ML15113A068
| ML15113A068 | |
| Person / Time | |
|---|---|
| Site: | Oconee  (DPR-038, DPR-047, DPR-055) |
| Issue date: | 11/23/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A071 | List: |
| References | |
| DPR-38-A-124, DPR-47-A-124, DPR-55-A-121 NUDOCS 8312070338 | |
| Download: ML15113A068 (36) | |
Text
1s 0UNITED STATES NA EAR REGULATORY COMMISSIO WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 124 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 September 1, 1983, as supplemented September 14, 1983, 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 3.8 of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 124are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8312070338 831123 PDR ADOCK 05000269 PPDR
4'e
.0 0
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J n F. Stolz, Chi O eratina Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 23, 1983
UNITED STATES NL1LEAR REGULATORY COMMISSIO WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.124 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated September 1, 1983, as supplemented September 14, 1983, 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 3.8 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.124 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo F. Stolz, Chief Op rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 23, 1983
SEUNITED STATES M NOLEAR REGULATORY COMMISSIOP WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO.3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 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 September 1, 1983, as supplemented September 14, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 121 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 COIMMISSION J n F. Stolz, Chief 0 erating Reactors B ch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 23, 1983
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 124 TO DPR-38 AMENDMENT NO.
124TO DPR-47 AMENDMENT NO. 121 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 viii viii ix ix X
x 2.1-3b 2.1-36 2.1-5 2.1-5 2.1-8 2.1-8 2.1-11 2.1-11 2.3-2 2.3-2 2.3-3 2.3-3 2.3-9 2.3-9 2.3-11 2.3-11 2.3-12 2.3-12 2.3-13 2.3-13 3.5-9 3.5-9 3.5-10 3.5-10 3.5-11 3.5-11 3.5-16 3.5-16 3.5-16a 3.5-16a 3.5-16b 3.5-16b 3.5-19 3.5-19 3.5-19a 3.5-19a 3.5-19b 3.5-19b 3.5-19c 3.5-19c 3.5-19d 3.5-19d 3.5-19e 3.5-19e 3.5-22 3.5-22 3.5-22a 3.5-22a 3.5-22b Deleted 3.5-25
.325 3.5-25a Deleted 3.5-25b Deleted
LIST OF FIGURES (CONT'D)
Fiure page 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 H20 3.5.2-lAl Rod Position Limits for Four Pump Operation -
Unit 1 3.5-15 3.5.2-lA2 Rod Position Limits for Four Pump Operation -
Unit 1 3.5-13a 3.5.2-1A3 Rod Position Limits for Four Pump Operation -
Unit 1 3.5-15b 3.5.2-IBI Rod Position Limits for Four Pump Operation -
Unit 2 3.5-16 3.5.2-1B2 Rod Position Limits for Four Pump Operation -
Unit 2 3.5-16a 3.5.2-1B3 Rod Position Limits for Four Pump Operation -
Unit 2 3.5-16b 3.5.2-1i1 Rod Position Limits for Four Pump Operation -
Unit 3 3.5-17 3.5.2-1C2 Rod Position Limits for Four Pump Operation -
Unit 3 3.5-17a 3.5.2-1C3 Rod Position Limits for Four Pump Operation - Unit 3 3.5-17b 3.5.2-2A1 Rod Position Limits for 3 Pump Operation - Unit 1 3.5-18 3.5.2-2A2 Rod Position Limits for 3 Pump Operation - Unit 1 3.5-18a 3.5.2-2A3 Rod Position Limits for 3 Pump Operation - Unit 1 3.5-18b 3.5.2-2A4 Rod Position Limits for 2 Pump Operation - Unit 1 3.5-18c 3.5.2-2A5 Rod Position Limits for 2 Pump Operation - Unit 1 3.5-18d 3.5.2-2A6 Rod Position Limits for 2 Pump Operation - Unit 1 3.5-18e 3.5.2-2B1 Rod Position Limits for 3 Pump Operation - Unit 2 3.5-19 3.5.2-2B2 Rod Position Limits for 3 Pump Operation -
Unit 2 3.5-19a 3.5.2-2B3 Rod Position Limits for 3 Pump Operation - Unit 2 3.5-19b 3.5.2-2B4 Rod Position Limits for 2 Pump Operation - Unit 2 3.5-19c 3.5.2-2B5 Rod Position Limits for 2 Pump Operation - Unit 2 3.5-19d 3.5.2-2B6 Rod Position Limits for 2 Pump Operation - Unit 2 3.5-19e 3.5.2-2C1 Rod Position Limits for 3 Pump Operation - Unit 3 3.5-20
LIST OF FIGURES (CONT'D)
Figure Page 3.5.2-2C2 Rod Position Limits for 3 Pump Operation -
Unit 3 3.5-20a 3.5.2-2C3 Rod Position Limits for 3 Pump Operation - Unit 3 3.5-20b 3.5.2-2C4 Rod Position Limits for 2 Pump Operation -
Unit 3 3.5-20c 3.5.2-2C5 Rod Position Limits for 2 Pump Operation -
Unit 3 3.5-20d 3.5.2-2C6 Rod Position Limits for 2 Pump Operation -
Unit 3 3.5-20e 3.5.2-3Al Operational Power Imbalance Envelope - Unit 1 3.5-21 3.5.2-3A2 Operational Power Imbalance Envelope - Unit 1 3.5-21a 3.5.2-3A3 Operational Power Imbalance Envelope -
Unit 1 3.5-21b 3.5.2-3B1 Operational Power Imbalance Envelope -
Unit 2 3.5-22 3.5.2-3B2 Operational Power Imbalance Envelope - Unit 2 3.5-22a 3.5.2-3C1 Operational Power Imbalance Envelope - Unit 3 3.5-23 3.5.2-3C2 Operational Power Imbalance Envelope - Unit 3 3.5-23a 3.5.2-3C3 Operational Power Imbalance Envelope - Unit 3 3.5-23b 3.5.2-4Al APSR Position Limits - Unit 1 3.5-24 3.5.2-4A2 APSR Position Limits - Unit 1 3.5-24a 3.5.2-4A3 APSR Position Limits -
Unit 1 3.5-24b 3.5.2-4B1 APSR Position Limits -
Unit 2 3.5-25 3.5.2-4C1 APSR Position Limits -
Unit 3 3.5-26 3.5.2-4C2 APSR Position Limits - Unit 3 3.5-26a 3.5.2-4C3 APSR Position Limits - Unit 3 3.5-26b 3.5.2-5 LOCA - Limited Maximum Allowable Linear Heat 3.5-27 3.5.4-1 Incore Instrumentation Specification Axial Imbalance 3.5-31 Indication 3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt 3.5-32 Indication 3.5.4-3 Incore Instrumentation Specification 3.5-33 4.5.1-1 High Pressure Injection Pump Characteristics 4.5-4 4.5.1-2 Low Pressure Injection Pump Characteristics 4.5-5 Amendments Nos. 124
, 124,
& 121 ix
LIST OF FIGURES (CONT'D)
Figure Page 4.5.2-1 Acceptance Curve for 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.
