ML15113A096
| ML15113A096 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/15/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A097 | List: |
| References | |
| DPR-38-A-129, DPR-47-A-129, DPR-55-A-126 NUDOCS 8405240282 | |
| Download: ML15113A096 (74) | |
Text
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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.129 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 13, 1984, 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 reaulations 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.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.129. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
40240282l 640515 PDR.ADOCK 05000269 IF PDR
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION John
.Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Chances to the Technical Specifications Date of Issuance: May 15, 1984
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. 129 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 13, 1984, 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.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.129 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 John F.dStolz, Chief Operating Reactors Branch No. 4 Division of Licensina
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 15, 1984
UNITED STATES.
NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.126 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 13, 1984, 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 conductedin 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.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.126 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 John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Chances to the Technical Specifications Date of Issuance:
May 15, 1984
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO.1 29 TO DPR-38 AMENDMENT NO.1 29 TO DPR-47 AMENDMENT NO.126 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 iii iii vi vi viii viii ix ix x
x 2.1-3d 2.1-3d 2.1-9 2.1-9 2.3-2 2.3-2 2.3-10 2.3-10 3.5-9 3.5-9 3.5-10 3.5-10 3.5-11 3.5-11 3.5-15 3.5-15 (3 pages) 3.5-15a 3.5-15b 3.5-16 3.6-16 (3 pages) 3.5-16a 3.5-16b 3.5-17 3.5-17 (3 pages) 3.5-17a 3.5-17b 3.5-18 3.5-18 (3 pages) 3.5-18a 3.5-18b 3.5-18c 3.5-18d 3.5-18e 3.5-19 3.5-19 (3 pages) 3.5-19a 3.5-19b 3.5-19c 3.5-19d 3.5-19e
-2 Remove Pages Insert Pages 3.5-20 3.5-20 (3 pages) 3.5-20a 3.5-20b 3.5-20c 3.5-20d 3.5-20e 3.5-21 3.5-21 (3 pages) 3.5-21a 3.5-21b 3.5-22 3.5-22 (3 pages) 3.5-22a 3.5-23 3.5-23 (3 pages) 3.5-23a 3.5-23b 3.5-24 3.5-24 (3 pages) 3.5-24a 3.5-24b 3.5-25 3.5-25 (2 pages) 3.5-26 3.5-26 (2 pages) 3.5-26a 3.5-26b 3.5-27 3.5-27 (3 pages) 3.5-28 3.5-28 3.5-29 3.5-29 (2 pages) 3.5-30 3.5-30 3.5-31 3.5-31 3.5-32 3.5-32 3.5-33 3.5-33 3.5-34 3.5-34 3.5-35 3.5-35 3.5-36 3.5-36 3.5-37 3.5-37 3.5-38 3.5-38 3.5-39 3.5-39 3.5-40 3.5-40 3.5-41 3.5-42 3.5-43
Section Page 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 Criticalitv 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 Temverature 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 3.1-24 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 3.4 SECONDARY SYSTEM DECAY HEAT REMOVAL 3.4-1 3.5 INSTRUMENTATION SYSTEMS 3.5-1 3.5.1 Operational Safety Instrumentation 3.5-1 3.5.2 Control Rod Group and Power Distribution Limits 3.5-6 3.5.3 Engineered Safety Features Protective System 3.5-31 Actuation Setpoints 3.5.4 Incore Instrumentation 3.5-33 3.5.5 Radioactive Effluent Monitoring Instrumentation 3.5-37 3.6 REACTOR BUILDING 3.6-1 3.7 AUXILIARY ELECTRICAL SYSTEMS 3.7-1 3.8 FUEL LOADING AND REFUELING 3.8-1 3.9 RADIOACTIVE LIQUID EFFLUENTS 3.9-1 Amendments Nos. 129, 129, 3 126
LIST OF TABLES Table No.
Page 2.3-1A Reactor Protective System Trip Setting.Limits - Unit 1 2.3-11 2.3-1B Reactor Protective System Trip Setting Limits - Unit 2 2.3-12 2.3-1C Reactor Protective System Trip Setting Limits - Unit 3
.2.3-13 3.5-1-1 Instruments Operating Conditions 3.5-4 3.5-1.
Quadrant Power Tilt Limits 3.5-14 3.5.5-1 Liquid Effluent Monitoring Instrumentation Operating 3.5-39 Conditions 3.5.5-2 Gaseous*Process and Effluent Monitoring Instrumentation 3.5-41 Operating Conditions 3.7-1 Operability Requirements for the Emergency Power 3.7-14 Switching Logic Circuits 3.17-1 Fire Protection & Detection Systems 3.17-5 4.1-1 Instrument Surveillance Requirements 4.1-3 4.1-2 Minimum Equipment Test Frequency 4.1-9 4.1-3 Minimum Sampling Frequency and Analysis Program 4.1-10 4.1-4 Radioactive Effluent Monitoring Instrumentation 4.1-16 Surveillance Requirements 4.2-1 Oconee Nuclear Station Capsule Assembly Withdrawal 4.2-3 Schedule at Crystal River Unit No. 3 4.4-1 List of Penetrations with IOCFR50 Appendix J Test 4.4-6 Requirements 4.11-1 Radiological Environmental Monitoring Program 4.11-3 4.11-2 Maximum Values for the Lower Limits of Detection (LLD) 4.11-5 4.11-3 Reporting Levels for Radioactivity Concentrations in 4.11-8 Environmental Samples 4.17-1 Steam Generator Tube Inspection 4.17-6 6.1-1 Minimum Operating.Shift Requirements with Fuel in Three 6.1-6 Reactor Vessels Amendments Nos.
129,129, &126 vi
LIST OF FIGURES (CONT'D)
Figure Pg 3.1.2-3A Reactor Coolant System Inservice Leak and Hydrostatic 3.1-7c Test Heatup and Cooldown Limitation -
Unit 1 3.1.2-3B Reactor Coolant System Inservice Leak and Hydrostatic 3.1-7d Test Heatup and Cooldown Limitation -.Unit 2 3.1.2-3C Reactor Coolant System Inservice Leak and Hydrostatic 3.1-7e Test Heatup and Cooldown Limitation - Unit 3 3.1.10-1 Limiting Pressure vs. Temperature Curve for 100 STD 3.1-22 cc/Liter HZ0 3.5.2-1 Rod Position Limits for Four Pump Operation - Unit 1 3.5-15 3.5.2-2 Rod Position Limits for Four Pump Operation - Unit 2 3.5-16 3.5.2-3 Rod Position Limits for Four Pump Operation - Unit 3 3.5-17 3.5.2-4 Rod Position Limits for Three Pump Operation -
Unit 1 3.5-18 3.5.2-5 Rod Position Limits for Three Pump Operation - Unit 2 3.5-19 3.5.2-6 Rod Position Limits for Three Pump Operation -
Unit 3 3.5-20 3.5.2-7 Rod Position Limits for Two Pump Operation -
Unit 1 3.5-21 3.5.2-8 Rod Position Limits for Two Pump Operation - Unit 2 3.5-22 3.5.2-9 Rod Position Limits for Two Pump Operation - Unit 3 3.5-23 3.5.2-10 Operational Power Imbalance Envelope - Unit 1 3.5-24 3.5.2-11 Operational Power Imbalance Envelope - Unit 2 3.5-25 3.5.2-12 Operational Power Imbalance Envelope - Unit 3 3.5-26 3.5.2-13 APSR Position Limits -
Unit 1 3.5-27 3.5.2-14 APSR Position Limits -
Unit 2 3.5-28 3.5.2-15 APSR Position Limits -
Unit 3 3.5-29 3.5.2-16 LOCA - Limited Maximum Allowable Linear Heat.
