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| {{#Wiki_filter:ENCLOSURE 1REVISED PAGES OF FACILITY OPERATING LICENSE NO. NPF-63DOCKET NO. 50-400SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1Replace the following pages of the Facility Operating License. The revised pages are identifiedby the date of the letter issuing these pages and contain marginal lines indicating the areas of change.REMOVEINSERTPage 6 Page 6Page 7Page 7 -----Page 8 (11)Mitigation Strategy License ConditionDevelop and maintain strategies for addressing large fires and explosionsand that include the following key areas:(a) Fire fighting response strategy with the following elements:1. Pre-defined coordinated fire response strategy andguidance2. Assessment of mutual aid fire fighting assets3. Designated staging areas for equipment and materials4. Command and control5. Training of response personnel(b) Operations to mitigate fuel damage considering the following:1. Protection and use of personnel assets2. Communications3. Minimizing fire spread4. Procedures for implementing integrated fire responsestrategy5. Identification of readily-available pre-staged equipment6. Training on integrated fire response strategy7. Spent fuel pool mitigation measures(c) Actions to minimize release to include consideration of:1. Water spray scrubbing2. Dose to onsite respondersD.ExemptionsThe facility requires an exemption from Appendix E, Section IV.F.1, whichrequires that a full participation exercise be conducted within one year before theissuance of a license for full power operation. This exemption is authorized bylaw and will not endanger life or property or the common defense and security,and certain special circumstances are present. This exemption is, therefore,hereby granted pursuant to 10 CFR 50.12 as follows: Shearon Harris Nuclear Power Plant, Unit 1, is exempt from therequirement of 10 CFR Part 50, Appendix E, Section IV.F.1 for theconduct of an offsite full participation exercise within one year before theissuance of the first operating license for full power and prior to operationabove 5 percent of rated power, provided that a full participation exerciseis conducted before or during March 1987. Revised by letter dated July 26, 2007 The facility is granted an exemption from Pa ragraph III.D.2(b)(ii) of Appendix J to10 CFR Part 50 (see SER Section 6.2.6). This exemption is authorized by lawand will not endanger life or property or the common defense and security, and certain special circum stances are present. In addition, the facility was previouslygranted an exemption from the criticality alarm requirements of paragraph 70.24of 10 CFR Part 70 insofar as this section applies to this license. (See LicenseNumber SNM-1939 dated October 28, 1985, which granted this exemption). E.Physical Security (Section 13.6.2.10)The licensee shall fully implement and maintain in effect all provisions of theCommission-approved physical security, training and qualification, andsafeguards contingency plans including amendments made pursuant toprovisions of the Miscellaneous Amendments and Search Requirementsrevisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain SafeguardsInformation protected under 10 CFR 73.21, are entitled: "Guard Training andQualification Plan" submitted by letter dated October 19, 2004, "Physical SecurityPlan" and "Safeguards Contingency Plan" submitted by letter dated October 19,2004 as supplemented by letter dated May 16, 2006. | | {{#Wiki_filter:ENCLOSURE 1 REVISED PAGES OF FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 Replace the following pages of the Facility Operating License. The revised pages are identified by the date of the letter issuing these pages and contain marginal lines indicating the areas of change. |
| F.Fire Protection Program (Section 9.5.1) Carolina Power & Light Company shall implement and maintain in effect allprovisions of the approved fire protection program as described in the FinalSafety Analysis Report for the facility as amended and as approved in the SafetyEvaluation Report (SER) dated November 1983 (and Supplements 1 through 4),and the Safety Evaluation dated January 12, 1987, subject to the followingprovision below.The licensees may make changes to the approved fire protection programwithout prior approval of the Commission only if those changes would notadversely affect the ability to achieve and maintain safe shutdown in the event ofa fire.G. Reporting to the CommissionExcept as otherwise provided in the Technical Specifications or EnvironmentalProtection Plan, Carolina Power & Light Company shall report any violations ofthe requirements contained in Section 2.C of this license in the following manner:initial notification shall be made within twenty-four (24) hours to the NRCOperations Center via the Emergency Notification System with written follow-upwithin 30 days in accordance with the procedures described in 10 CFR 50.73 (b),(c) and (e).Revised by letter dated July 26, 2007 H. The licensees shall have and maintain financial protection of such type and insuch amounts as the Commission shall require in accordance with Section 170 ofthe Atomic Energy Act of 1954, as amended, to cover public liability claims.I. This license is effective as of the date of issuance and shall expire at midnight onOctober 24, 2026.FOR THE NUCLEAR REGULATORY COMMISSIONORIGINAL SIGNED BYHAROLD R. DENTONHarold R. Denton, DirectorOffice of Nuclear Reactor Regulation | | REMOVE INSERT Page 6 Page 6 Page 7 Page 7 |