124
, 124 121 x
INTRODUCTION These Technical Specifications apply to the Oconee Nuclear Station, Units 1, 2, and 3 and are in accordance with the requirements of 1nCiR5, Section 50.36.
The bases, which provide technical support or reference the pertinent FSAR section for technical support of the individual specificationsiare included for informational purposes and to clarify the intent of the specification.
These bases are not part of the Technical Specifications, and they do not constitute limitations or requirements for the licensee. The Technical Specifications while applying to Units 1, 2, and 3 are written on a single unit basis; exceptions to this are identified.
AmendmentsNos.
124, 124, &
121 x.
- 1.
The 1.30 DNBR limit produced by the combination of the radial peak,.axial peak and position of the axial peak that yields no less than a 1.30 DNBR.
- 2.
The combination of radial and axial peak that causes central fuel melting at the hot spot.
The limit is 20.4 kw/ft for fuel rod burnup less than or equal to 10,000 MWD/MTU and 21.2 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 2.1-3B correspond to the expected minimum flow rates with four pumps, three pumps, and one pump in each loop, respectively.
The curve of Figure 2.1-1B is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3B.
The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup dependent 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. All plant operating limits are based on a minimum DNBR criteria of 1.30 plus the amount necessary to offset the reduction in DNBR due to fuel rod bow. (3)
The maximum thermal power for three-pump operation is 88.07 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.07 =
79.92 percent power plus the maximum calibration and instrument error. The maximum thermal power for other coolant pump conditions is produced in a similar manner.
For each curve of Figure 2.1-3B, 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 2.1-1B is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3B.
References (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurizer Water, BAW-10000, March 1970.
(2) Oconee 2, Cycle 4 - Reload Report, BAW-1491, August 1978.
(3) Oconee 2, Cycle 7 - Reload Report, DPC-RD-2002, September 1983.
Amendments Nos.
124,124
, & 121 2.1-3b
2400 ACCEPTABLE OPERAT ON 2200 UNACC PTABLE OPERATION 160U 580 600 620 640 660 Reactor Coolant Core Outlet Temperature, 0 F CORE PROTECTION SAFETY LIMITS UNIT 2 OCONEE NUCLEAR STATION Figure 2.1-1B Amendments Nos. 124 124, & 121 2.1-3
THERMAL POWER LEVEL, % FP
-120
(-32.4, 112.0)
(32.4, 112.0)
M1= 0.70 M2=-0.70 ACCEPTABLE
(-49.5,100.0) 4PUMP
-100 (49.5, 100.0)
OPE RATION
(-32.4 88.07)
(32.4, 88.07)
ACCEPTABLE
-80
(-49.5, 76.07) j 3 & 4 PUMP (49.5, 76.07)
OPERATION uI
(-32.4 60.63)
-0(32.4,60.63)
ACCEPTABLE
(-49.5, 48.63) 2, 3 & 4 PUMP (49.5, 48.63)
OPE RATION
-40 II II 2
I I
I I
II
-60
-40
-20 20 40 60 REACTOR POWER IMBALANCE CORE PROTECTION SAFETY LIMITS UNIT 2 onnnOCONEE NUCLEAR STATION Amendments Nos.124 124, & 121 2.1-8 D
OL Fioure 2-1-2R
2400 ACCEPTABLE
/
OPERATION
/
2200 4 PUMPN 2000 2 PUMP 3PUMP
/
1800 UNACC PTABLE OPERA lON 1600 580 600 620 640 660 Reacor Coolant Core Outlet Temperature, OF PUMPS COOLANT POWER TYPE OF LIMIT OPERATING FLOW (GPM)
(% FP) 4 374,880(100%)
112.0 DNBR 3
280,035(74.7%)
90.7 DNBR 2
183,690(49.0%)
63.63 DNBR/QUALITY CORE PROTECTION SAFETY LIMITS UNIT 2 OCONEE NUCLEAR STATION Figure 2.1-3B Amendments Nos. 124, 124, & 121 2.1-11
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 Flow 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 maximum 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 2.3-1A 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 units 1 and 3, the maximum calibration and instrument errors are algebraically summed to determine the string errors in the safety calculations. Unit 2 employs 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 DNER 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. 124,
124, & 121 2.3-2
level trip and associated reactor power/reactor power-imbalance boundaries by 1.07% - Unit 1 for 1% flow reduction.
1.07% - