ML15112A994
| ML15112A994 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/10/1981 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A995 | List: |
| References | |
| NUDOCS 8103030899 | |
| Download: ML15112A994 (28) | |
Text
EUNITED 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. 93
-License No. DPR-38
- 1. The Nuclear kegulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated August 25, 1980, as supplemented December 22, 1980, and January 22, 1981, 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 3.3 of Facility Operating License No. DPR-38 is hereby amended to read as follows:
31.5 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 93 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
it o es6lt g
-2
- 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 Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 10, 1981
o
.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. 93 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee).dated August 25, 1980, as supplemented-December 22, 1980, and January 22, 1981, 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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 93 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
'I 9
-2
- 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 Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 10, 1981
o UNITED STATES NUCLEAR REGULATORY COMMISSION WASMINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90
-License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee, dated August 25, 1980, as supplemented December 22, 1980, and January 22, 1981, 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; C. 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. 90 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 Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical.
Specifications Date of Issuance:
February 10, 1981
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 93 TO DPR-38 AMENDMENT NO. 93 TO DPR-47 AMENDMENT NO. 90 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following pages nf 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 2.1-3d 2.1-3d 2.1-9 2.1-9 2.1-12 2.1-12 2.3-10 2.3-10
.1-23 3.1-23 3.2-2 3.2-2 3.5-10 3.5-10 3.5-13 3.5-13 3.5-17 3.5-17 3.5-17a 3.5-17a 3.5-17b 3.5-17b 3.5-20 3.5-20 3.5-20a 3.5-20a 3.5-20b 3.5-20b 3.5-23 3.5-23 3.5-23a 3.5-23a 3.5-23b 3.5-23b 3.5-26 3.5-26 3.5-26a 3.5-26a 3.5-26b 3.5-26b
Section Page 1.5.4 Instrument Channel Calibration 1-3 1.5.5 Heat Balance Check 1-4 1.5.6 Heat Balance Calibration 1-4 1.6 POWER DISTRIBUTION 1-4 1.7 CONTAINMENT INTEGRITY 1-4 2
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1-1 2.1 SAFETY LIMITS, REACTOR CORE 2.1-1 2.2 SAFETY LIMITS, REACTOR COOLANT SYSTEM PRESSURE 2.2-1 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE 2.3-1 INSTRUMENTATION 3
LIMITING CONDITIONS FOR OPERATION 3.0-1 3.0 LIMITING CONDITIONL FOR OPERATION 3.0-1 3.1 REACTOR COOLANT SYSTEM 3.1-1 3.1.1 Operational Components 3.1-1 3.1.2 Pressurization, Heatup, and Cooldown Limitations 3.1-3 3.1.3 Minimum Conditions for Criticality 3.1-8, 3.1.4 Reactor Coolant System Activity 3.1-10 3.1.5 Chemistry 3.1-12 3.1.6 Leakage 3.1-14 3.1.7 Moderator Temperature Coefficient of Reactivity 3.1-17 3.1.8 Single Loop Restrictions 3.1-19 3.1.9 Low Power Physics Testing Restrictions 3.1-20 3.1.10 Control Rod Operation 3.1-21 3.1.11 Shutdown Margin 3.1-23 3.1.12 Reactor Coolant System Subcooling.Margin Monitor 3.1-2.4 3.2 HIGH PRESSURE INJECTION AND CHEMICAL ADDITION SYSTEMS 3.2-1 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, REACTOR 3.3-1 BUILDING SPRAY AND LOW PRESSURE SERVICE WATER SYSTEMS Amendments Nos.
93, 93&90 ii
- 2.
The combination of radial and axial peak that causes central fuel melting at the hot spot. The limit is 20.15 kw/ft.for Unit 3.
Power peaking is not a directly observable quantity, and, therefore, limits have been established.on the bases of the reactor power imbalance produced by the power peaking.
The specified flow rates for Curves 1, 2 and 3 of Figure 2.1-2C correspond to the expected minimum flow rates with four pumps, three pumps and one pump in each loop, respectively.
The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup independent DNBR rod bow penalty for the ap plicable cycle minus a credit of 1% for the flow area reduction factor used in the hot channel analysis (4).
All plant operating limits are presently based on an original method of cal culating rod bowing penalties that are more conservative than those that would be obtained with new approved procedures (4).
For Cycle 6 operation, this sub rogation results in a 10% DNBR margin, which is partially used to offset the reduction in DNBR due to fuel rod bowing.
The maximum thermal power for three-pump operation is 87.2 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.08 80.7 percent power plus the maximum calibration and-instrument error.
The.maximum thermal power for other coolant pump conditions are produced in a similar manner.
For each curve of Figure 2.1-3C a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.30 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation. The curve of Figure 2.1-1C is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3C.
References (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000, March 1970.
(2) Oconee 3, Cycle 3 - Reload Report -
BAW-1453, August, 1977.
(3) Amendment 1 - Oconee 3, Cycle 4 - Reload Report - BAW-1486, June 12, 1978.
(4) Oconee 3, Cycle 6 -
Reload Report -
BAW-1634, August, 1980 Amendments Nos, 93, 93,
& 90 2.1-3d
THERMAL POWER LEVEL.
120 112
-27.44,11 7)
(31.36,112) j ACCEPTABLE 110
=,
- 0. 79 4 PUMP OPERATION 50 M2
-2 54 I
300 II I
(-55.90) g-90 (40.90)
ACCEPTABLE 3 & 4 PUMP
-80 OPERATI ON 70 55, 65. 17)
(40,65. 17)
- 59. 42 ACCEPTABLE 60 2, 3 & 4 PUMP PERATION 50
-8 50
-0 3
-0
-14 0
20 3I 0
0 6
a55.37.r42)
Po(40, 37 42) 30 20 c
UNACCEPTABLEU OPERATIONNEE-NULOPERATION FeIgue I
12
-6O
-50
-40
-30
-20
-10 0
10 20 30 40 50 60 Reactor Power Imnalance, %
CORE PROTECTION SAFETY LIMITS UNIT 3 KPW OCONEE NUCLEAR STATION Figure 2.1-2C Amendments Nos. 930 930.4 90
- 2. 1-9
2400 ACCEPTABLE OPERATION to 2200 CU 0
8 1600 1
1 C-3 1800 560 580 600 620 640 Reactor Coolant Outlet TemperatureF
- Power, Pumps Typc. of Curve Coolant Flow, gpni OpRat ng Lim L 1
374,880 (100%)*
112 4
DN3R 2
280,035 (74.7%)
87.2 3
DNBR 3
183,690 (49:0%)
59.4 2
Quality
- 106.5% of first-core design flow.
CORE PROTECTION SAFETY LIMITS UN IT 3 Amendments Nos.
93, 93, & 90 OCONEE NUCLEAR STATION Figure 2.1-3C
THERMAL POWER LEVEL.
108 110
(-14., 108)
(17, 108)
ACCEPTABLE 4 PuW 1P 0
1= 0.88 JOPERATION 12 1.76 90
(-
40,85)
(30
- 80. 67 IACCEPTABLE 80 PuWP 70 OPERATION 60
(-40.57 87)
(30 57.67) 52.92 ACCEPTABLE 5
40 12.3 & 4 PuW 40 OPERATION 30 (30, 29.92) 20 UNACCEPTABLE UNACCEPTABLE OPERATION 710 OPERATION II I
a l
m III
-60
-50
-40
-30
-20
-10 0
10 20 30 40 50 Power Imnalance, %
PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS UNIT 3 POWEE OCONEE NUCLEAR STATION Figure 2.3-2C Amendments Nos.
93, 93,
& 90 2..3-10
3.1..11 Shutdown Margin Specification The available shutdown margin during all system conditions except refueling shall be greater than 1% ak/k with the highest worth control rod fully withdrawn.
3ases A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and
- 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
During power operation and startup the SHUTDOWN MARGIN is known to be within limis if all control rods are OPERABLE and withdrawn to or beyond the insertion limits specified in Specification 3.5.2.
During refueling conditions equivalent protection is provided in the requirements of Specification 3.8.4.
Amendments Nos.