| | ----- Page 8 |
| | |
| | (11) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: |
| | (a) Fire fighting response strategy with the following elements: |
| | : 1. Pre-defined coordinated fire response strategy and guidance |
| | : 2. Assessment of mutual aid fire fighting assets |
| | : 3. Designated staging areas for equipment and materials |
| | : 4. Command and control |
| | : 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: |
| | : 1. Protection and use of personnel assets |
| | : 2. Communications |
| | : 3. Minimizing fire spread |
| | : 4. Procedures for implementing integrated fire response strategy |
| | : 5. Identification of readily-available pre-staged equipment |
| | : 6. Training on integrated fire response strategy |
| | : 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: |
| | : 1. Water spray scrubbing |
| | : 2. Dose to onsite responders D. Exemptions The facility requires an exemption from Appendix E, Section IV.F.1, which requires that a full participation exercise be conducted within one year before the issuance of a license for full power operation. This exemption is authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. This exemption is, therefore, hereby granted pursuant to 10 CFR 50.12 as follows: |
| | Shearon Harris Nuclear Power Plant, Unit 1, is exempt from the requirement of 10 CFR Part 50, Appendix E, Section IV.F.1 for the conduct of an offsite full participation exercise within one year before the issuance of the first operating license for full power and prior to operation above 5 percent of rated power, provided that a full participation exercise is conducted before or during March 1987. |
| | Revised by letter dated July 26, 2007 |
| | |
| | The facility is granted an exemption from Paragraph III.D.2(b)(ii) of Appendix J to 10 CFR Part 50 (see SER Section 6.2.6). This exemption is authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. In addition, the facility was previously granted an exemption from the criticality alarm requirements of paragraph 70.24 of 10 CFR Part 70 insofar as this section applies to this license. (See License Number SNM-1939 dated October 28, 1985, which granted this exemption). |
| | E. Physical Security (Section 13.6.2.10) |
| | The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Guard Training and Qualification Plan submitted by letter dated October 19, 2004, Physical Security Plan and Safeguards Contingency Plan submitted by letter dated October 19, 2004 as supplemented by letter dated May 16, 2006. |
| | F. Fire Protection Program (Section 9.5.1) |
| | Carolina Power & Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility as amended and as approved in the Safety Evaluation Report (SER) dated November 1983 (and Supplements 1 through 4), |
| | and the Safety Evaluation dated January 12, 1987, subject to the following provision below. |
| | The licensees may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. |
| | G. Reporting to the Commission Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Carolina Power & Light Company shall report any violations of the requirements contained in Section 2.C of this license in the following manner: |
| | initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73 (b), |
| | (c) and (e). |
| | Revised by letter dated July 26, 2007 |
| | |
| | H. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims. |
| | I. This license is effective as of the date of issuance and shall expire at midnight on October 24, 2026. |
| | FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY HAROLD R. DENTON Harold R. Denton, Director Office of Nuclear Reactor Regulation |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Attachment 1 - TDI Diesel Engine Requirements2. Appendix A - Technical Specifications3. Appendix B - Environmental Protection Plan4. Appendix C - Antitrust ConditionsDate of Issuance: January 12, 1987Revised by letter dated July 26, 2007}} | | : 1. Attachment 1 - |
| | TDI Diesel Engine Requirements |
| | : 2. Appendix A - Technical Specifications |
| | : 3. Appendix B - Environmental Protection Plan |
| | : 4. Appendix C - Antitrust Conditions Date of Issuance: January 12, 1987 Revised by letter dated July 26, 2007}} |
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MONTHYEARML0720500642007-07-26026 July 2007 Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 (Tac No. MD4537) Project stage: Other ML0720404432007-07-26026 July 2007 Revised Pages of Facility Operating License No. NPF-63 Project stage: Other 2007-07-26
