ML15112A853
| ML15112A853 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/19/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A854 | List: |
| References | |
| NUDOCS 7904060070 | |
| Download: ML15112A853 (14) | |
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.71 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 21, 1978, 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.
7904060670
0 0
-2
- 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.71 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 19, 1979
UNITED STATES 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.71 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 21, 1978, 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
- 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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 19, 1979
UNITED STATES NUCLEAR REGULATORY COMMISSION of WASHINGTON. D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No.
- 1. The Nuclear Regulatory Commissiorn (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated February 21, 1978, 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
- 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. 68 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 19, 1979
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 71 TO DPR-38 AMENDMENT NO.
71 TO DPR-47 AMENDMENT NO. 68 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove the following pages and insert revised identically numbered pages:
3.1-3 3.1-3a 3.1 3.1-6 3.1-7 3.1-7c Changes on the revised pages are indicated by marginal lines.
3.1.2 Pressurization, Heatup, and Cooldown Limitation Specification 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 tures shall be limited in accordance with Figure 3.1.2-1A Unit 1 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 Figure 3.1.2-ZA 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 ASME Section XI shall be limited to the heatup and cooldown rates and allowable combinations of pressure and temperature provided in Figure 3.1.2-3A Unit 1 3.1.2-3B Unit 2 3.1.2-3C Unit 3 3.1.2.3 For thermal steady state system hydro tests required by ASME Section XI the system may be pressurized to the limits set forth in Specification 2.2 and 3.1.2.2.
3.1.2.4 The secondary side of the steam generator shall not be pressurized above 237 psig if the temperature of the vessel shell is below 11O0F.
3.1.2.5 The pressurizer heatup and cooldown rates shall not exceed 100oF/hr.
The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 4100F.
Amendment No. 71, 71
, & 68 3.1-3
3.1.2.6 Prior to exceeding SiX (Unit 1) four (Unit 2) four (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) 3.1.2-1C (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.
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 2 and 3.
For Unit 1, the request for operation beyond the 6 EFPY shall be submitted six months prior to the end of the six year period.
3.1-3a Amendment No. 71
, 71
, & 68
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-temperatur 1 jimitations5 the reactor mlant pressure boundary, are given in BAW-1436
, BAW-1437 and BAW-1438 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 100F for possible errors in the pressure and temperature sensing instruments.
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 pressure-temperature limit lines shown on the figure specified in 3.1.2-1 for reactor criticality and on the figure referred to in 3.1.2.3 for hydrostatic 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 RTNDT 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 +600F, the protection against non ductile failure is achieved by limiting the secondary coolant pressure to 20 percent of the preoperational system hydrostatic test pressure. The lim itations of 1100F and 237 psig are based on the highest estimated RT of
+400 F ahd the preoperational system hydrostatic test pressure of 1312psig.
The average metal temperature is assumed to be equal to or greater than the coolant temperature. The limitations include margins of.25 psi and 10 F for possible instrument error.
The spray temperature difference is imposed to maintain the thermal stresses at the pressurizer spray line nozzle below the design limit.
- 3. 1-4 Amendment No. 71,71
, &68
REFERENCES (1) Analysis of Capsule OCI-E from Duke Power Company Oconee Unit 1 Reactor Vessel Materials Surveillance Program, BAW-1436, September 1977.
(2) Analysis of Capsule OCII-C from Duke Power Company Oconee Unit 2 Reactor Vessel Materials Surveillance Program, BAW-1437, May 1977.
(3) Analysis of Capsule OCIII-A from Duke Power Company Oconee Unit 3 Reactor Vessel Materials Surveillance Program, BAW-1438, July 1977.
3.1-5 mmn 71 71, & 68
OCONEE UNIT I ONLY 2200 0
H rt
- l.
2000 APPLICABLE FOR HEATUP RATES OF
&I 100'F/HR (j50*F IN ANY 1/2 1800 HOUR PERIOD)
- CRITICALITY LIIIT 1600 II CL1400 THE ACCEPTABLE PRESSURE AND TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE. THE REACTOR MUST NOT BE 0:
1200 MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE 0 -
TO THE RIGHT or THE CRITICALITY LIMIT CURVE. MARGINS OF 25 PSIS AND I0F ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.