3.5-30 3.5.4-1 Incore Instrumentation Specification Axial Imbalance 3.5-34 Indication 3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt 3.5-35 Indication Amendments Nos. 129,129 126 Viii
LIST OF FIGURES (CONT'D)
Figure Page 3.5.4-3 Incore Instriumentation Specification 3.5-36 4.5.1-1 High Pressure Injection Pump Characteristics 4.5-4 4.5.1-2 Low Pressure Injection Pump Characteristics 4.5-5 4.5.2-1 Acceptance Curve fa Reactor Building Spray Pumps 4.5-9 6-.1-1 Station Organization Chart 6.1-7 6.1-2 Management Organization Chart 6.1-8 Amendments Nos.
129
, 129
, & 126 ix
THIS PAGE INTENTIONALLY LEFT BLANK Amendments Nos. 129 129, & 126 x
- 2.
The combination of radial and axial peak that causes central fuel meltihg at the hot spot. The limits for Unit 3 are 20.5 kw/ft for fuel rod burn up less than or equal to 10,000 NWD/MTU and 21.5 kw/ft -
after 10,000 MWD/MTU.
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 of Figure 2.1-3C correspond to the expected minimum flow rates with four pumps, three pumps, and one pump in each loop, respectively.
Due to the reduced power production capability of the fuel with increasing irradiation, the DNBR penalty for rod bow has been determined to be insignificant and unnecessary.
(4,5)
The maximum thermal power for three-pump operation is 88.8 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 (Reference 4).
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-IC 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 8 -
Reload Report -
DPC-RD-2003, February 1984.
(5) Fuel Rod Bowing in Babcock & Wilcox Fuel Designs, BAW-10147P-A, Rev. 1, Babcock & Wilcox, May 1983.
Amendments Nos. 129, 129, & 126 2.1-3d
THERMAL POWER LEVEL,%
-120
{-29.), 11-2.0)
(29.5, 112.0)
Ml =0.60 M2 = -0.60 ACCEPTABLE
(-49.5, 100.0) 1 4 PUMP
-100 (49.5100.0)
OPERATION
(
29.5,88.8)
(29.5, 88.8)
ACCEPTAB LE
-80
(-49.5, 76.07) 1, 3 & 4 PUMP
.)(49.5, 76.8)
OPERATION
(-29.5, 61.1)
(29.5, 61.1) 60 ACCEPTA8 LE
(-49.5, 49.1)."2, 3, & 4 PUMP
>(49.5, 49.1)
OPERATION 4
I-4
-20
-60
-40
-20 20 40 60 REACTOR POWER IMBALANCE,%
CORE PROTECTION SAFETY LIMITS UNIT 3 u!own OCONEE NUCLEAR STATION Amendments los. 129, 129,
& 126 2.1-9 Figure 2.1-2C
During normal plant operation with all reactor coolant pumps operating, reactor trip is-initiated when the reactor power level reaches 105.5% of rated power. Adding to this the possible variation in trip setpoints due to calibration and instrument errors, the maximum actual power at which a trip would be actuated could be 112%, which is more conservative than the value used in the safety analysis.
(4)
Overpower Trip Based on FKw and Imbalance The power level trip set point.produced by the reactor coolant system flow is based on a power-to-flow ratio which has been established to accommodate the most severe thermal transient considered in the design, the loss-of-coolant flow accident from high power. Analysis has demonstrated that the specified power-to-flow ratio is adequate to prevent a DNBR of less than 1.3 should a low flow condition exist due to any electrical malfunction.
The power level trip setpoint produced by the power-to-flow ratio provides both high power level and low flow protection in the event the reactor power level increases or the reactor coolant flow rate decreases. The power level trip setpoint produced by the power-to-flow ratio provides overpower DNB pro tection for all modes of pump operation. For every flow rate there is a maxi mum permissible power level, and for every power level there is a minimum permissible low flow rate. Typical power level and low flow rate combinations for the pump situations of Table 2.3-IA are as follows:
- 1. Trip would occur when four reactor coolant pumps are operating if power is 107% and reactor flow rate is.100%, or flow rate is 93.46% and power level is 100%.
- 2. Trip would occur when three reactor coolant pumps are operating if power is 79.92% and reactor flow rate is 74.7% or flow rate is 70.09% and power level is 75%.
- 3. Trip would occur when one reactor coolant pump is operating in each loop (total of two pumps operating) if the power is 52.43% and reactor flow rate is 49.0% or flow rate is 45.79% and the power level is 49%.
The flux-to-flow ratios account for calibration and instrument errors and the maximum variation from the RC flow signal in such a manner that the reactor protective system receives a conservative indication of RC flow. For unit 1, the maximum calibration and instrument errors are algebraically summed to determine the string errors in the safety calcu lations. Units 2 and 3 employ a Monte-Carlo simulation technique with final string errors corresponding to the 95/95 tolerance limits.
The power-imbalance boundaries are established in order to prevent reactor thermal limits from being exceeded. These thermal limits are either power peaking kw/ft limits or DNBR limits.
The reactor power imbalance (power in the top half of core minus power in the bottom half of core) reduces the power level trip produced by the power-to-flow ratio such that the boundaries of Figure 2.3-2A -
Unit 1 are produced. The power-to-flow.ratio reduces the power 2.3-2B - Unit 2 2.3-2C - Unit 3 Amendments Nos.129
,129
, & 126 2.3-2
THERMAL POWER LEVEL,%
(-12.5, 108.0)
(12.5. 18.0.)
M2 = -0.80
-100 ACCEP ABLE 4
(-35.0, 90.0)
UMP OP ERATIO (35.0, 90.0)
(-12.5,80.65)
(12.5, 80.65) 800 65 PMP OPERATION
(-35.0, 62.65)
(35.0, 62.65)
-60
(-12.5, 52.9)
(12.5, 52.9)
A CEPTA LE 2,3, 4
PUMP OP RATIO
-0
(-35.0, 34.9) <
r (35.0, 34.9)
-20
-60
-40
-20 20 40 60 REACTOR POWER IMBALANCE, %
PROTECTIVE SYSTEM.
MAXIMUM ALLOWABLE SETPOINTS -
UNIT 3 nomOCONEE NUCLEAR STATION Amendments Nos.
129,129
& 126 2.3-10 CE LR A
Figure 2.3-2C
- f.
If the maximum positive quadrant power tilt exceeds the Maximum Limit of Table 3.5-1, the reactor shall be shut down within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Subsequent reactor operation is permitted for the purpose of measurement, testing, and corrective action provided the ther mal power and the Nuclear Overpower Trip Setpoints allowable for the reactor coolant pump combination are restricted by a reduc tion of 2% of thermal power for each 1% tilt for the maximum tilt observed prior to shutdown.