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Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency ML21320A0012022-01-20020 January 2022 Issuance of Amendment No. 189 to Regarding Administrative Change to Reflect Development of a Technical Requirements Manual ML21316A2482022-01-19019 January 2022 Issuance of Amendment No. 188, Regarding Revision of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22012A4192022-01-18018 January 2022 Correction to Amendment to Revise the Technical Specification for Engineered Safety Feature Actuation System Instrumentation ML21224A1012021-10-0707 October 2021 Issuance of Amendments to Revise the Technical Specification for Engineered Safety Feature Actuation System Instrumentation ML21155A2132021-08-26026 August 2021 Plant ML21116A2072021-05-0404 May 2021 Correction to Amendment No. 184 Regarding TSTF Traveler TSTF-505, Rev. 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21047A4702021-04-0808 April 2021 Issuance of Amendment No. 185 Regarding Reduction of Reactor Coolant System Minimum Flow Rate and Update to the Core Operating Limits Report References ML21047A3142021-04-0202 April 2021 Issuance of Amendment No. 184 Regarding Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times RITSTF Initiative 4B ML21033B0072021-03-22022 March 2021 Issuance of Amendment No, 183 to Correct Non-Conservative Technical Specification Related to Reactor Coolant System Pressure/Temperature Limits ML21035A1322021-03-16016 March 2021 Issuance of Amendment No. 182 Regarding Technical Specifications Related to Accident Monitoring Instrumentation, and Refueling Operations Instrumentation ML20259A5122020-12-0808 December 2020 Issuance of Amendment No. 181 Regarding Adoption of 10 CFR Part 50, Appendix J, Option B, for Type B and C Testing and for Permanent Extension of Type a, B, and C Leak Rate Testing Frequencies(L-2019-LLA-0256) ML20281A2792020-10-13013 October 2020 Correction Letter to Amendment No. 179 Regarding Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML20273A0232020-10-0909 October 2020 Correction Letter to Amendment No. 180 Issued September 4, 2020 ML20212L5942020-09-29029 September 2020 Issuance of Amendment No. 179 Regarding Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20099F5052020-06-29029 June 2020 Issuance of Amendment No. 177 Regarding Elimination of Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications ML19225C0692019-09-19019 September 2019 Issuance of Amendment No. 175 Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints ML19192A0122019-09-17017 September 2019 Issuance of Amendment No. 174 Adopt Title 10 of the Code of Federal Regulations 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components ML19108A1732019-07-18018 July 2019 Issuance of Amendment No. 173 Regarding Emergency Plan Emergency Action Level Scheme Change ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18347A3852019-03-29029 March 2019 Issuance of Amendment No. 169, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18262A3032018-11-19019 November 2018 Issuance of Amendment No. 168 Regarding License Amendment Request for Rod Control Movable Assemblies Technical Specifications Changes ML18204A2862018-10-22022 October 2018 Issuance of Amendment No. 167 Regarding (CAC MF9996; EPID 2017-LLA-0303) ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application 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 ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) ML17324B0482017-12-0606 December 2017 Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17074A6722017-05-25025 May 2017 Issuance of Amendment Relocation of Explosion Gas Monitoring Program Technical Specifications ML17048A1842017-05-24024 May 2017 Issuance of Amendment on Changes to Technical Specifications Section 3.8, Electrical Power Systems and Section 6.8. Procedures and Programs ML17102A9232017-05-18018 May 2017 Nonproprietary Issuance of Amendments Revising Technical Specifications for Methodology Reports DPC Ne 1008 P Revision 0, DPC Nf 2010 Revision 3 and DPC Ne 2011 P Revision 2 (CAC Nos. MF6648, MF6649, MF7693/MF7694) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17066A2992017-03-28028 March 2017 2nd Correction to License Amendment No. 154 Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program ML16200A2852016-11-29029 November 2016 Shearon Harris Nuclear Power Plant, Unit 1 - Issuance of Amendments Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program (CAC No. MF6583) 2024-08-02
[Table view] |
Text
ENCLOSURE 1 REVISED PAGES OF FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 Replace the following pages of the Facility Operating License. The revised pages are identified by the date of the letter issuing these pages and contain marginal lines indicating the areas of change.