P T
0 A
383 80 800 B
556 193 C
556 283 C
0 2250 313 a= 600 -
1 0 292 3FF 556 292 400 -
F 556 323 A
N 2250 353 so 100 140 to0 220 260 300 340 380 420 Indicated Reactor Coolant System Temperature. Tc. "F REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP LIMI TATIONS APPLICABLE FOR FIRST 6.0 EFFECTIVE FULL POWER YEARS UNIT 1 unrown OCONEE NUCLEAR STATION Fioure 3.1.2-1A
OCONEE UNIT I ONLY 2200 THE ACCEPTABLE PRESSURE AND TEMPERATURE COMBINATION ARE SELOW AND TO THE RIGHT OF THE F
- j ALIMIT CURVE. MARGINS OF 25 PSIS AND IOF ARE INCLUOED FOR POSSIBLE INSTRUMENT 1000 ERROR.
- 1. WHEN THE DECAY HEAT REMOVAL (DHR) SYSTEM IS OPERATING WITH N0 RC 1-00 PUMPS OPERATING, THE INDICATED DHR SYSTEM RETURN TEMPERATURE TO THE REACTOR VESSEL SHALL BE USED.
1800
- 2. A MAXIMUM STEP TEMPERATURE CHANGE OF 15*F IS ALLOWABLE 01 APPLICABLE FOR COOLDOWN RATES WHEN REMOVING ALL RC PUMPS FROM OPERATION WITH THE 00 1400
-oF
< 100*F/HR (< 50*F if ANY DHR SYSTEM OPERATING. THE STEP TEMPERATURE CHANGE
(
1/2 HOUR PERI00)(2 1200 IS DEFINED AS THE RC TEMP (PRIOR TO STOPPING ALL PC PUMPS) MINUS THE DHR RETURN TEMP (AFTER STOPPING ALL RC PUMPS). THE C. 1000 IODF/HR RAMP DECREASE IS ALLOWABLE DOT A
183 10 BEFORE AND AFTER THE STEP TEMP 0
A 56 14 8 00C 556 149 CHANGE.
C 556 215 0
380 221 So E 1290 261 C
C F
2250 317 200 A
SO 100 140 1o0 220 260 300 340 310 420 IndIcated Reactor Coolant System Temperatore. Ic. *F REACTOR COOLANT SYSTEM NORMAL OPERATION-COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 6.0 EFFECTIVE FULL POWER YEARS UNIT 1 Ioutro OCONEE NUCLEAR STATION Figure 3.1.2-2A
OCONEE UNIT I ONLY F
- 2400 APPLICABLE FOR NEATUP RATES OF Ct 2200 100*f/HR (j 50*F IN ANT 1/2 HOUR 200
-PERIOD) 2000 1600 -
"APPLICABLE FOR COOLDOIW Mn THE ACCEPTABLE PRESSURE AND TEMPERATURE COMBINATIONS ARE RATES OF ( 100F/HR 1400 IELOW AND TO THE RIGHT OF THE LIMIT CURVE. MARGINS OF (150F IN ANT 1/2 HOUR 25 PSIS AND IOF ARE INCLUDED FOR POSSIBLE INSTRUMENT 0
1200 ERROR.
FOR COOLDOWR, NOTES I AND 2 ON FISURE 3.1.2-2A PERIOD)
- 4.
APIPLICAh1.
A 249 Of DOS 55 11 5
C 556 255 1
1330 261 t
50E 2113 271 C
F 2500 232 0 2500 401 Z
2111 p
I I
I I
I SO I00 140 180 220 260 300 340 350 420 Indicated Reactor Coolant System Temperature. Tc *F REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDRO STATIC TEST HEATUP AND COOLDOWN LIMITATION APPLICABLE FOR FIRST 6.0 EFFECTIVE FULL POWER YEARS untown OCONEE NUCLEAR STATION UN 31 Figure 3.1.2-3A