ML15112A973
| ML15112A973 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/07/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A974 | List: |
| References | |
| NUDOCS 8012020042 | |
| Download: ML15112A973 (13) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment by the Duke Power Company (the licensee) dated October 1, 1976, and May 30, 1979, as supplemented May 26, 1977, and June 11, 1979, and application dated March 24, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR.Chapter 1; B. The facility will operate in conformity with the applications, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be.conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment wilT not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
o 120 2oof
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indpicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.
DPR-38 is hereby amended to read as follows:
3.8 Technical Specifications The Technjcal Specifications contained in Appendices A and B, as revised through Amendment No. 88 are hereby incorporated in the license. The licensee shall operate the facility in accordance,with the Technical Specifications.
- 3. This license anendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION oert Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 7, 1980
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENTTO FACILITY OPERATING LICENSE Amendment No.8, License No. DP - 47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment by the Duke Power Company (the licensee) dated July 8, 1977, and May 30, 1979, as supplemented September 21, 1977, and June 11, 1979, and application dated March 24, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
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- 2. Accordingly, the license is amended by changes to the Technical Specifications-as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.
DPR-47 is hereby amended to read: as follows:
3.B Technical Specifications TheTechnical Specifications contained in Appendices A and B, as revised-through Amendment No.88 are hereby incorporated in the license. The licensee shall operate the facility in accordance with. the Technical Specifications.
- 3.
This Ticense amendment is effective as of the date of its issuancE.
FOR THE NUCLEAR REGULATORY COMMISSION obert W.- Reid, Chief Operating Reactors Branch P4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 7, 1980
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment by the Duke Power Company (the licensee) dated July 8, 1977, and May 30, 1979, as supplemented September 21, 1977, and June 11, 1979, and application dated March 24, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
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- 2. Accordingly, the-ilcense~ is amended by changes to the Technical Specifications as-indicated in the attachment to this license amendment and para.graph-3.B of Facility Operating License No.
DPR-55 is hereby amended to read as. follows:
3.B TechnicaT Speci fica-ti ons The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85 are hereby incorporated in, the license.
The.licensee shall operate the facility in accordancer with the Technical Spec if i
cations.
- 3.
This license: anmendment is effective as of the date:of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 7, 1980
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 88 TO DPR-38 AMENDMENT NO. 88 TO DPR-47 AMENDMENT NO. 35 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:.
Remove Pages Insert Pages vi vi 4.2-1 4.2-1 4.2-2 4.2-2 4.2-3 4.2-3 4.2-4 4.3-1 4.3-1
Section Pae 3.4 STEAM AND POWER CONVERSION SYSTEM 3.4-1 3.5 INSTRUMENTATION SYSTEMS 3.5-1 3.5.1 Operational Safety Instrumentation 3.5-1 3.5.z Control Rod Group and Power Distribution Limits 3.5-6 3.5.3 Engineered Safety 7atures Protective System 3.5-28 Actuation Setpoints, 3.5.4 Incore Instrumentation 3.5-30 3.6 REACTOR BUILDING 3.6-1 3.7 AUXILIARY ELECTRICAL SYSTEMS 3.7-1 3.8 FUEL LOADING AND REFUELING 3.8-1 3.9 RELEASE OF LIQUID RADIOACTIVE WASTE 3.9-1 3.10 RELEASE OF GASEOUS RADIOACTIVE WASTE 3.10-1 3.11 MAXIMUM POWER RESTRICTION 3.11-1 3.12 REACTOR BUILDING POLAR CRANE AND AUXILIARY HOIST 3.12-1 3.13 SECONDARY SYSTEM ACTIVITY 3.13-1 3.14 SHOCK SUPPRESSORS (SNUBBERS) 3.14-1 3.15 PENETRATION ROOM VENTILATION SYSTEMS 3.15-1 3.16 HYDROGEN PURGE SYSTEM 3.16-1 3.17 FIRE PROTECTION AND DETECTION SYSTEMS 3.17-1
- 4.
SURVEILLANCE REQUIREMENTS 4-1 4.0 SURVEILLANCE STANDARDS 4-1 4.1 OPERATIONAL SAFETY REVIEW 4.1-1 4.2 STRUCTURAL INTEGRITY OF ASME CODE CLASS 1, 2 AND 3 COMPONENTS 4.2-1 4.3 TESTING FOLLOWING OPENING OF SYSTEM 4.3-1 4.4 REACTOR BUILDING 4.4-1 Amendments Nos. 88, 88 & 85 111
LIST OF TABLES Table No.
Page 2.3-1A Reactor Protective System Trip Setting Limits - Unit 1 2.3-11 2.3-1B Reactor Protective System Trip Setting Limits -
Unit 2 2.3-12 2.3-1C Reactor Protective System Trip Setting Limits -
Unit 3 2.3-13 3.5.1-1 Instrument Operating Conditions 3.5-3 3.5-1 Quadrant Power Tilt Limits 3.5-14 3.17-1 Fire Protection & Detection Systems 3.17-3 4.1-1 Instrument Surveillance Requirements 4.1-3 4.1-2 Minimum Equipment Test Frequency 4.1-9 4.1-3 Minimu;.' Sampling Frequency 4.1-10 4.2-1 Oconee Nuclear Station Capsule Assembly Withdrawal Schedule 4.2-3 at Crystal River Unit No. 3 4.11-1 Oconee Environmental Radioactivity Monitoring Program 4.11-3 4.11-2 Offsite Radiological Monitoring Program 4.11-4 4.11-3 Analytical Sensitivities 4.11-5 4.18-1 Safety Related Shock Suppressors (Snubbers) 4.18-3 6.1-1 Minimum Operating Shift Requirements with Fuel in Three 6.1-6 Reactor Vessels 6.6-1 Report of Radioactive Effluents 6.6-8 Amendments Nos.
