ML16138A605
| ML16138A605 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/19/1987 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A606 | List: |
| References | |
| NUDOCS 8710270318 | |
| Download: ML16138A605 (13) | |
Text
o 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. 163 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 August 22, 1985, as supplemented on February 11, 1986, 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 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 amended by changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 3.8 of Facility Operating License No. DPR-38 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. 163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8710270318 871019 PDR ADOCK 05000269 P
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-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION a.
Hood, Acting-Director.
Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance:
October 19, 1987
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UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 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 August 22, 1985, as supplemented on February 11, 1986, 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 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 amended by changes to the Technical Specifications as indicated in the attachments 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION DarlZS Hood, Acting Director Project Directorate II-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance: October 19, 1987 PI W3LRP-I/II PD 3/DRP-I/II (C-Bethesa PDII-3/DRP-I/II MOO c Yrad H
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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. 160 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 August 22, 1985 as supplemented on February 11, 1986, 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 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 amended by changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 3.8 of Facility Operating License No. DPR-55 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. 160, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Da S. Hood, Ating Director Project Directorate II-3 Division of Reactor Projects -
I/Il
Attachment:
Technical Specification Changes Date of Issuance: October 19, 1987
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 163 TO DPR-38 AMENDMENT NO. 163 TO DPR-47 AMENDMENT NO. 160 TO DPR-55 DOCKET NOS. 50-269, 50-270, AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3.3-3 3.3-3 6.1-1 6.1-1 6.1-la 6.1-la 6.1-2
.6.1-2 6.1-3 6.1-3 6.2-1 6.2-1
- b.
The BWST shall contain a minimum level of 46 feet of water having a minimum concentration of 1835*ppm boron at a minimum temperature of 500F. The manual valve, LP-28, on the discharge line shall be locked open.
If these requirements are not met, the BWST shall be considered unavailable and action initiated in accordance with Specification 3.2.
3.3.5 Reactor Building Cooling (RBC) System
- a.
Prior to initiating maintenance on any component of the RBC system, the redundant component shall be tested to assure operability.
- b.
When the RCS, with fuel in the core, is in a condition with pressure equal to or greater than 350 psig or temperature equal to or greater than 250 0 F and subcritical:
(1) Two independent RBC trains, each comprised of an RBC fan; associated cooling unit, and associated ESF valves shall be operable.
(2) Tests or maintenance shall be allowed on any compbnent of the RBC system provided one train of the RBC and one train of the RBS are operable. If the RBC system is not restored to meet the requirements of Specification 3.3.5.b(1) above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a condition with RCS pressure below 350 psig and RCS temperature below 250 0 F within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c.
When the reactor is critical:
(1) In addition to the requirements of Specification 3.3.5.b(1) above, the remaining RBC fan, associated cooling unit, and associated ESF valves shall be operable.
(2) Tests or maintenance shall be allowed on one RBC train
- under either of the following conditions:
(a) One RBC train may be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(b) One RBC train may be out of service for 7 days provided both RBS trains are operable.
(c) If the inoperable RBC train is not restored to meet the requirements of Specification 3.3.5.c(1) within the time permitted by Specification 3.3.5.c(2) (a) or (b), the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the requirements of Specification 3.3.5.c(1) are not met within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following hot'shutdown, the reactor shall be placed in a condition with RCS pressure below 350 psig and RCS temperature below 250 0F within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.3-3 Amendment No. 163 (Unit 1)
Amendment No..163 (Unit 2)
- 2010 ppm boron for Unit 3, Cycle 10 only.
Amendment No. 160 (Unit 3)
6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, AND AUDIT 6.1.1 Organization 6.1.1.1 The Station Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.1.2 In all matters pertaining to actual operation and maintenance and to these Technical Specifications, the Station Manager shall report to and be directly responsible to the Vice President, Nuclear Production Department, through the General Manager, Nuclear Stations. The organization is shown in Figure 6.1-2.
6.1.1.3 The station organization for Operations, Technical Services, Maintenance, Station Services, and Integrated Scheduling shall be functionally as shown in Figure 6.1-1. Minimum operating shift requirements are specified in Table 6.1-1.
6.1.1.4 Incorporated in the staff of the station shall be personnel meeting the minimum requirements encompassing the training and experience described in Section 4 of ANSI/ANS-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel" except for the Site Health Physicist, the Superintendent of Operations and the Operating Engineer.
The Site Health Physicist shall have a bachelor's degree in a science or engineering subject or the equivalent in experience, including some formal training in radiation protection, and shall have at least five years of professional experience in applied radiation protection of which three years shall be in applied radiation protection work in one of Duke Power Company's nuclear stations.
A qualified individual who does not meet the above requirements, but who has demonstrated the required radiation protection management capabilities and professional experience in applied radiation protection work at one of Duke Power Company's multi unit nuclear stations, may be appointed to the position of Site Health Physicist by the Station Manager, based on the recommend ations of the System Health Physicist and as approved by the General Manager, Nuclear Stations.
The Superintendent of Operations shall have a minimum of eight years of responsible nuclear or fossil station experience, of which a minimum of three years shall be nuclear station experience.
A maximum of two years of the remaining five years of experience may be fulfilled by academic training, or related technical training, on a one-for-one time basis. The Superintendent of Operations shall hold or have held a Senior Reactor Operator license.
6.1-1 Amendment No. 163 (Unit 1)
Amendment No. 163 (Unit 2)
Amendment No. 160 TUnit 3)
.1' 0
The Operating Engineer shall have a minimum of eight years of responsible nuclear or fossil station experience, of which a minimum of three years shall be nuclear station experience. A maximum of two years of the remaining five years of experience may be fulfilled by academic training, or related technical training on a one-for-one time basis. The Operating Engineer shall hold a Senior Reactor Operator license.