93,93
, & 90 3.1-23
Bases The high pressure injection system and chemical addition system provide con trol of the reactor coolant system boron concentration.(1)
This is normally accomplished by using any of the three high pressure injection pumps in series with a boric acid pump associated with either the boric acid mix tank or the concentrated boric acid storage tank. An alternate method of boration will be the use of the high pressure injection pumps taking suction directly from the borated water storage tank.(2)
The quantity of boric acid in storage in the concentrated boric acid storage tank or the borated water storage tank is sufficient to borate the reactor coolant system to a 1% dk/k subcritical margin at cold conditions (70 F) with the maximum worth stuck rod and no credit for xenon at the worst time in core life. The current cycles for each unit, Oconee 1 Cycle 6, Oconee 2 Cycle 5, and Oconee 3 Cycle 6 were analyzed with the most limiting case selected as the basis for all three units.
Since only the present cycles were analyzed, the specifications will be reevaluated with each reload. A minimum of 995 ft. 3 of 8,700 ppm boric acid in the concentrated boric acid storage tank, or a minimum of 350,000 gallons of 1800 ppm boric acid in the borated water storage tank (3) will satisfy the requirements. The volume requirements include a 10%
margin apd, in addition, Allow for a deviation of 10 EFPD in the cycle length.
The specification assures that two supplies are available whenever the reactor is critical so that a single failure will not prevent boration to a cold con dition. The required amount of boric acid can be added in several ways. Using only one 10 gpm.boric acid pump taking suction from the concentrated boric acid storage tank would require approximately 12.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> to inject the required boron. An alternate method of addition is to inject boric acid from the borated water storage tank using the makeup pumps. The required boric acid can be injected in less than six hours using only one of the makeup pumps.
The concentration of boron in the concentrated boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason, and to assure a flow of boric acid is available when needed, these tanks and their associated piping will be kept at least 10oF above the crystallization temperature for the concentration present. The boric acid concentration of 8,700 ppm in the concentrated boric acid storage tank cor responds to a crystallization temperature of 77 F and therefore a temperature requirement of 87 0F. Once in the high pressure injection system, the concen trate is sufficiently well mixed and diluted so that normal system temperatures assure boric acid solubility.
REFERENCES (1) FSAR, Section 9.1; 9.2.
(Q) FSAR, Figure 6.2 (3) Technical Specification 3.3 Amendments Nos. 93, 93, & 90 3.2-2
3.5.2.6 Xenon Reactivity Except for physics tests, reactor power shall not be increased above the power level-cutoff shown in Figures 3.5.2-lA1, and 3.5.2-LA2 for Unit 1; Figures 3.5.2 IBI, and 3.5.2-1B2, for Unit 2; and Figures 3.5.2-II, 3.5.2-1C2, and 3.5.2-1C3 for Unit 3 unless one of the following conditions is satisfied:
- 1.
Xenon reactivity did not deviate more than 10 percent from the equi librium value for operation at steady state power.
- 2.
Xenon reactivity deviated more than 10 percent but is now within 10 percent of the equilibrium value for operation at steady state rated power and has passed its final maximum or.minimum peak during its ap proach to its equilibrium value for operation at the power level cut off.
- 3.
Except for xenon free startup (when 2. applies), the reactor has oper ated within a range of 87 to 92 percent of rated thermal power for a period exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
3.5.2.7 1 Reactor power imbalance shall be monitored on a frequency not to exceed two hours during power operation above 40 percent rated power. Except for physics tests, imbalance shall be maintained within the envelope defined by Figures 3.5.2-3A1, 3.5.2-3A2, 3.5.2-3B1, 3.5.2-3C1, 3.5.2-3C2 and 3.5.2-3C3. If the imbalance is not within the envelope defined by these figures, corrective measures shall be taken to achieve an acceptable imbalance. If an acceptable imbalance is not achieved within two hours, reactor power shall be reduced until imbalance limits are met.
3.5.2.8 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the manager or his designated alternate.
3.5.2.9 The operational limit curves of Technical Specifications 3.5. 2.5.c.
and 3.5.2.7 are valid for a nominal design cycle length, as defined in the Safety Evaluation Report for the appropriate unit and cycle.
