ML15113A211
| ML15113A211 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/09/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A212 | List: |
| References | |
| DPR-38-A-143, DPR-47-A-143, DPR-55-A-140 NUDOCS 8510210194 | |
| Download: ML15113A211 (11) | |
Text
UNITED STATES Ai 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. 143 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated February 10, 1983, 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; 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 satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 143 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8510210194 851009 PDR-ADOCK 05000269 P -
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo F. Stolz, Chi ef Op rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 9, 1985
UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 143 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated February 10, 1983, 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; 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 satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 143 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license amendment is effective as of the date of its issuance.
. FOR THE NUCLEAR REGULATORY COMMISSION Jo n.
Stolz, Chief Op rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 9, 1985
l t
- REG, o10 UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
140 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated February 10, 1983, 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; 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 satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-55 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Chi O erating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 9, 1985
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO.
143 TO DPR-38 AMENDMENT NO.
143 TO DPR-47 AMENDMENT NO. 140 TO DPR-55 DOCKETS 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 3.1-3 3.1-3 3.1-3a 3.1-3a 3.1-4 3.1-4 3.1-5 3.1-5
.1.2 Pressurization. Heatu. and Cooldovn Limitation Soecification 3.1.2.1 The reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall be limited as follows:
Heatup:
Heatup rates and allowable combinations of pressure and tempera ture shall be limited in accordance with Table 3.1-1 and Figure 3.1.2-IA Unit 3 3.1.2-1B Unit 2 3.1.2-1C Unit 3 Cooldown:
Cooldown rates and allowable combinations of pressure and tempera ture shall be limited in accordance with Table 3.1-2 and Figure 3.1.2-2A Unit 1 3.1.2-2B Unit 2 3.1.2-2C Unit 3 3.1.2.2 Leak tests required by Specification 4.3 and ASN Section XI shall be limited to the heatup and cooldown rates and allowable combina tions of pressure and temperature prdvided in Tables 3.1-1, 3.1-2 and Figure 3.1.2-3A Unit 1 3.-1.2-3B Unit 2 3.1.2-3C Unit 3 3.1.2.3 For leak test of connected systems required by License Condition 3.H. outlined in Section 4.5.4.2, where the reactor coolant sys tem allowable pressure-temperature limits are controlling, the RCS may be pressurized to the limits set forth in Specification 3.1.2.2.
3.1.2.4 For thermal steady state system hydro tests required by ASMEI Section XI the system may be pressurized to the limits set forth in Specification 2.2 and 3.1.2.2.
3.1.2.5 The secondary side of the steam generator shall not be pressurized above 237 psig if the temperature of the vessel shell is below 110*F.
3.1.2.6 The pressurizer heatup and cooldown rates shall not exceed 100aF/hr.
The spray shall-not be used if the temperature difference between the pressurizer and the spray fluid is greater than 410*F.
3.1-3
3.1.2.7 Prior to exceeding fifteen (Unit 1) fifteen (Unit 2) fifteen (Unit 3) effective full power years of operation.
Figures 3.1.2-1A (Unit 1), 3.1.2-2A (Unit 1) 3.1.2-1B (Unit 2), 3.1.2-2B (Unit 2) 3.1.2-IC (Unit 3), 3.1.2-2C (Unit 3) and 3.1.2-3A (Unit 1) 3.1.2-3B (Unit 2) 3.1.2-3C (Unit 3) and Technical Specification 3.1.2.1, 3.1.2.2 and 3.1.2.3 shall be updated for the next service period in accordance with 10 CFR 50, Appendix G, Section V.B and V.E.
3.1.2.8 The updated proposed technical specification referred to in 3.1.2.7 shall be submitted for NRC review at least 90 days prior to the end of the service period for Units 1, 2 and 3.
3.1-3a
Base Units 1, 2 and 3 All components in the Reactor Coolant SYstem are design Thes cy lic loa s a e itroduced by normal load transients reactor trips, startup and shutdown operations, and inser-vice leak and hydrostatic tests.
The various categories Of load cycles used for design Purposes are provided in Table 5.2-i of the FSAR.
The major components of the reactor Coolant pressure boundary have been nalyzed in accordance with Appendix c to 10 CFR 50.boudary h
is analysis, including the actual Presurtepate li suitos of thes reactor coolant pressure boundary, re eiven in BAW-169 9 an the The igures specified in 3.1.2.,
3.12.2 and 3.1.2.4 present the pressure temperature limit curves for normal heatup, normal cooldown and hydrostatic tests respectively. The limit curves are applicable UP to the indicated Teffactual shft inwe yerRTpr effectd v fulldu n o p t r thef b oe tion. These curves are adju sted by 25 Psi and 1001 for Possible errors in the pressure and temperature sensing instruments The Pressure limit is also adjusted for the Pressure differ ental etwenthe Point Of sYstem pressure measurement and the limiting Component for all operating resactor Coolant Pump Combinations.
The cooldowh limit curves are not applicable to conditions Of Off-normal operation (e.g., small LOCA and extended loss Of feedwater) where cooling is achieved for extended Periods of time by circulating water from the JiPI througb the core.
If cor e cooling is restricted to meet the cooldown limits
- under other than normal operation, core integrity could be jeopardized.
The Pressure-temperature limit lines shown on the figures specified in 3.1.2. for reactor Criticality and on the figures referred to in 3.1.2&4 for hydrostatc testing have been provided. to assure compliance. with the minimum temperature requirements of Appendix G to 0 CFR 50 for reactor
- criticality and for inserva ce hydrostatic testing.
The actual shift in RT "7of the bel tline region material will be es.tablished perodiall duingoperation by removing and evaluating, in accordance with Appendix ii to 10 CTR 50, reactor vessel material irradiation surveillance specimens which are installed near the inside wall of this or a similar reactor vessel in the core region, or in test reactors.
The limitation On steam generator pressure and temperature provide protection against nonductile failure of the secondary side of the steam generator.
At metal temperatures lower than the RT of +60F, the protection against nonductile failure is achieved by ImrDTin scnaycoatpesr to 20 percent of the preoperational system hydrostatic test pressure.
The 3.1-4.
limitations of 110F and 237 psig are based on the highest estimated RT of +40aF and the preoperational system hdrostatic test pressure of 1312 psig.
The average metal temperature is assumed to be equal to or greater than the coolant temperature. The limitations include margins of 25 psi and 10aF for possible instrument error.
The requirements to perform leakage tests of systems outside of containment which could-potentially contain radioactivity 'were established I hYRC following THI.
Oconee performs the leak test of LPI by establishing C pressure at about 300 psig and with LPI at this same pressure, checking for leakage. Such a test is within the scope of testing upon which the curves referenced in Specification 3.1.2.2 are based--that is, they are not routine evolutions, such as heatup and cooldown, but rather infrequent leak tests conducted on a refueling outage basis. As such, the hydrostatic/leak test pressure-temperature limitations are applicable for the RCS when performing leak tests of the LPI system.
The spray temperature difference is imposed to maintain the thermal stresses at the pressurized Spray line nozzle below the design limit.
REFERENCES (1) Analysis of Capsule OCII-A from Duke Power Company Oconee Unit 2 Reactor Vessel Materials Surveillance Program, BAW-1699, December 1981.
(2) Analysis of Capsule OC1ll-B from Duke Power Company Oconee Unit 3 Reactor Vessel Materials Surveillance Program, BAW-1697, October 1981.
(3) Analysis of Capsule OCI-E from Duke Power Company Oconee Unit I Rejctor Vessel Materials Surveillance Program, 8AW-1436, September, 1977.
3.1-5