- g.
Quadrant power-tilt shall be monitored on a minimum frequency of once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during power operation above 15% full power.
3.5.2.5 Control Rod Positions
- a.
Technical Specification 3.1.3.5 does not prohibit the exercising of individual safety rods as required by Table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2.
- b.
Except for physics tests, operating rod group overlap shall be 25% +/- 5% between two sequential groups.
If this limit is ex ceeded, corrective measures shall be taken immediately to achieve an acceptable overlap. Acceptable overlap shall be attained within two hours or the reactor shall be placed in a hot shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c.
Position limits are specified for regulating and axial power shaping control rods.
Except for physics tests or exercising control rods, the regulating control rod insertion/withdrawal limits are specified on figures 3.5.2-1 (Unit 1) for four 3.5.2-2 (Unit 2) 3.5.2-3 (Unit 3) pump operation, on figures 3.5.2-4 (Unit 1) for three 3.5.2-5 (Unit 2) 3.5.2-6 (Unit 3) pump operation, and on figures 3.5.2-7 (Unit 1) for two 3.5.2-8 (Unit 2) 3.5.2-9 (Unit 3) pump operation. Also, excepting physics tests or exercising control rods, the axial power shaping control rod insertion/
withdrawal limits are specified on figures 3.5.2-13 (Unit 1) 3.5.2-14 (Unit 2) 3.5.2-15 (Unit 3)
If the control rod position limits are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod position. An acceptable control rod position shall then be attained within two hours.
The minimum shutdown margin required by Specification 3.5.2.1 shall be maintained at all times.
Amendments Nos. 129 129
, & 126 3.5-9
3.5.2.6 Xenon Reactivity Except for physics tests, reactor power shall not be increased above the power level-cutoff shown in Figures 3.5.2-1 (Unit 1) unless one of the following 3.5.2-2 (Unit 2) 3.5.2-3 (Unit 3) conditions is satisfied:
- 1.
Xenon reactivity did not deviate more than 10 percent from the equilibrium 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 approach to its equilibrium value for operation at the power level cutoff.
- 3.
Except for xenon free startup (when 2. applies), the reactor has operated 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 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 3.5.2-10 (Unit 1).
If the imbalance 3.5.2-11 (Unit 2).
3.5.2-12 (Unit 3) 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 pro vided 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 the operation, appropriate limits will be established and the Technical Specification curves will be modified as required.
Amendments Nos. 129
- 129,
& 126 3.5-10
Bases Operation at power with an inoperable control rod is permitted within the limits provided. These limits assure that an acceptable power distribution is maintained and that the potential effects of rod misalignment on associ ated accident analyses are minimized. For a rod declared inoperable due to misa-l-ignment, the-rod with the greatest misalignment shall be evaluated first.
Additionally, the position of the rod declared inoperable due to misalignment shall not be included in computing the average position of the group for deter mining the -operability of -rods -with lesser misalignments.
'hen a control rod is declared inoperable, boration may be initiated to achieve the existence of 1% Ak/k hot -shutdown margin.
The power-imbalance envelope defined in Figures 3.5.2-10 (Unit 1) 3.5.2-11 (Unit 2) 3.5.2-12 (Unit 3) is based on LOCA analyses which have defined the maximum linear heat rate (see Figure 3.5.2-16) such that the maximum clad temperature will not exceed the Final Acceptance Criteria. Corrective measures will be taken immediately should the indicated quadrant tilt, rod position, or imbalance be outside their specified boundary. Operation in a situation that would cause the Final Acceptance Criteria to be approached should a LOCA occur is highly improbable because all of the power distribution parameters (quadrant tilt, rod position, and imbalance) must be at their limits while simultaneously all other engineer ing and uncertainty factors are also at their limits.*
Conservatism is introduced by application of:
- a.
Nuclear uncertainty factors
- b.
Thermal calibration
- c.
Fuel densification power spike factors (Units 1 and 2 only)
- d.
Hot rod manufacturing tolerance factors
- e.
Fuel rod bowing power spike factors The 25% t 5% overlap between successive control rod groups is allowed since the worth of a rod is lower at the upper and lower part of the stroke. Con trol rods are arranged in groups or banks defined as follows:
Group Function 1
Safety 2
Safety 3
Safety 4
Safety 5
Regulating 6
Regulating 7
APSR (axial power shaping bank)
Actual operating limits depend on whether or not incore or excore detectors are used and their respective instrument calibration errors.
The method.
used to define the operating limits is defined in plant operating procedures.
Amendments Nos. 129
, 129, & 126 3.5-11
OPERATION (204. 102)
(280, 102) 100 NOT ALLOWED SHUTDOWN (300,102) POWER LEVEL MARGIN (275,92)
CUTOFF= 1004FP so (273,80)
OPERATION RESTRICTED 60 40 R139 5n0)x (200,50)a OPERATION 20 ACCEPTABLE (64,15)
(0,7.5) 0 LLI 0
100 200 300 Roa incex, I Witnerawn GR6 5 O
25 75 100 GR 7 L O
25 100 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 0 TO 26 +10/-0 EFPD UNIT 1 WOUE=0 OCONEE NUCLEAR STATION Figure 3.5.2-1 (1 of 3)
Amendments Nos. 129, 129, & 126 3.5-15
POWER LEVEL CUTOFF= 100% F (275, 102 )(300,102) 100 (238, 102).
(270, 92) o PERATION 80 SHUTDON LNIMITRESTRICTE (266,80)
MARGIN LIMIT OPERATION NOT 60.
ALLOWED 0
(173, 50)
- (200,
- 50) 40 OPERATION ACCEPTABLE e-20
- (8 1,15) 0 I
O 100 200 300 Roa Inaex, % wi tnarawn GR5 0
75 100 GR 6 0
25 75 100 GR 7 I 0
25 100 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 26 +10/-0 TO 200 t10 EFPD UNIT 1 UEowl OCONEE NUCLEAR STATION Figure 3.5.2-1 (2 oF 3)
Amendments Nos.
129, 129, & 126
(275,102) 100 (238,102)
(300,102) POWER LEVEL (CUTOFF 100% FF PERAT ION 80 SHUTDOWN 0
(26,8l MARGIN LIMIT RESTRICTE (30,3)
OPERATION NOT 6 o ALLOWED (11
- (200,50) a 40 OPERATION ACCEPTABLE 20 (0.6.8) 0 1
0 100 200 300 Ra Index, s Witnarawn GR5 0
75 100 GR 6 I I
1 0
25 75 100 GR 7 1 1
0 25 100 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION AFTER 200 t 10 EFPD UNIT 1 (arrant OCONEE NUCLEAR STATION Figure 3.5.2-1 (3 of 3)
Amendments Nos.
129,129
, & 126
POWER LEVEL 110.70 100.
(150,102?
CUTOFF*1Co% FP (260.90) 80-SHUTDOWN MARGIN (250,80)
LIMIT RESTRICTED OPERATION CL
- 60.
