ML16138A729
| ML16138A729 | |
| Person / Time | |
|---|---|
| Site: | Oconee  (DPR-38-A-194, DPR-47-A-194, DPR-55-A-191) |
| Issue date: | 05/07/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A730 | List: |
| References | |
| GL-86-10, GL-88-12, NUDOCS 9205180357 | |
| Download: ML16138A729 (15) | |
Text
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&0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 194 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated January 16, 1991, as supplemented December 9, 1991, and March 26, 1992, complies 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 application, the provisions 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 set forth in 10 CFR Chapter I; D. The issuance of this license 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 satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraphs 3.B. and 3.E. of Facility Operating License No. DPR-38 is hereby amended to read as follows:
920180357 900 920 05029 FDR~
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-2 3.B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 194, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.E. Fire Protection Duke Power 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 and as approved in the SERs dated August 11, 1978, and April 28, 1983; October 5, 1978, and June 9, 1981 Supplements to the SER dated August 11, 1978; and Exemptions dated February 2, 1982; August 31, 1983; December 27, 1984; December 5, 1988; and August 21, 1989 subject to the following provision:
The licensee 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.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/1l Office of Nuclear Reactor Regulation
Attachment:
- 1. Technical Specification Changes
- 2. Page 8 of the License Date of Issuance:
May 7, 1992
UNITED STATES NUCLEAR REGULATORY COMMISSION
/
WASHINGTON, D.C. 20566 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 194 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the licensee) dated January 16, 1991, as supplemented December 9, 1991, and March 26, 1992, complies 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 application, the provisions 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 set forth in 10 CFR Chapter I; D. The issuance of this license 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 satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraphs 3.B. and 3.E. of Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.194, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.E. Fire Protection Duke Power 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 and as approved in the SERs dated August 11, 1978, and April 28, 1983; October 5, 1978, and June 9, 1981 Supplements to the SER dated August 11, 1978; and Exemptions dated February 2, 1982; August 31, 1983; December 27, 1984; December 5, 1988; and August 21, 1989 subject to the following provision:
The licensee 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.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
1/11 Office of Nuclear Reactor Regulation
Attachment:
- 1. Technical Specification Changes
- 2. Page 8 of the License Date of Issuance:
May 7, 1992
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 191 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated January 16, 1991, as supplemented December 9, 1991, and March 26, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions 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 set forth in 10 CFR Chapter 1; D. The issuance of this license 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 satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraphs 3.B. and 3.E. of Facility Operating License No. DPR-55 is hereby amended to read as follows:
-2 3.B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through.Amendment No. 191, are hereby incorporated in the license. The licensee shall operate the facility.in accordance with the Technical Specifications.
3.E. Fire Protection Duke Power 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 and as approved in the SERs dated August 11, 1978, and April 28, 1983; October 5, 1978, and June 9, 1981 Supplements to the SER dated August 11, 1978; and Exemptions dated February 2, 1982; August 31, 1983; December 27, 1984; December 5, 1988; and August 21, 1989 subject to the following provision:
The licensee 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.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
- 1. Technical Specification Changes
- 2. Page 8 of the License Date of Issuance:
May 7, 1992
ATTACHMENT TO LICENSE AMENDMENT NO. 194 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 194 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 191 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications and License with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages iv, v and vi iv, v and vi 3.17-1 through 3.17-9 4.19-1 and 4.19-2 4.19-1 6.1-4 6.1-4 6.1-6a 6.1-6a 6.6-5 6.6-5 Page 8 of the License 8
Section Page 3.10 RADIOACTIVE GASEOUS EFFLUENTS 3.10-1 3.11 (NOT USED) 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 SNUBBERS 3.14-1 3.15 CONTROL ROOM PRESSURIZATION AND FILTERING SYSTEM AND 3.15-1 PENETRATION ROOM VENTILATION SYSTEMS 3.16 HYDROGEN PURGE SYSTEM 3.16-1 4
SURVEILLANCE REQUIREMENTS 4.0-1 4.0 SURVEILLANCE STANDARDS 4.0-1 4.1 OPERATIONAL SAFETY REVIEW 4.1-1 4.2 STRUCTURAL INTEGRITY OF ASME CODE CLASS 1, 2 AND 3 4.2-1 COMPONENTS 4.3 TESTING FOLLOWING OPENING OF SYSTEM 4.3-1 4.4 REACTOR BUILDING 4.4-1 4.4.1 Containment.Leakage Tests 4.4-1 4.4.2 Structural Integrity 4.4-14 4.4.3 Hydrogen Purge System 4.4-17 4.4.4 Reactor Building Purge System 4.4-20 4.5 EMERGENCY CORE COOLING SYSTEMS AND REACTOR BUILDING 4.5-1 COOLING SYSTEMS PERIODIC TESTING 4.5.1 Emergency Core Cooling Systems 4.5-1 4.5.2 Reactor Building Cooling Systems 4.5-6 4.5.3 Penetration Room Ventilation System 4.5-10 4.5.4 Low Pressure Injection System Leakage 4.5-12 4.6 EMERGENCY POWER PERIODIC TESTING 4.6-1 4.7 REACTOR CONTROL ROD SYSTEM TESTS 4.7-1 4.7.1 Control Rod Trip Insertion Time 4.7-1 4.7.2 Control Rod Program Verification 4.7-2 4.8 MAIN STEAM STOP VALVES 4.8-1 iv Amendment No.
194 (Unit 1)
Amendment No.
194 (Unit 2)
Oconee 1, 2, and 3 Amendment No.
191 (Unit 3)
Section Page 4.9 EMERGENCY FEEDWATER PUMP AND VALVE PERIODIC TESTING 4.9-1 4.10 REACTIVITY ANOMALIES 4.10-1 4.11 (NOT USED) 4.11-1 4.12 CONTROL ROOM PRESSURIZATION AND FILTERING SYSTEM 4.12-1 (INTENTIONALLY BLANK) 4.13-1 4.14 REACTOR BUILDING PURGE FILTERS AND SPENT FUEL POOL 4.14-1 VENTILATION SYSTEM 4.15 (NOT USED) 4.15-r 4.16 RADIOACTIVE MATERIALS SOURCES 4.16-1 4.17 STEAM GENERATOR TUBING SURVEILLANCE 4.17-1 4.18 SNUBBERS 4.18-1 4.19 (NOT USED) 4.20 DELETED PER AMENDMENTS 109, 109, and 106 4.21 (NOT USED) 4.21-1 5
DESIGN FEATURES 5.1-1 5.1 SITE 5.1-1 5.2 CONTAINMENT 5.2-1 5.3 REACTOR 5.3-1 5.4 NEW AND SPENT FUEL STORAGE FACILITIES 5.4-1 6
ADMINISTRATIVE CONTROLS 6.1-1 6.1 ORGANIZATION, REVIEW, AND AUDIT 6.1-1 6.1.1 Organization 6.1-1 6.1.2 Technical Review and Control 6.1-2 6.1.3 Nuclear Safety Review Board 6.1-3a 6.2 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE 6.2-1 6.3 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED 6.3-1 6.4 STATION OPERATING PROCEDURES 6.4-1 V
Amendment No. 194 (Unit 1)
Amendment No. 194 (Unit 2)
Oconee 1, 2, and 3 Amendment No. 191 (Unit 3)
LIST OF TABLES Table No.
P age 2.3-1 Reactor Protective System Trip Setting Limits Units 1,2 and 3 2.3-7 3.5.1-1 Instruments Operating Conditions 3.5-4 3.5-1 Quadrant Power Tilt Limits 3.5-14 3.5.5-1 (NOT USED) 3.5-39 3.5.5-2 (NOT USED) 3.5-41 3.5.6-1 Accident Monitoring Instrumentation 3.5-45 3.7-1 Operability Requirements for the Emergency Power 3.7-14 Switching Logic Circuits 4.1-1 Instrument Surveillance Requirements 4.1-3 4.1-2 Minimum Equipment Test Frequency 4.1-9 4.1-3 Minimum Sampling Frequency and Analysis Program 4.1-10 4.1-4 (NOT USED) 4.1-16 4.4-1 List of Penetrations with 10CFR50 Appendix J Test Requirements 4.4-6 4.11-1 (NOT USED) 4.11-3 4.11-2 (NOT USED) 4.11-5 4.11-3 (NOT USED) 4.11-8 4.17-1 Steam Generator Tube Inspection 4.17-6 6.1-1 Minimum Operating Shift Requirements with Fuel in Three Reactor Vessels 6.1-6 vi Amendment No.
194 (Unit 1)
Amendment No.
194 (Unit 2)
Oconee 1, 2, and 3 Amendment No. 191 (Unit 3)
Pages 4.19-1 and 4.19-2 Not Used 4.19-1 Amendment No. 194 (Unit 1)
Amendment No. 194 (Unit 2)
Amendment No. 191 (Unit 3)
6.1.3.3 Subjects Requiring Review The following subjects shall be reported to and reviewed by the NSRB:
- a.