Operation beyond the nominal design cycle length is permitted provided that an evaluation is performed to verify that the operational limit curves are valid for extended operation. If the operational limit curves are not valid for the extended period of operation, appropriate limits will be established and the Technical Specification curves will be modified as required.
Amendments Nos.
93,
93, & 90 3.5-10.
REFERENCES (1) FSAR, Section 3.2.2.1.2 (2) FSAR, Section 14.2.2.2 (3) FSAR, SUPPLEMENT 9 (4) B&W FUEL DENSIFICATION REPORT BAW-1409 (UNIT 1)
BAW-1396 (UNIT 2)
BAW-1400 (UNIT 3)
(5) Oconee 1, Cycle 4 - Reload Report -
BAW 1447, March, 1977, Section 7.11 (6) Oconee 3, Cycle 6 -
Reload Report -
BAW-1634, August, 1980.
Amendments Nos.
93, 93, & 90 3.5-13
100 (158.102) 1 274. 102 POWER LEVEL 90 -
-(
6 2
CUTOFF =
100% FP)
.(25.80 LIMIT RESTRICTED 70 REGION OPERATION IN THIS KW FT LIMIT U
60 -
REGION NOT ALLOWED 50 (83.50)
PERMISSIBLE OPERATING REGION 40 30 20 10 0
20 40 60 80 100 120 140 160 10 200 220 240 260 280 300 0
25 50 75 100 Roa Inoex. ; Witnarawn SanK 5 0
25 50 75 100 Ban 6
0 25 50 75 100 I
I I
Bank 7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 0 TO 50 (+10, -0) EFPD UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2,1C1 Amendments Nos. 93, 93,
& 90 3.5-17
158, 102)
(267 102) 100 POWER LEVEL 90.(261.92)
CUTOFF 1000' FP) 80 SHUTDOWN MARGIN **4t (251.80 LIMIT RESTRICTED 70 REGION p
OPERATION IN THIS
.ap KW FT LIMIT 60 REGION NOT ALLOWED CN 50 (83,50)
PERMISSIBLE OPERATING REGION a
40 30 20
'0 0
20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0
25 50 75 100 Raa Index. 1 tndrawn Bank 5 0
25 50 75 100 BanK6 0
25 50 75 Bank 7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 50 (+ 10, -0) TO 200 (+ 10) EFPD UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-1C2 Amendments Nos. 93, 93, & 90 3.5-17a
206 102) 267 102)
I00 POWER LEVEL (261 92) 90 CUTOFF = 100 FP 80 SHUTDOWN MARGIN RCE1 (251 80)
LIMIT RESTRICTED REGION 70 OPERATION IN THIS REGION NOT ALLOWED 60 U(135
- 50)
PERMISSIBLE OPERATING REGION 40 30
- 84. 27) 20 0
.).8 5
0 20 40 60 80 100 120 140 150 180 200 220 240 260 280 300 0
25 50 75 100 Roo Inaex, itnorawn SBanK 5 0
25 50 75 100 BanK 6 0
.25 50 715 100 Bank 7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION AFTER 200 (+ 10) EFPO UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-1C3 Amendments Nos.
93, 93,
& 90 3.5-17b
A RESTRICTED 3-RCP 100 8
RESTRICTED 2.3-RCP 90 80 242.77)
<158.77)
(300
- 77) 70 3-RCP SHUTDOWN MARGIN LIMIT MR I
B PERMSSIBLE OPERATING 60 REGION 3-RCP el(15852)
(300.52) 502-RCP (164.52)
SM LIMI 40 A
83 38)
KW FT LIMIT 30 PERMISSIBLE OPERATING REGION 94,30) 2.3-RCP (83. 26)
(0 1 3.12)
A (0.11) 10 (0.8)
.B 0
0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0
25 50 75 100 Roo Index, Witnorawn Bank 5 0
25 50 75 100 I
I I
Bank 6 0
25 50 75 100 I
I I
I Bank 7 ROD POSITION LIMITS FOR TWO- & THREE-PUMP OPERATION FROM 0 to 200 + 10 EFPD UNIT 3 ow' OCONEE NUCLEAR STATION Figure 3.5.2-2C1 Amendmentp Nos. 93,
93, & 90 3.5.20
100 A
RESTRICT 3-RCP B
RESTRICT 2.3-RCP 90 80 208 77242,77)
(300. 77) 70 OPERATION IN THIS REGION NOT ALLOWED L
60 CIO 208,52) 158.50)
(300, 52) 50 k
40 3-RCP (135.38) t 2-RCP SHUTDOWN MARGIN SHUTD0WN MARGIN 30 -LIMIT
,l\\
LIMIT 69(135.25)
PERMISSIBLE OPERATING REGION 2.3-RCP (58. 12) 10 (0OB) 0 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0
25 50 75 100 Rod Index, Witndrawn Bank 5 0
25 50 75 100 Bank 6 0
- 25.
