ML15112A942
| ML15112A942 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/07/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A943 | List: |
| References | |
| NUDOCS 8010210046 | |
| Download: ML15112A942 (13) | |
Text
o' UNITED STATES 0
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.
87 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 July 22, 1980, 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 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:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87 are hereby incorporated in the license. The licensee shall operate thefacility in accordance with the Technical Specifications.
8010210 046
-2
- 3. This licse ai hdihent is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W.. Reid, Chief Operatihg Reactors Branch #4 Division of Licensing Attachm6nt:
Changes t6 the Technical Specificatiohs Date of Issuanobi Ottober 7i 1980
o1 UNITED STATES NUCLEAR REGULATORY COMMISSION 4
o WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE.NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 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 July 22, 1980, 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 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:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
2
- 3. This license amendent is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMHISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division qf Licensing
Attachment:
Capges to the Technical Specifications Date of Issuance: October 7, 1980
REG(,
UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 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 July 22, 1980, 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 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. OPR-55 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing Attachrncn Changes to the Technical Specifications Date of Issuance: October 7, 1980
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 87 TO DPR-38 AMENDMENT NO. 87 TO DPR-47 AMENDMENT NO. 84 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 3.1-6a 3.1-6a 3.1-6b 3.1-6b 3.1-7a 3.1-7a 3.1-7b 3.1-7b 3.1-7d 3.1-7d 3.1-7e 3.1-7e
- 0.
n THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).
o THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE, THEY INCLUDE AN ADDITIONAL co MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 100F).
THE REACTOR MUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMIT.
00 2500 SOO a0 H
HEAlUP RATE:
50aF/HR 2000
-.CRITICALITY LIMIT 0
G POINT PRESSURE PSIG TEMP.
OF 500~n A
381 700
.0B 556 186.
C 556 2831 0
1540 300*
E 2250 326*
logo F
56 323*
s 1540 340*
H 2250 366 L3F 6
313.
F I
I 100 200 300 400 Indicated Reactor Coolant System Temperature. Tc, oF UNIT 2 REACTOR COOLANT SYSTEM NORMAL OPERATION HEATUP LIMITATIONS APPLICABLE FOR FIRST 5.0 EFPY OCONEE NUCLEAR STATION Figure 3.1.2-18
THE ACCEPTABLE PRESSURE TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).
THE LIMIT CUNVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING TIE LIMIT CURVE.
THEY INCLUDE AN ADDITINAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 10-F).
THE REACTOR MUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE 0
COMBINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMIT.
00 14 2500 000 C&E H
HEATUP RATE:
50*F/HR 4--
2000 CRITICALITY LIMIT Z 500 POINT PRESSURE PSIG TEMP.
F A
40 B
556 198 G
C 556 283 0
1186 290 1000 2250 344 F
556 323 C3 1166 330 H
2250 384 I
0 326 F
500 AC AI IOU0 200 300 400 500 600 700 Indicated Reactor Coolant System Temperature. TC, oF UNIT 3
REACTOR COOLANT SYSTEM NORMAL OPERATION HEATUP LIMITATIONS APPLICABLE FOR FIRST 5.0 EFPY fit OCONEE NUCLEAR STATION Figure 3.1.2-IC
- 1. WHEN THE DECAY HEAT REMOVAL (OH) SYSTEM IS OPERATING WITH NO RC PUMPS OPERATING, THE INDICATED 0HR SYSTEM RETURN TEMPERATURE TO THE REACTOR VESSEL SHALL BE USED.
- 2.
A MAlIMUM STEP TEMPERATURE CHANGE OF 15*F IS AILOWABLE WHEN REMOVING ALL RC PUMPS FROM OPERATION WITH THE OH SYSTEM OPERATING. THE SIP TEMPERATURE CHANGE IS DEFINED AS TIHE RC TEMP (PRIOR TO STOPPING ALL RC PUMPS) MINUS THE OH RETURN TEMP (AFTER STOPPING ALL RC PUMPS)
THE 100.F/HR RAMP DECREASE IS ALLOWABLE BOTH BEFORE AND AFTER THE STEP TEMP CHANGE.