UNACCEPTABLE OOPERAAION 0
40 ACCEPTABLE 0 P C.R AT O0N 20 (0,5) 0 50 100 150 200 250 300 ROD INOEX.%WO
-0 25 50 75 100 BANK 5 0
25 50 75 100 SANK 6 0
25 50 75 100 SANK 7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION FROM 0 TO 25 (+10,
-0)
EFPD UNIT 2 pPowu OCONEE NUCLEAR STATiON
-z Figure 3.5.2-2 (1 of 3)
Amendments Nos.
129,129
, &126 3.5-16
POW ER I-5S E 27 1 21 ( 00 1 2 100 (150.102 (75.102)
SHUTDOWN (250.90)
MA RGIN LIMIT so-(240.80)
RESTRICTSO OPERATION UNACCEPTABLE 60-OPERAION (90,50)
(200.50) 0 ACCEPTABLE OPERATION (40,15)
(90.15)
(05)
- 0.
0 50 100 150 250 M
R00 INOEX,%WO 0
25 50 75 100 BANK S 0
25 50 75 100 BANK 5 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR FOUR PU-IP OPERATION FROM 25 (+10, -0) TO 200 +/- 10 EFD UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-2 (2 of 3)
Amendments Nos.
129
, 129
, & 126
POWER LEVEL CUTOFF-1 0 0 % FP 100 (220.102)
(275,10)(2C0.102) 250.90) 80 R ESTR ICTED OPERATION (240.80)
UNACCEPTA8LE OPERATION
- U.
60 LU
.(200.50)
SHUTDOWN MARGIN ACCEPTABLE LIMIT OPERATION 20 (0,5)(9 15 05 00 150 200 250 2
00RD INOEX.%WO BAN5 100510 BANK 0
25 52 7550 75 10 BANK 6 1.25 50 75 100 BANK 7 ROD POSITION LIMITS FOR FOUR PUM!P OPERATION AFTER 200 - 10 EFPD UNIT 2
%DUE PO OCONEE NUCLEAR STATION Figure 3.5.2-2 (3 of 3)
Amendments Nos.129
, 129, & 126
300 (150,1023 POWER LEVEL
,~(012 (260.S01 80SHUTDOWN (2s0.30)
MAAGiN LIMIT RESTRICTED OPERATION
- 1.
UNACCEPTABLE O
~OPERATION00)20.)
0 ACCEEPTA8LE OPERATICN 20 (00,15 0Ica10 150 200 250 ROO INDEX.%WO 0
25 50 75 100 BANK 5 0
25 50 75 100 BANK 5 0
25 so 75 100 BANK 7 ROD POSITION LlylITS FOR FOUR-PUMPp OE,A-TTON
- Ro% 0 TO 25 +1O/-()F?
OCONEE NUCLEAR STATIONi Amendments Nos. 129
,129
,& 126 3.5-17 Figure 3.5.2-3 t2 of 3)1
100-(150. 1021 POW'c LEVEL f775.102)
CUTCF-00% Fp SH~UT OW'N LM RiT,
.j 80-(4,0 R ESTS ICT5D OPERATION UNACCEPTABLE S60-OPERATION CL (90,50)
(200.50) 0 Lu ACCEPTABLE 20 0
50 iCO
- a 20 5
200 ROO INDEX,%W0 0
25 50 75 100 SANKS5 0
25 so 75 100 SANK 6 0
25 5-0 75 100)
BANK 7 ROD POSITION LI2ITS FOR FOUR-PMip OPERPATIOUT FROM 25 +10/-0 TO 200 +10/-10 EFPD f UN IT 3 auwiOCONEE NUCLEAR STATION Figure 3.5.2-3 (2 of 3)
Amendments Nos. 1*29
,129,
& 126
POWER LEVEL cu 4-0
- 001% FpP (0022M.202)
_(275,102)(.0 so-
~REST IC71Ec OPERATION (4,C U N A CC'FT A BL OPERATION C6 J40o SHUTCOWNACCEPTABLE MARGIN OPE RTIC C LIM IT P
050 100 150 0
-s ROD INOEX.%WO a
25 so 75 100 BANK 5 0
25 50 75 100 BANK 6 25 50 75 100 BANK 7 ROD POSITION LIYITS FOR FOUR-PUJL~f O)pETIO~
AFTR 200 +10/-1(
FP UNIT 3 OUPwf CONEE NUCLEAR STATION Figure 3.5.2-3 (3 of 3 Amendments. Nos. 129
,129
,&126
100 I.
80 (204, 77)
(265.7,77)
SHUTDOWN MARGIN PERATION (300 cu LIMIT RESTRICTE 0
60 OPERATION NOT ALLOWED (200,50) 8 40 (139, 38) 20 OPERATION ACCEPTABLE 0 (0, 6. 1-)
0 0
100 200 300 Rod Index, % witnarawn GR 5 I
0 75 100 GR 61 AI O
25 75 100 GR 7 1 0
25 100 ROD POSITION LIMIITS FOR THREE-PUIP OPERATION' FROM 0 TO 26 +10/-0 EFPD UNIT 1 (U[a OCONEE NUCLEAR STATION Figure 3.5.2-4 (1 of 3)
Amendments Nos. 129
,129
, & 126 3.5-18
100 0
ida OPERATION RESTRICTED 7
80 OPERATION (238,77)
(259.4,77)
NGf ALLOWYED0 SN UT00N (300,77)
MARGIN 60 LIMIT (200,50) 40 0
(173,38)
OPERATION 20 ACCEPTABLE a (0,5.6) 0 I
100 200 300 Ro Inaex, o Witnarawn GR 5 1 0
75 100 GR 6 0
25 75 100 GR 7 1 I
0 25 100 ROD POSITION LIMITS FOR THREE-PUMP OPERATION FROM 26 +10/-0 TO 200 +/-10 EFPD UNIT 1 ouK(pun% OCONEE NUCLEAR STATION Figure 3.5.2-4 (2 of 3)
Amendments Nios. 129, 129
, & 126
00 OPERATION RESTRICTED 80 OPERATION (238.77) 259.4,77)
NOT ALLOWED SHUTD0WN (300,77)
MARGIN 60 LIMIT (200,50) 40 (173,.38)
OPERATION ACCEPTABLE 00 0 (0,5. 6) 0 100 200 300 Roa InOex, % Witnarawn GR 5 0
75 100 GR 6 t 25 75 100 GR 7 1
0 25 100 ROD POSITION LIMITS FOR THREE-PUMp OPERAT7ON AFTER 200 t10 EFPD UNIT I OCONEE NUCLEAR STATION Figure 3.5.2-4 (3 of 3)
Amendments Nos.
129,
129, & 126
100 80 (130,77)
(245,770 U.
.so UNACCEPTA8LE SOPERATION RESTRICTED 900so)
OPERATION (200,50) 0 LU SHUTDOWN ACCEPTABLE OPERATION 20 (30.15)
(90.15)
(0,10)
(0,5) 0 0
50 100 150 200 250 300 ROD INOEX.%WD 0
25 50 75 100 BANK 5 0
25 50 75 100 BANK 6 0
25 so 75 100 BANK7 ROD POSITION LIMITS FOR THREE PUMP. OPERATION FROM 0 TO 25 (+10, -0) EFD UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-5 (1 of 3)
Amendments Nos.