50 75 100 Bank 7 ROD POSITION LIMITS FOR TWO- & THREE-PUMP OPERATION AFTER 200 + 10 EFPD UNIT 3 KEPOWE OCONEE NUCLEAR STATION Figure 3.5.2-2C2 Amendments Nos.
93, 93, & 90 3.5-20a
Figure 3.5.2-2C3 Deleted During Oconee Unit 3, Cycle 6 Operation Amendments Nos. 93, 93, & 90 3.5-20b
RESTRICTED REGION (23. 102)
(-18, 102)
- 100
(-28,92)
(25,92)
(-36, 80) 80 (25.80)
- 60 60 PERMISSIBLE OPERATING REGION a 0
40 20 0I
-40
-30
-20
-10 0
10 20 30 Axial Power Imbalance, %
OPERATIONAL POWER IMBALANCE ENVELOPE FROM 0 TO 50 (+ 10, -0) EFPD UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-3C1 Amendments Nos.
93, 93 90 3.5-23
RESTRICTEO REGION (23.102)
-30, 102) 100
-29 92)
(25 92)
.38 80 80 25 80) 60 PERMISSIBLE OPERATING REGION 40 0
-40.
.30
-20
-10 0
+10
+20
+30 Axial Power Imoalance.
OPERATIONAL POWER IMBALANCE ENVELOPE AFTER 50 (+ 10, -0) EFPO UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-3C2 Amendments Nos. 93, 93
& 90 3.5-23a
Figure 3.5.2-3C3 Deleted During Oconee Unit 3, Cycle 6 Operation Amendments Nos.
93, 93
,& :90 3.5-Z3b
(6.5,102) 100 (35,102)
RESTRICTED REGION 6.5.92)
(38,92) 80 (
(0,80)
(57,80) 60 iloo50) 40 PERMISSIBLE OPERATING REGION 20 0
J 0
20 40 60 80 100 Bank 8 Position, % Withdrawn APSR POSITION LIMITS FOR OPERATION FROM 0 TO 50 (+ 10, -0) EFPD
- IOCONEE NUCLEAR STATION Figure 93.5.2-431 Amendments-Nos. 93,93,&
903.5-26,
(6 5.102) 100 (36, 102)
-RESTRICTEO REGION 6 5. 92)
(34. 5.92) 80
. (0.80)
(55. 80) 60 (100
- 50) 40 PERMISSIBLE OPERATING REGION 20 0
20 40 60 80 100 Bank 8 Position, "o Witndrawn APSR POSITION LIMITS FOR OPERATION FROM 50 (+10, -0) TO 200 (+ 10) EFPD UNIT 3 EIPOWE OCONEE NUCLEAR STATION Figure 3.5.2-4C2 Amendments Nos.
93,93 90
- 3. 5-26a
13, 102)
(36, 102) 100 100 RESTRICTED REGION (34.5,92) go 80 (0.80)
(55.80)
SBa (100 50)
PERMISSIBLE OPERATING REGION 40 20 0
20 40 60 80 100 Bank 8 Position, % Witnarawn APSR POSITION LIMITS FOR OPERATION AFTER 200 (+ 10) EFPO UNIT 3 OMEOWEJ OCONEE NUCLEAR STATION Figure 3.5.2-4C3 3.5-2tb Amendments Nos.
93, 93, & 90