00 2500 COOLDOWN RATE:
100 F/HR 2000 POINT PRESSURE PSIG TEMP. 'F
_1500 A
181 80 8
556 110 C556 215 0900 224 E
2250 3a Z
1000 02
.THE ACCEPTABIE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).
THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL 500 B
C REGION CONTROLLING THE LIMIT CURVE, THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25PSI AND 100 F)
A 100 200 300 400 500 600 100 Indicated Reactor Coolant System Temperature, Tc, *F UNIT 2 REACTOR COOLANT SYSTEM NORMAL OPERATION COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 5.0 EFPY venta OCONEE NUCLEAR STATION Figure 3.1.2-28
I. WHEN THE DECAY HEAT REMOVAL (OH) SYSTEM IS OPERATING WITH NO RC PUMPS OPERATING, THE INDICATED OHR SYSTEM RETURN TEMPERATURE TO THE REACTOR VESSEL SHALL BE USED.
C+
- 2. A MAXIMUM STEP TEMPERATURE CHANGE OF 750 F IS ALLOWABLE WHEN REMOVING ALL RC PUMPS FROM OPERATION WITH THE OH SYSTEM OPERATING. THE STEP TEMPERATURE CHANGE IS DEFINED AS THE o
4A RC TEMP.
(PRIOR TO STOPPING ALL RC PUMPS)
MINUS THE OH RETURN TEMP (AFTER STOPPING ALL RC PUMPS).
THE 100*F/HRrRAMP DECREASE IS ALL UWABLE BOTH BEFORE AND AFTER THE STEP TEMP.
o CHANGE.
co 2500 F
CL COOLDOWN RATE:
100aF/HR 2000 POINT PRESSURE PSIG TEMP. *F in A
169 B0
- 0 556 190 C
556 213 E0850 219 E
f 1200 250 aF 2250 318 100 THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).
THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE 500 B
REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE.
THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 100 F) 10 1
I IIIIII 100 200 300 400 500 600 Indicated Reactor Coolant System Temperature, TC. F UNIT 3 REACTOR COOLANT SYSTEM NORMAL OPERATION COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 5.0 EFPY OCONEE NUCLEAR STATION Figure 3.1.2-2C
CD THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).
THE LIMIT CURVES INCLUDE THE PRESSURE OIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE, THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 10*F) FOR COOLDOWN, NOTES I AND 2 ON FIGURE 3. 1.2-2B ARE APPLICABLE.
co co 2500 F
GHEATUP RATE.
50*F/HR COOLOOWN RATE 100*F/HR 4t%
APPLICABLE FOR COOLDOWN RATES OF < 100*F/HR 2000 POINT PRESSURE PSIG -
TEMP. Of, A
276 80 8
571 141 1500 E
C 571 255
_0 330 20 E
1530 267 F
2500 313 408 1000 a
C, LA a
560 -
6 C
mB 100 200 300 400 500 Indicated Reactor Coolant System Temperature. Tc. "F UNIT 2 REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDROSTATIC TEST HEATUP AND COOLDOWN LIMITATIONS APPLICABLE FOR 5.0 EFPY somewre OCONEE NUCLEAR STATION Figure 3.1.2-3B
THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).
THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT
(-I.
CURVE.
THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR, (25 PSI AND 100F).
FOR COOLDOWN NOTES I AND 2 ON FIG. 3.1.2-2C ARE APPLICABLE.
0 a
2500 E
G O0 HEATUP RATE:
50*F/HR 0
COOLDOWN RATE:
100*F/HR
-2000 APPLICABLE FOR COOLDOWN RATES OF < 100oF/HR 6A POINT PRESSURE PSIS TEMP. *F E
1500 A
156 80 0-D 571 255
-- *B5 71 1 6 6 00 1300 254 00 2500 32 1000 2500 400 aO 4
C m
500 go A/
Igo 200 300 400 500 600 100 Inoicated Reactor Coolant System Tempeiature. Tc. *F UNIT 3 REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDROSTATIC TES HEATUP AND COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 5.0 EFPY OCONEE NUCLEAR STATION Figure 3.1.2-3C