129, 129
, & 126 3.5-19
100 s0 (10,77)
(238,77)
(3CO.77)
UNACCEPTABLE OPERATION RESTRICTED (90,50)
OPERATION (200,50)
SHUTDOWN MAAGIN LIMIT ACCEPTA8LE OPERATION 20 (0,10)
(0,5) 0, O
50 100 150 200 250 ROD INOEX,%WO 0
25 50 75 100 BANKS 0
25 S
75 100 BANK 6 0
25 50 75 100 BANK7 ROD POSITION LIMITS FOR THREE PUMP OPERATION FROM 25 (+10, -0) TO 200 t10 EFPD UNIT 2 uxow OCONEE NUCLEAR STATION Figure 3.5.2-5 (2 of 3)
Amendments Nos. 129
, 129
, & 126
RESRICTSO
/OPER.AT! ON U.
- 0.
UNACCEPTABLE (0,0 o
OPERATION
~40 SHUTDOWN ACCSFTASLE MARGINCP.
0 0
50 100 150 20250 O
25ROO INOEX.%WO 0
25 0 75100 aANKS 0
25 50.*
75 100 BANK 6 0
25 50 7S 100 B3ANK 7 ROD POSITION L142-1TS FOR THREE PU~jp OPELRATION AFTER 200 +/-10 EFPD UN'liIT 2 OUXE Plwf OCONEE NUCLEAR STATiCN Figure 3.5.2-5 (3 of 3)
Amendments N~os. 129,129
,& 1 26
(1M. 77) 14.7 U.
Uj UNACCEPTABL-C oOPERATION R ER IC7,E C6OPERATION (20.50) 0 LU MARGIN ACCzVTA8LE LIMITOPERATION 0
010ISO 20C 250 ROO INOEX(.%WO 0
25 so 75 100 BANKS 5 25 50 75 100 BANKS6 0
25 50 75 10 BANK 7 ROD POSITION Ll.MITS FOR THREE PU'! OPERATIOlI FROM 0 TO 25 +10/-.o E L NIT 3 0ulwlOCONEE NUCLEAR S-TATIC.',
Figure 3.5.2-6 Amendments Nos.129 l 29 126 3.5-20 (1 of 3)
(IM17 (2.7 (0.
UNACCCPTASLE
~ 60 CPERAi1ON w
RESTRICTED o
OPERATION w
SHUTDOWN MARGIN LIMIT Acczp-rAaL-c.
OPERATION 20,1) 9.s (0.5) 0o 50ISO1 200 2sa ROD INCEX.%WO o
25 so 75 100 BANKS 0
25 Cc) 75 100 BANKS6 0
25 so 7S ic BANK 7 ROD POSITION LIMITS FOR
=H.E PUMP OPERATION FROM 25 +10/-0 TO 200 +10/-1O0FD
~
UNIT 3
- DUIEPaw I OCONEE NUCLEAR STATOj Figure 3.5.2-6 (2 -of 3)
Amendments Nos.
129, 129, 12 6
1001 OPERAIcN (210,771 C
(226.771 LA.
.(160.50)
UNACCEPTAaLE (205) c OPERATION LU SHUTOWN ACCETASLE MARGIN PERATION LJMIT 20 (90.15)
(0,C)*
0 50 100 150 200 250 ROD INOEX.%WO 0
25 50 7S 100 BANK 5 0
25 50 75 100 BANK6 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION AFTER 200 +10/-10 EFD UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-6 (3 of 3)
Amendments Nos. 129
, 129
, & 126
100 0
SOOPERATION NOT ALLOWED 60 SHUTDOWN MARGIN LIMIT (204.9,52)
(300,52) 40 20 J 139,26)
OPERATION ACCEPTABLE (0,4.8) 6,8 0
100 200 300 Roa Inaex, % Witnarawn GR 5 L 0
.75 100 GR 6 1
1 0
25 75 100 GR7 0
25 100 ROD POSITION LLMITS FOR TWO PUMP OPERATION FROM 0 TO 26 +10/-0 EFPD UNIT 1 0OWnaw OCONEE NUCLEAR STATION Figure 3.5.2-7 (1 of 3)
Amendments Nos. 129
- 129,
&126 3.5-21
100 80 OPERATION NOT ALLOWED 60 SHUTDOWN (238,52)
MARGIN
- O LIMIT (300,52) 40 OPERATION ACCEPTABLE
""0 (173,26)
(0,4.4) 0 0
100 200 300 Ro0
- Index, 51 Witnarawn GR 5 1 O
75 100 GR 6 1 I
0 25 75 100 GR 7
I1_
0 25 100 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 26 +10/-0 TO 200 t10 E??D UNIT 1 HEouawE OCONEE NUCLEAR STATION Figure 3.5.2-7 (2 of 3)
Amendments Nos. 129
, 129
, & 126
100 60 (2 8.2 SHUTOOWN (3.2 MARGIN
- C LIMIT (300,52) 40 OPERATION 6-ACCEPTABLE 20 (173,26)
(0,4.4)
( 1 B 60 0
100 200 300 R00 InOBX, SWitnorawin GR 5 1
I O
75 100 GR 651 1t 0
25 75 100 GR 7 I 0
25 100 ROD POSITION LIMITS FOR TWO PUMP OPERATON AFTER 200 010 EFPD UNIT 1 uanOCONEE NUCLEAR STATION Figure 3.5.2-7 (3 of 3)
Amendments Nos.
129 1209
& 126
100 80 (80.2)
(205.52)
(300,521
((200,50 c40 SHUITOOWN RS~cE MARGINOPEAATION LIMIT ACCtEPTA8L-E OPERATION 20 -UNACCEPTABLE OPERATION (90.15
.E (0.10)4 (0, 5) 050 100 150 200 250 M00 ROD INDEX,%WO 0
25 50 75 100 SANK 5 0
25 50 75 100 BANK 6 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 0 TO 25 (+10, -0) EFPD UNIT 2 a
11OWT OCONEE NUCLEAR STATION Figure 3.5.2-8 (1-of 3)
Amendments Nose 129
,129
,& 126 3.5-22
I0 100 80 u0 LU 805200.52)
Q.
40 SHIUTDOWN RESTRICTED MARGIN OPERATION ACCEPTABLE LIMIT OPERATION 20 UNACCEPTABLE OPERATION 50.15)
(90.15)
(0.10)
(0.5) 0 50 100 150 200 250 300 RCD INOEX.%WO 0
25 50 75 100 BANK S 0
25 50 75 100 BANK 6 0
25 50 75 100 BANK 7 ROD POSITION LIIMITS FOR TWO PUMP OPERATION FROi 25 (+10,-0) TO 200 -10 EF?D UNIT 2 v~own OCONEE NUCLEAR STATION Figure 3.5.2-8 (2 of 3)
Amendments Nos. 129
, 129
, & 126
100 80 0
RESTRICTED OPERATION S(170.52)
(203.52.52 UNACCEPTABLE OPERATION U 40 MAAGION.