83, 88 & 85 1
4.2 STRUCTURAL INTEGRITY OF ASME CODE CLASS 1, 2 AND 3 COMPONENTS Applicability Applies to the surveillance of the ASME Code Class 1, 2 and 3 components.
Objective To assure the continued structural integrity of the ASME Code Class 1, 2 and 3 components.
Specification 4.2.1 Inservice examination of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50, Section 50.55a(g)(4), to the extent practicable within the limitations of design, geometry and materials of construction of the components, except where specific written relief has been granted by the Commission.
4.2.2 To assure the structural integrity of the reactor internals throughout the life of the unit, the two sets of main internals bolts (connecting the core barrel to the core support shield and to the lower grid cylinder) shall remain in place and under tension. This will be verified by visual inspec tion to determine that the welded bolt locking caps remain in place. All locking caps will be inspected after hot functional testing and whenever the internals are removed from the vessel during a refueling or maintenance shutdown. The core barrel to core support shield caps will be inspected each refueling shutdown.
4.2.3 At approximately three-year intervals, the bore and keyway of each reactor coolant pump flywheel shall be subjectedito an inplace, volumetric examination. Whenever maintenance or repair activities necessitate flywheel removal, a surface examination of exposed sur faces and a complete volumetric examination shall be performed if the interval.measured from the previous such.inspection is greater than 6 2/3 years.
Amendments Nos. 88, 88 & 85 4.2-1
4.2.4 The reactor vessel material irradiation surveillance specimens removed from Units 1, 2 and 3 reactor vessels in 1976 shall be installed, ir radiated in and withdrawn from the Crystal River Unit 3 reactor vessel in accordance with the schedule shown in Table 4.2-1.
Following with drawal of each capsule listed in Table 4.2-1, Duke Power Company shall be responsible for testing.the specimens in those capsules and submit ting a report of test results In accordance with 10 CFR 50, Appendix H.
4.2.5 The licensee shall submit a report or application for license amendment to the NRC within 90 days after the occurrence of the following: After March 13, 1'978, any time that Crystal River Unit No. 3 fails to maintain a cumulative reactor utilization' factor of greater than 45%.
The report shall provide justification for continued operation of Oconee Nuclear Station Units 1,. 2 and 3 with the reactor vessel surveil lance program conducted'.at Crystal River Unit No. 3 or the application for license amendment shall propose an alternate program for conduct of the reactor* vessel surveillance program.
Bases The surveillance program has. been developed to comply with the applicable edition of Section XI and addenda of the ASME Boiler and Pressure Vessel Code, Inservice Inspection of Nuclear Reactor Coolant Systems, as required by 10 CFR 50.55(a) to the extent practicable within limitations of design, geometry and materials of construction. The program places major emphasis on the area of highest stress concentrations and on areas where fast neutron irradiation might be sufficient to change material properties.
The number of reactor vessel specimens and the frequencies for removing and testing these specimens are provided to assure compliance with the requirements of Appendix H to 10 CFR Part 0.
For the purpose of Technical Specification 4.2.5. Cumulative reactor utilization factor is defined as:
{(Cumulative thermal megawatt hours since attainment of commercial operation at 100% power) x 100) + {(licensed thermal power) x (cumula tive hours since attainment of commercial operation at 100% power).
The defini tion of Regulatory Guide 1.16, Revision 4 (August 1975) applies for the term "commercial operation".
Amendments Nos. 88, 88 & 85 4.2-2
Table 4.2-1, OCONEE NUCLEAR STATION CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT CRYSTAL RIVER UNIT NO. 3 Capsule Designation Insertion Withdrawal OCI-A
,End of 1st Cycle End of 7th Cycle OCI-B End of 7th Cycle End of 16th Cycle OCI-C End of 2nd Cycle End of 11th Cycle OCI-D End of 9th Cycle End of 18th Cycle OCII-A End of 1st Cycle End of 2nd Cycle OCII-B End of 4th Cycle End of 9th Cycle OCII-D End of 9th Cycle End of 18th Cycle OCII-E End of 1st Cycle End of 9th Cycle OCTI-F End of 9th Cycle End of 18th Cycle OCIII-B End of 1st Cycle End of 2nd Cycle OCIII-C End of 5th Cycle End of 10th Cycle OCIII-D End of Ist Cycle End of 9th Cycle OCI1I-E End of 5th Cycle End of 18th Cycle OCIII-F End of 11th Cycle End of 20th Cycle NOTE:
OCI Capsules are from Unit No. 1 OCII Capsules are from Unit No. 2 OCIII -
Capsules are from Unit No. 3 Amendments Nos.88, 88 & 85 423
4.3 TESTING FOLLOWING OPENING OF SYSTEM Applicability Applies to test requirements for Reactor Coolant System integrity.
Objective To assure Reactor Coolant System integrity prior to return to criticality following normal opening, modification, or repair.
Specification 4.3.1 When Reactor Coolant System repairs or modifications have been made, these repairs or modifications shall be inspected and tested to meet all applicable code requirements prior to the reactor being made critical.
4.3.2 Following any opening of the Reactor Coolant System, it shall be leak tested at not less than 2200 psig prior to the reactor being made critical.
4.3.3 The limitations of Specification 3.1.2 shall apply.
Bases Repairs or modifications made to the Reactor Coolant System are inspectable and testable under applicable codes. The specific code and edition thereof shall be consistent with 10CFR 50.55.
REFERENCES FSAR, Section 4 Amendments Nos. 88, 88 & 85 4.3-1