REMOVE INSERT Page 6 Page 6 Page 7 Page 7
Page 8
(11) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2. Assessment of mutual aid fire fighting assets
- 3. Designated staging areas for equipment and materials
- 4. Command and control
- 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:
- 1. Protection and use of personnel assets
- 2. Communications
- 3. Minimizing fire spread
- 4. Procedures for implementing integrated fire response strategy
- 5. Identification of readily-available pre-staged equipment
- 6. Training on integrated fire response strategy
- 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
- 1. Water spray scrubbing
- 2. Dose to onsite responders D. Exemptions The facility requires an exemption from Appendix E,Section IV.F.1, which requires that a full participation exercise be conducted within one year before the issuance of a license for full power operation. This exemption is authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. This exemption is, therefore, hereby granted pursuant to 10 CFR 50.12 as follows:
Shearon Harris Nuclear Power Plant, Unit 1, is exempt from the requirement of 10 CFR Part 50, Appendix E, Section IV.F.1 for the conduct of an offsite full participation exercise within one year before the issuance of the first operating license for full power and prior to operation above 5 percent of rated power, provided that a full participation exercise is conducted before or during March 1987.
Revised by letter dated July 26, 2007
The facility is granted an exemption from Paragraph III.D.2(b)(ii) of Appendix J to 10 CFR Part 50 (see SER Section 6.2.6). This exemption is authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. In addition, the facility was previously granted an exemption from the criticality alarm requirements of paragraph 70.24 of 10 CFR Part 70 insofar as this section applies to this license. (See License Number SNM-1939 dated October 28, 1985, which granted this exemption).
E. Physical Security (Section 13.6.2.10)
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Guard Training and Qualification Plan submitted by letter dated October 19, 2004, Physical Security Plan and Safeguards Contingency Plan submitted by letter dated October 19, 2004 as supplemented by letter dated May 16, 2006.
F. Fire Protection Program (Section 9.5.1)
Carolina Power & Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility as amended and as approved in the Safety Evaluation Report (SER) dated November 1983 (and Supplements 1 through 4),
and the Safety Evaluation dated January 12, 1987, subject to the following provision below.
The licensees may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G. Reporting to the Commission Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Carolina Power & Light Company shall report any violations of the requirements contained in Section 2.C of this license in the following manner:
initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73 (b),
(c) and (e).
Revised by letter dated July 26, 2007
H. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
I. This license is effective as of the date of issuance and shall expire at midnight on October 24, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY HAROLD R. DENTON Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attachment 1 -
TDI Diesel Engine Requirements
- 2. Appendix A - Technical Specifications
- 3. Appendix B - Environmental Protection Plan
- 4. Appendix C - Antitrust Conditions Date of Issuance: January 12, 1987 Revised by letter dated July 26, 2007