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., response for the Harris Nuclear Plant, Unit 1 (HNP).
- 1. Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
Response
CP&L has confirmed that the equipment necessary to execute the mitigating strategies, as described in submittals to the NRC (References 1 through 7) and as reviewed and approved by the NRC (Reference 8), is available and capable of performing its intended function at HNP.
- 2. Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?.
Response
CP&L has confirmed that the guidance and strategies implemented are capable of being executed considering the current configuration of HNP and the current staffing and skill levels of the staff at HNP.
Page 1 of 2
Enclosure to SERIAL: HNP- 11-055 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 30-DAY RESPONSE TO NRC BULLETIN 2011-01
References:
I. Letter from T. Morton to the NRC, "Response to February 25, 2005, NRC Letter,
Subject:
NRC Staff Guidance for Use in Achieving Satisfactory Compliance with February 25, 2002, Order Section B.5.b," dated May 31, 2005.
- 2. Letter from C. Kamilaris to the NRC, "Harris Nuclear Plant - Response to NRC Letter dated November 2, 2005, 'Request for Additional Information Regarding the February 2002, Order Section B.5.b, for Brunswick, Crystal River, Shearon Harris, and Robinson Nuclear Plants'," dated December 14, 2005
- 3. Letter from C. Gannon to the NRC, "Harris Nuclear Plant - Response to NRC Letter dated December 2, 2005, 'Demand for Information: Shearon Harris Nuclear Plant',"
dated January 19, 2006.
- 4. Letter from R. Duncan to the NRC, "Shearon Harris Nuclear Power Plant - Report of Inspection of Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b, Temporary Instruction 2515/164 NRC Inspection Report 05000400/2005008,"
dated February 24, 2006.
- 5. Letter from C. Gannon to the NRC, "Harris Nuclear Plant - Supplemental Response to NRC Letter Dated January 25, 2006, 'Shearon Harris Nuclear Plant - Report of Inspection of Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b, Temporary Instruction 2515/164 -NRC Inspection Report 05000400/2005008',"
dated August 2, 2006.
- 6. Letter from R. Duncan to the NRC, "Shearon Harris Nuclear Power Plant, Unit No. 1, Docket No. 50-400/License No. NPF-63, Response Providing Information Regarding Implementation Details for the Phase 2 and 3 Mitigation Strategies," dated February 12, 2007.
- 7. Letter from R. Duncan to the NRC, "Response to Verbal Request for Additional Information Regarding Harris Nuclear Plant Letter HNP-07-003 Dated February 12, 2007," dated April 27, 2007.
- 8. Letter from the NRC to Carolina Power & Light Company, "Shearon Harris Nuclear Power Plant, Unit 1 - Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 (TAC NO.
MD4537)," dated July 26, 2007.
Page 2 of 2