ACCEPTABLE UMRI OPERATION LIMI 20 (100.15 0
0s 100 150 2
2500 0
25 50 75 10000 INOEX.%WO BANKS 0
25 50 75 1C0 BANK6 0
25 50 75 BANK 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION AFTER 200 tio EFD UNIT 2 nonwa OCONEE NUCLEAR STATION Figure 3.5.2-8 (3 of 3)
Amendments Nos.
129, 129, & 126
100 80
- a.
SHTDW
- 0.
)
a.)
ROOARGINW
- 0.
25 so010 0
AN 50 2
so 7
o 0AN 252 50 75 100 BANK 7 ROD POSIT:
LI-rTS FOR rrJO, PUTk OFE--:Zo:;
FROM 0 TO 25 +,10/-0oF?
UN IT 3 OCONEE NUCLEAR STATION Amendments Nos. 129 129
& 126 Figure 3.5.2-9 3.5-23
100 80 2
c C
a (200,.50) 4 0 SH OW RESTRICTED MARGIN OPERATION A CCt'FTASBLE UMIT OPERATION 20 UNACCEPTABLE OPERATION (0,10)<
- 0.
o 50 100 150 200 250 2
ROD INCEX.%WO 0
25 50 75 100 BANK 5 0
25 50 75 100 SANK 6 0
25 SO 75 100 BANK 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 25 +10/-0 TO 200 +10/-10 EFPt IMIT 3 ounn OCONEE NUCLEAR STATION
- Figure 3.5.2-9 (2 of 3)
Amendments Nos.
129,129
, & 126
100 U.
RESTRIC7"C0 A60 OPERATION (170.5521 C
UNACCFTAaL!c(0,0 o
OPFATlON
'4c SH4UTDOWN ACPA~
MARGINOPRTN LIMIT 0001s o
50 100 150 71M 2CC ROD INDEX.%Wo a
25 50 75 100 BANKC a
0 25 50 75 100 UBANK 6 0
25 so 75 10a BANK 7 ROD POSITION L12IT FOR TWO PUMP OPERATION AFTER 200 +10/-10 EFPD UNIT 3
- Out~wt~OCONEE NUCLEAR STATION Figure 3.5.2-9 (3 of 3)
Amendments Nos.
129 129 *& 126
- i
(-12, 102)
(20, 102)
(-17.4, 92) 1 90 (25,92)
(-24.8,80) 80 (30,80)
OPERATION 70 ACCEPTABLE 60 50 040 30 20 10
-40
-30
-20
-10 0
10 20 30 40 Axial Power Imoalance, %
OPERATIONAL POWER IMBALANCE ENVELOPE FROM 0 TO 26 +10/-0 EFpD UNIT 1 NoUXomE OCONEE NUCLEAR STATION Figure 3.5.2-10 (1 of 3)
Amendments Nos. 129
,129
, &126 3.24
17, 1021-(20, 102)
(-26.86,92)(3
,2
(-31,80) 80(35,80)
C 070 OPERATION ACCEPTABLE 60
--50 40 6
- 30 20 10
-40
-30
-20
-10 0
10 20 30 40 Axial Power Imoalance, %
OPERATIONAL POW ER LLBALANCE ENVELOPE FROM 26 +10/-0 TO 200 110 EFPD UNIT 1 1
OUwF OCONEE NUCLEAR STATION Figure 3.5.2-10 (2 of 3)
Amendments Nos. 129
, 129
, &126
OPERATION RESTRICTED
(-19,102)
(20. 102)
-*100
(-29,92) 30 C2 (3
92
(-31,80) 80 (35,80) 0 70 OPERATION ACCEPTABLE 60 0
20 10
-40
-30
-20
-10 0
10 20 30 40 Axial Power Imbalance, f OPERATIONAL POWER LMBALANCE ENVELOPE AFTER 200 +/-10 EFPD UNIT 1 noUsEER OCONEE NUCLEAR STATION Figure 3.5.2-10 (3 of 3)
Amendments Nos. 129, 129, & 126
REACTOR POWER,%FP
(-18.2, 102.0)
(25.0,102.0) 100
(-27.3, 90.0)
ACCEPjABLE (30.0,90.0)
OPERATION
(-32.2, 80.0) s8 60 RESTRICTED OPERATION RESTRICTED OPERATION 40 20
-100
-80
-60
-40
-20 0
20 40 60 80 100 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE FROM 0 TO 25 (+10,
-0)
EFD UNIT 2
'01 uowj OCONEE NUCLEAR STATION Figure 3.5.2-11 (1 of 2)
Amendments Nos.
129
, 129
, & 126 3.5-25
REACTOR POWER,%FP
(-30.0, 102.0)
(25.0,102.0)
(-35.0,90.0) F ACCE ABLE OPERATION (30.0,90.0) 80 60 RESTRICTED OPERATION RESTRICTED OPERATION
-40 20
-100
-80
-60
-40
-20 0
20 40 60 80 100 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE AFTER 25 (+10,. -0)
EFPD UNIT 2 UEnMIR OCONEE NUCLEAR STATION Figure 3.5.2-11 (2 of 2)
Amendments Nos. 129
,129
, & 126
REACTOR POWER,%FP
(-16.5, 102.0)
-100 (25.0,102.0)
(-25.7, 90.0)
ACCE TABLE s(30.0,90.0)
OPERATION
(-28.2, 80.0) 80 60 RESTRICTED OPERATION RESTRICTED OPERATION 40 20
-100
-80
-60
-40
-20 0
20 40 60 80 100 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE FROM 0 TO 200 +10/-10 EFPD UNIT 3 ounw OCONEE NUCLEAR STATION Figure 3.5.2-12 (1 of 2)
Amendments Nos. 129
,129
, &126 3.5-26
REACTOR POWER,%FP
(-30.0, 102.0)
(25.0,102.0) 100 ACCE? ABLE
-)
OPER TION 80 60 RESTRICTED OPERATION RESTRICTED OPERATION 40
- 20
-100
-80
-60
-40
-20 0
20 40 80 80 ic0 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE AFTER 200 +10/-10 EF?D UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-12 (2 of 2)
Amendments Nos.
129 129, &12G
110 00 (10, 102)
(33, 102) 100 (10,902)
(34, 92) 900 80 (0,80)
(38,80)
OPERATION RESTRICTED 70 60 50 40 OPERATION ACCEPTABLE 30 20 10 0
10 20 30 40 50-60 70 80 90 100 APSR Position, % witnarawn APSR POSITION LIMITS FOR OPERATION FROM 0 TO 26 +10/-0 EFPD UNIT 1
<u Fpowi OCONEE NUCLEAR STATION Figure 3.5.2-13 (1 of 3)
Amendments Nos. 129
, 129
& 126 7
3.5-27
(10, 102)
(34,102) 90 10,92)
(38,92)
OPERATION RESTRICTED 80 (
(0,80)
(38.5,80) 70 60 OPERATION 50.ACCEPTABLE (100,50) 40 30 30 20 0
10 20 30 40 50 60 70 80 90 100 APSR Position, 7 Witnarawn APSR POSITION LIMITS FOR OPERATION FROM 26 +101-0 TO 200 t1O EFPD UNIT 1 OCONEE NUCLEAR STATION Figure 3.5.2-13 (2 of 3)
Amendments Nos.129
,129
., &126
- 10. 102)
(3.102)
I00 90 (38,92)
OPERATION RESTRICTED
( (0, 80).