6.1.1.5 Retraining and replacement of station personnel shall be in accordance with Section 5.5 of the ANSI/ANS-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel."
6.1.1.6 A training program for the fire brigade shall meet or exceed the requirements of Section 27 of the NFPA Code-197S, except that training sessions may be held quarterly.
6.1.1.7 The two functions of the Shift Technical Advisor, namely accident assessment and operating experience assessment, are fulfilled in the following manner:
- a. An experienced SRO, who has been instructed in additional academic subjects, will be assigned on-shift to provide the accident assessment capability.
- b. The operating experience assessment function will be provided by the Station Safety Review Group.
6.1-la Amendment No.
163 (Unit 1)
Amendment No. 163 (Unit 2)
Amendment No. 160 (Unit 3)
6.1.2 Technical Review and Control 6.1.2.1 Activities
- a.
Procedures required by Technical Specification 6.4 and other procedures which affect station nuclear safety, and changes (other than editorial or typographical changes) thereto, shall be prepared by a qualified individual/organization. Each such procedure, or procedure change, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or procedure change, but who may be from the same organization as the individual/group which prepared the procedure, or procedure change. Such procedures and procedure changes may be approved for temporary use by two members of the station staff, at least one of whom holds a Senior Reactor Operator's License on the unit(s) affected.
Procedures and procedure changes shall be approved prior to use or within seven days of receiving temporary approval for use by the Station Managec; or by the Operating Superintendent, the Technical Services Superintendent, the Superintendent of Integrated Scheduling, the Station Services Superintendent (for fire protection and security related procedures only),
or the Maintenance Superintendent, as previously designated by the-Station Manager.
- b.
Proposed changes to theTechnical Specifications shall be prepared by a qualified individual/organization. The preparation of each proposed Technical Specifications change shall be reviewed by an individual/group other than the individual/group which prepared the proposed change, but who may be from the same organization as the individual/group which prepared the proposed change. Proposed changes to the Technical Specific ations shall be approved by the Station Manager.
- c.
Proposed modifications to station nuclear safety-related structures, systems and components shall be designed by a qualified individual/
organization. Each such modification shall be reviewed by an individual/
group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which b designed the modification. Proposed modifications to station nuclear safety-related structures, systems and components shall be approved prior to implementation by the Station Manager; or by the Operating Super intendent, the Technical Services Superintendent, the Superintendent of Integrated Scheduling, or the Maintenance Superintendent, as previously designated by the Station Manager.
- d.
Individuals responsible for reviews performed in accordance with 6.1.2.1.a, 6.1.2.1.b, and 6.1.2.1.c shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the appropriate designated station review personnel.
- e.
Proposed tests and experiments which affect station nucreir safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; or by the Operating Superintendent, the Technical Services Superintendent, the Maintenance Superintendent, or the 6.1-2 Amendment No. 163 (Unit 1)
Amendment No. 163 (Unit 2)
Amendment No. 160 (Unit 3)
Superintendent of Integrated Schdeuling, as previously designated by the Station Manager.
- f.
Incidents reportable pursuant to Technical Specification 6.6.2.1 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence. Such reports shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production Depart ment, or his designee; and to the Director of the Nuclear Safety Review Board.
- g.
The Station Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production Department.
- h.
The station security program, and implementing procedures, shall be reviewed at least once per 12 months. Changes determined to be necessary, as a result of such review shall be approved by the Station Manager or Station Services Superintendent and transmitted to the Vice President, Nuclear Production Department, or his designee; and to the Director of the Nuclear Safety Review Board.
- i. The station emergency plan, and implementing procedures, shall be re viewed at least once per 12 months.
Changes determined to be necessary as a result of such review shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production Department, or his designee; and the Director of the Nuclear Safety Review Board.
- j. The Station M3nager shall assure that an independent fire protection and loss prevention inspection and audit shall be performed annually utilizing qualified off-site personnel and that an inspection and audit by a qualified fire consultant shall be performed at intervals no greater than three years.
- k.
Unplanned onsite releases of radioactive material to the environs shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence. Such reports shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Produciton Department, or designee, and to the Director of the Nuclear Safety Review Board.
- 1.
Proposed changes to the Offsite Dose Calculatoin Manual (ODCM) shall be prepared by a qualified individual/organization. Each proposed change shall be reviewed by an individual/group other than the individual group which prepared the proposed change, but who may be from the same organiz ation as the individual/group which prepared the proposed change.
Proposed changes to the ODCM shall be approved by the Station Manager prior to implementation.
6.1.2.2 Records Records of the above activities shall be maintained.
6.1-3 Amendment No. 163 (Unit 1)
Amendment No. 163 (Unit 2)
Amendment No. 160 (Unit 3)
6.2 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE 6.2.1 The Station Manager shall assure that any reportable event is promptly investigated.
6.2.2 The Vice President, Nuclear Production Department shall be notified of any reportable event.
A written report shall be prepared which describes the circumstances leading up to and resulting from the incident and shall recommend appropriate action to prevent or mini mize the probability of a recurrence. The report shall be submitted to the Vice President, Nuclear Production Department, and the Director of the Nuclear Safety Review Board.
6.2.3 The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.6.2 and 10 CFR 50.73.
6.2-1 Amendment No.
163 (Unit 1)
Amendment No. 163 (unit 2)
Amendment No. 160 (Unit 3)