The safety evaluations for (1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provisions of 10 CFR 50.59(a)(1) to verify that such actions did not constitute an unreviewed safety question.
- b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59..
- c.
Proposed tests or experiements which involve an unreviewed safety question as defined in 10 CFR 50.59.
- d.
Proposed changes in Technical Specifications or the Facility Operating Licenses.
- e.
Violations of applicable statutes, codes, regulations, orders, Technical Specifications, License requirements, or of internal procedures or instructions having nuclear safety significance.
- f.
Significant operating abnormalities or deviations from normal and expected performance of station equipment that affect nuclear safety.
- g.
Incidents that are the subject of non-routine reports submitted to the Commission.
- h.
Quality Assurance Department audits relating to station operations and actions taken in response to these audits.
- i.
Proposed changes to Fire Protection Program.
6.1-4 Amendment No. 194 (Unit 1)
Amendment No 194 (Unit 2)
Oconee 1, 2, and 3 Amendment No. 191 (Unit 3)
ADDITIONAL REQUIREMENTS
- 1.
One licensed operator per unit shall be in the Control Room at all times when there is fuel in the reactor vessel.
- 2.
Two licensed operators shall be in the Control Room during startup and scheduled shutdown of a reactor.
- 3.
At least one licensed operator shall be in the reactor building when fuel handling operations in the reactor building are in progress.
- 4.
An operator holding a Senior Reactor Operator license and assigned no other operational duties shall be in direct charge of refueling operations.
5..
At least one person per shift shall have sufficient training to perform routine health physics requirements.
- 6.
If the computer for a reactor is inoperable for more than eight hours, an operator, in addition to those required above, shall supplement the shift crew.
- 7.
An operator holding a Senior Reactor Operator's license shall be in the Control Room from which the unit is operated whenever the unit is above cold shutdown.
- 8.
Temporary deviations from the requirements of Table 6.1-1 may be allowed in cases of sudden illness, injury or other similar emergencies provided replacement personnel are notified immediately and are on site as soon as possible to return shift manning to minimum.,
6.1-6a Amendment No.
194 (Unit 1)
Amendment No.
194 (Unit 2)
Oconee 1, 2, and 3 Amendment No.
191 (Unit 3)
6.6.3 Special Reports Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
- a. Auxiliary Electrical Systems, Specification 3.7
- b. (Not Used)
- c. (Not Used)
- d. Reactor Coolant System Surveillance, Inservice Inspection, Specification 4.2.1 Reactor Vessel Specimen, Specification 4.2.4
- e. Reactor Building Surveillance, Containment Leakage Tests, Specification 4.4.1
- f. Structural Integrity Surveillance, Tendon Surveillance, Specification 4.4.2.2
- g. (Not Used)
- h. (Not Used)
Amendment No. 194 (Unit 1)
Amendment No.
194 (Unit 2)
Oconee 1, 2, 3 6.6-5 Amendment No. 191 (Unit 3)
-8 properly raised at the Federal Power Commission concerning such commitments, including allocation of costs or the rates to be charged. Applicant will negotiate (including the execution of a contingent statement of intent) with respect to the foregoing commitments with any neighboring entity including distribution systems where applicable engaging in or proposing to engage in bulk power supply transactions, but applicant shall not be required to enter into any final arrangement prior to resolution of any substantial questions as to the lawful authority of an entity to engage in the transactions. In addition, applicant shall not be obligated to enter into a given bulk power supply transaction if:
(1) to do so would violate, or incapacite it from performing any existing lawful contract it has with a third party; (2) there is contemporaneously available to it, a competing or alternative arrangement which affords it greater benefits which would be mutually exclusive of such arrangement; (3) to do so would adversely affect its system operations or the reliability of power supply to its customers, or (4) if to do so would jeopardize applicant's ability to finance or construct on reasonable terms facilities needed to meet its own anticipated system requirements.
3.E. Fire Protection Duke Power 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 and as approved in the SERs dated August 11, 1978, and April 28, 1983; October 5, 1978 and June 9, 1981 Supplements to the SER dated August 11, 1978; and Exemptions dated February 2, 1982; August 31, 1983; December 27, 1984; December 5, 1988; and August 21, 1989 subject to the following provision:
The licensee 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.
REVISED BY NRC LETTER DATED May 7, 1992