(3.580 T
80 70 60 OPERATION 50.ACCEPTABLE 40 2
30 20 10 0
t 0
10 20 30 40 50 60 70 80 90 100 APSR Position, a Wftnarawn APSR POSITION LIMITS FOR OPERATION AFTER 200 10 EFPD TNIT 1 OCONEE NUCLEAR STATION Figure 3.5.2-13 (3 of 3)
Amendments Nos. 129 129, &12G
(9.1, 102) 100 (40.102)
(9.1,90) 80 (9.1, 80)
(40.80) 1(0,70)
RESTRICTED OPERATION L
0 (60.60)
<40 -
ACCEPTA8LE OPERATION (100,40)
U 20 0
20 40 60 s0 100 APSR POSITION,%WD APSR POSITION LIMITS FOR OPERATION FROM 0 EFPD TO EOC UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-14 (1 of 1)
Amendment Nos.
129
, 129
, & 12G 3.5-28
(4.0.102) 100-(40,102)
(4.0.90) 80-(4.0,80)
(40.80)
(0,70)
RESTRICTED OPERATION
- 40. ACCEPTABLE OPERATION U
S60-6.0 0
CL 0
CL 0
20 40 60 80 100 APSR POSITION.
WO APSR POSITION LIMITS FOR OPERATION FROM 0 TO 200 +10/-10 EFPD UNIT 3 fonuXE OCONEE NUCLEAR STATION Figure 3.5.2-15 (I of 2)
Amendments Nos.129,129
, & 126 3529
(10.0. 102)-
(40,102) 410.0. 90) 80 f 10.0, 80)
(40,80)
RESTRICTED OPERATION 6 0.70)
CL
- a.
3
< 40-ACCEPTA8LE OPERATION L"
(100,40) 20 0
20 40 6080 100 APSR POSITION,%WO APSR POSITION LIMITS FOR OPERATION AFTER 200 +10/-10 EFPD UNIT 3 ouXEy OCONEE NUCLEAR STATION Figure 3.5.2-15 (2 of 2)
Amendments Nos. 129
, 129
, & 126
2C 18 16 0000 0
14 Generic FAC BAW-10103 z
12 0
2 4
'6 8
10 12 Axial Location of Peak Power From Bottom of Core, ft LOCA-LI4ITED MAXIMUM ALLOUABL LINEAR HEAT nuou~
OCONEE NUCLEAR STATION Figure 3.5.2-16 J
Amendments Nos.
129,129
, & 126 3.5-30
3.5.3 Engineered Safety Features Protective System Actuation Setpoints Applicability This specification applies to the engineered safety features protective system actuation setpoints.
Objective To provide for automatic initiation of the engineered safety features protective system in the event of a breach of RCS integrity.
Specification The engineered safety features protective actuation setpoints and permissible bypasses shall be as follows:
Functional Unit Action Setpoint High Reactor Building Reactor Building Spray
!30 psig Pressure High-Pressure Injection SA psig Low-Pressure Injection psig Start Reactor Building Cooling & Reactor Building Isolation (Essential and Non-G4 psig essential Systems)
Penetration Room Ventilation
!4 psig (1)
Lower Reactor Coolant High Pressure Injection
=1500 psig System Pressure
& Reactor Building Isolation (Non-essential systems)
(2)
Low Pressure Injection
_=500 psig (1) May be bypassed below 1750 psig and is automatically reinstated aboved 1750 psig.
(2) May be bypassed below 900 psig and is automatically reinstated above 900 psig.
Bases High Reactor Building Pressure The basis for the 30 psig and 4 psig setpoints for the high pressure signal is to establish a setting which would be reached immediately in the event of a DBA, cover the entire spectrum of break sizes and yet be far enough above normal operation maximum internal pressure to prevent spurious initiation.
Low Reactor Coolant System Pressure The basis for the 1500 psig low reactor coolant pressure setpoint for high pressure injection initiation and 500 psig for low pressure injection is to Amendments Nos.
129,129
, & 126 3.5-31
establish a value which is high enough such that protection is provided for the entire spectrum of break sizes and is far enough below normal operating pressure to prevent spurious initiation.(1)
REFERENCE (1) FSAR, Section 15.14.
Amendments Nos. 129,129
, & 126 3.5-32
3.5.4 Incore Instrumentation Applicabilitv Applies to the operability of the incore instrumentation system.
Objective To specify the functional and operational requirements of the incore instru mentation system.
Soecification 3.5.4.1 At or above 80 percent of the power allowable for the existing reactor coolant pump operating combination, incore detectors shall be operable as necessary to meet the following:
- a.
For axial imbalance measurements:
At least three detectors in each of at least three strings shall lie in the same axial plane, with one plane in each axial core half. The axial planes in each core half shall be symmetrical about the core mid-plane. The detector strings shall not have radial symmetry.
- b.
For quadrant power tilt measurements:
At least two sets of at least four detectors shall lie in each axial core half. Each set of detectors shall lie in the same axial plane. The two sets in the same core half may lie in the same axial plane. Detectors in the same plane shall have quarter core radial symmetry.
3.5.4.2 If requirements of 3.5.4.1 are not met, power shall be reduced below 80 percent of the power allowable for the existing reactor coolant pump combination within eight hours and incore detector measurements shall not be used to determine axial imbalance or quadrant power tilt.
Bases The operability of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. See Figures 3.5.4-1, 3.5.4-2, and 3.5.4-3 for satisfactory incore detector arrangements.
The safety of reactor operation at or beoy 80 percent of the power allowable for the reactor coolant pump combination 1 without the axial imbalance trip system has been determined by extensive 3-D calculations, and was verified during the physics startup testing program.
(1) FSAR, Section 5.1.2.3 Amendments Nos.
129,129
& 126 3.5-33
Lack radial sy~etry Axial Plane N
Top Axial rare Half Bottom Axial Core Half iNCORE INSTRUMENTATION SPECI FICAT ION AXIAL IMBALANCE INOICATION
~ICCREL I:STRLUMZ:-A-. Cu
~o~~~OCONEE NUCLEAR STATION Amendments Nos. 129 *129
&126 35-34 Figure 3.5.4-1
Radial Radial Symmetry in this plane 110 C,
Radial Symmetry in this plane INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TitT INDICATION INCORE INSTRULMENTATI'ON SPECIFICATION RADIAL FLUX TILT INDICATION, OCONEE NUCLEAR STATION Amendments Nos. 129, 129
& 126 Figure 3.5.4-2 3.5-35
(.1' 6U U)
INCORE INSTRUMENTA.TION SPEC IFICATION I:;CORE INS T'RJY!El.TAZ 10',
~ SPEC:FICATION Amenmens No 12 129 & 16 3.-36OCONEE NUCLEAR STATION Amenmens Ns. 19,29 & 16 35-3 Figure 3.5.4-3
3.5.5 Radioactive Effluent Monitoring Instrumentation Applicability Applies to radioactive liquid effluent, gaseous effluent, and gaseous process monitoring instrumentation.
