ML15112B040
| ML15112B040 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/16/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15112B041 | List: |
| References | |
| DPR-38-A-105-1, DPR-38-A-108, DPR-47-A-108, DPR-55-A-105 NUDOCS 8203300017 | |
| Download: ML15112B040 (11) | |
Text
0,RP REG, o
UNITED STATES
.q N~UULEAR 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.
108 License No. DPR-33
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated March 8, 1982, 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 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.
- 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-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. 108are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8203300017 820316 PDR ADOCK 05000269 P
A,PDR
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Chie Op rating Reactors Branch #4 ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 16, 1982
UNITED STATES NCLEAR 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.
108 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated March 8, 1982, 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 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.
- 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.108 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 h F. Stolz, Chief Op rating Reactors Branch #4 ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 16, 1982
41
- UNITED STATES NA EAR REGULATORY COMMISSION W WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 105 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 March 8, 1982, 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 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.
- 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-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.105 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 ohn F. Stolz, Chief perating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 16, 1982
ATTAC ENT TO LICENSE AMENDMENTS AMENDMENT NO. 108 TO DPR-38 AMENDMENT NO. 108 TO DPR-47 AMENDMENT NO. 105 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 3.1-3a 3.1-3a 3.1-4 3.1-4 3.1-6 3.1-6 3.1-7 3.1-7
3.1.2.6 Prior to exceeding six (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), 3.1.2-23 (Unit 2) 3.1.2-1C (Unit 3), 3.1.2-2C (Unit 3) and 3.1.2-3A (Unit 1) 3.1.2-33 (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 CYR 50, Appendix G,Section V.B.
3.1.2.7 The updated proposed technical specification referred to in 3.1.2.6 shall be submitted for NRC review at least 90 days prior to the end of the service period for Units 1, 2, and 3.
Amendments Nos.
108, 108, & 105 3 1-3U
Bases -
Units 1, 2, and 3 All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.
These cyclic loads are introduced by normal load transients, reactor trips, startup and shutdown operations, and inservice leak and hydrostatic tests.
The various categories of load cycles used for design purposes are provided in Table 4.8 of the FSAR.
The major components of the reactor coolant pressure boundary have been analyzed in accordance with Appendix G to 10 CFR 50. Results of this analysis, including the actual pressure-temperature limitations of the reactor coolant pressure boundary, are given in BAW-1699 and BAW-1697.
The Figures specified in 3.1.2.1, 3.1.2.2 and 3.1.2.3 present the pressure temperature limit curves for normal heatup, normal cooldown and hydrostatic tests respectively.
The limit curves are applicable up to the indicated effective full power years of operation. These curves are adjusted by 25 psi and 10oF for possible errors in the pressure and temperature sensing instru ments. The pressure limit is also adjusted for the pressure differential between the point of system pressure measurement and the limiting component for all operating reactor coolant pump combinations.
The cooldown 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 HPI through the core.
If core 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 3.1.2.1 for reactor criticality and on the figures referred to in 3.1.2.3 for hydro static testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice hydrostatic testing.
The actual shift in RT T of the beltline region material will be established periodically during operation by removing and evaluating, in accordance with Appendix H to 10 CFR 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 +60 0F, the protection against nonductile failure is achieved by liMing the secondary coolant pressure to 20 percent of the preoperational system hydrostatic test pressure. The Amendments Nos.
108, 108, & 105 3.1-4
OCONEE UNIT I ONLY CL)
CD 2200 0
H0 2000 APPLICABLE FOR HEATUP RATES OF 1000
&100'F/HR (5ioF IN ANT 1/2 F
1600 HOUR PERIOD)
CRITICALITY LIMIT C) 00 1400 THE ACCEPTABLE PRESSURE AND TEMPERATURE COM3BINATIONS ARE BELOW 1200 AND TO THE RIGHT OF THE LIMIT CURVE. THE REACTOR MUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE S1000 -
TO THE MIGHT or THE CRITICALITY LIMIT CURVE. MARGINS OF 25 PSIG AND IOF ARE INCLUDED FOR POSSIBLE INSTRUMENT EROR.
P T
g00 A
303 g0 556 193 C
556 263 a
600 -C 0
250 313 400 F
F 556 292 9
556 323 A
N 2250 353 S
200 100t 140 gg 220 260 300 340 380 420 IndIcates Reactor Coolant System Temperature, T. *F REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP LIMI TATIONS APPLICABLE FOR FIRST
.6.0 EFFECTIVE FULL POWER YEARS UNIT 1 4;nown OCONEE NUCLEAR STATION Figure 3.1.2-1A
(D OCONEE UNIT I ONLY (Dno THE ACCEPTABLE PRESSURE AND TEMPERATURAE COMBINATION ARE BELOW AND TO TNE RIGHT Of THE F
LIMIT CURVE.
MARGINS OF 25 PSIC AND IOF ARE INCLUDED FOR POSSIBLE INSTRUMENT 2USD ERROR.
- 1. WHEN THE DECAY NEAT REMOVAL (DHR) SYSTEM IS OPERATING WITH NO PC C0 PUMPS OPERATING, THE INDICATED OO SYSTEM RETURN TEMPERATURE TO TNE REACTOR VESSEL SHALL BE USED.
11600 o
- 2. A MAXIMUM STEP TEMPERATURE CHANGE OF 156F IS ALLOWABLE 14oo -WHEN REMOVING ALL C PUMPS FROM OPERATION WITH THE APPLICABLE FOR CDOLDOWN RATES OHR SYSTEM OPERATING.
THE STEP TEMPERATURE CHANGE OF (_100F/HR ((SO*F INANY IS DEFINED AS THE PC TEMP (PRIOR TO STOPPING 1/2 HOUR PERIOD) 1200 ALL PC PUMPS) MINUS THE DHR RETURN TEMP (AFTER STOPPING ALL IC PUMPS). THE 5
100*F/HR RAMP OECREASE IS ALLOWABLE SOT P
T BEFORE AND AFTER THE STEP TEMP 0
A 16 sD CA(
9 556 149 CHANGE.
C 556 21S I
g30 I
C E
790
?111 I
F 2250 311 180 A
Igo10 140 Igg 220 260
-301 348 310 41 inOcested Reacter Ceelan"t Systee Temperatveg Te. *F REACTOR COOLANT SYSTEM NORMAL OPERATION-COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 6.0 EFFECTIVE FULL POWER YEARS UNIT I DUIPWNOCONEE NUCLEAR STATION Figure 3.1.2-2A