Specifications 3.5.5.1 Liquid Effluents
- a.
The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.5.5-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of Speci fication 3.9.1 are not exceeded.
- b.
If a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint is less conservative than required, without delay suspend the release of radioactive liquid ef fluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- c.
In the event that the number of operable radioactive liquid effluent monitoring instrumentation channels falls below the limit given under Table 3.5.5-1, Column A, action shall be as shown in Column B. Exert best efforts to return the instru ments to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
3.5.5.2 Gaseous Process and Effluents
- a.
The radioactive gaseous process and effluent monitoring instru mentation channels shown in Table 3.5.5-2 shall be operable with their alarm/trip setpoints set to ensure that the limits of Specification 3.10.1 are not exceeded.
- b.
If a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint is less conservative than required, without delay suspend the release of radioactive gaseous ef fluents monitored by the affected channel or declare the chan nel inoperable, or change the setpoint so it is acceptably conservative.
C.
In the event that the number of radioactive gaseous process or effluent monitoring instrumentation channels falls below the limit given under Table 3.5.5-2, Column A, action shall be taken as shown in Column B. Exert best efforts to return the instruments to operable status within 30 days and, if unsuc cessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
Amendments Nos. 129, 129, & 126 3.5-37
3.5.5.3 Setpoints The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded. Setpoint correction may be permitted with out declaring the channel inoperable.
3.5.5.4 The provisions of Technical Specification 3.0 do not apply.
Bases The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.
The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases.
The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring (and controlling) the concentration of potentially explosive gas mixtures in the waste gas holdup system. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
Amendments Nos. 129 129
& 126 3.5-38
Table 3.5.5-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS A
B INSTRUMENT MINIMUM OPERATOR ACTION IF OPERABLE MINIMUM NUMBER OF CHANNELS APPLICABILITY OPERABLE CHANNELS IS NOT MET
- 1.
Monitors Providing Automatic Termina tion of Release Liquid Radwaste Efflu ent Line Monitors 1 RIA-33 1
(a)
Turbine Building Sump 1 RIA-54 (Units 1 & 2) 1(b) 3 RIA-54 (Unit 3) 1(b)
- 2.
Monitors not Providing Automatic Termination of Release Low Pressure Service Water 1 RIA-35 1
(d) 2 RIA-35 1
(d) 3 RIA-35 1
(d)
- 3.
Flow Rate Measuring Devices Liquid Radwaste Effluent Line 1
(c)
Keowee Hydroelectric Station Tailrace Dis charge
- NA NA NA
- 4.
Continuous Composite Sampler
- 3 Chemical Treat ment Pond Composite Sampler and Sampler Flow Monitor (Turbine Building Sumps Effluent) 1 (d)
- At all times.
"'Flow determined from number of hydro units operating; if hydro is not operating, leakage flow, which is measured periodically, is used.
Amendments Nos.
129,129
, & 126
Table 3.5.5-1 NOTES (a) Effluent releases may continue provided that prior to initiating a release:
- 1.
Two independent samples are analyzed in accordance with Specification 3.9 and;
- 2.
Two independent data entry checks for release rate calculations and valve lineups of the effluent pathway are conducted.
Otherwise, suspend release of radioactive effluents by this pathway.
(b) Effluent releases may continue provided that prior to each discrete release of the sump, grab samples are collected and analyzed for gross radioactivity (beta and/or gamma) at a lower limit of de tection of at least 10 7 pCi/ml.
(c) Effluent releases may continue provided flow rate is estimated at least once per four hours during actual releases.
(d) Effluent releases may continue provided that grab samples are collected and analyzed for gross radioactivity (beta and/or gamma) at a lower limit of detection of at least 1 pCi/ml every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Amendments Nos. 129,129
, & 126 3.5-40
Table 3.5.5-2 GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS A
B INSTRUMENT MINIMtUM OPERATOR ACTION IF OPERABLE MINIMUM NUNBER OF CHANNELS APPLICABILITY OPERABLE CHA1NTELS IS (PER NOT MET RELEASE PATH)
- 1.
Waste Gas Holdup Tanks
- a.
Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination Of Release (RIA-37, -
- 38) 1 (a)
- b.
Effluent Flow Rate Monitor (Waste Gas 1
(b)
Discharge Flow)
- 2.
Unit Vent Monitoring System
- a.
Noble Gas Activity Monitor Providing Alarm and Automatic Termination of Con tainment Purge Re lease (RIA - 45) 1 (a)
- b.
Iodine Sampler 1
(d)
C.
Particulate Sampler 1
(d)
- d.
Effluent Flow Rate Monitor (Unit Vent.
1 (b)
Flow)
- e.
Sampler Flow Rate Monitor 1
(e)
- f.
Effluent Flow Rate Monitor (Containment Purge) 1 (b)
- 3.
Interim Radwaste Building Ventilation Monitoring System
- a.
Noble Gas Activity Monitor (RIA -
- 53) 1 (c)
- b.
Iodine Sampler#
1 (d)
- c.
Particulate Sampler# 1 (d)
Amendments Nos. 129,129
, & 126 3.5-41
Table 3.5.5-2 (Cont'd)
GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS A
B INSTRUENT MINIMUM OPERATOR ACTION IF OPERABLE MINIMUM NLjiBER OF CHANNELS APPLICABILITY OPERABLE CHANNELS IS (PER NOT MET RELEASE PATH)
- d.
Effluent Flow Rate Monitor (Interim 1(b)
Radwaste Exhaust)#
- e.
Sampler Flow Rate Monitor#
1(e)
- 4.
Hot Machine Shop Ventilation Monitoring System
- a.
Iodine Sampler#
1 (d)
- b.
Particulate Sampler# 1(d)
- c.
Effluent Flow Rate Monitor (Hot Machine 1(b)
Shop Exhaust)#
- d.
Sampler Flow Rate Monitor#
1 (e)
At all times.
During waste gas holdup tank releases and/or containment purge operation.
Effective upon installation of equipment.
Amendments Nos. 129
, 129, & 126 3.5-42
Table 3.5.5-2 NOTES (a) Effluent releases from waste gas tanks or containment purges may con tinue provided that prior to initiating a release:
- 1.
Two independent samples are analyzed and;
- 2.
Two independent data entry checks for release rate calculations and valve lineups of the effluent pathway are conducted and; Effluent release from ventilation system or condenser air ejectors may continue provided that grab samples are taken once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross actiyvity (beta and/or gamma) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or continuously monitor through the unit vent. Otherwise, suspend release of radioactive effluents Via this pathway.
(b) Effluent releases may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(c) Effluent releases may continue provided grab samples are taken once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity (beta and/or gamma) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(d) Effluent releases may continue provided samples are continuously col lected with auxiliary sampling equipment for periods not to exceed 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the end of sample collection.
(e) Alarms indicating low flow may be substituted for flow measuring devices.
Amendments Nos. 129
, 129
, & 126 3.5-43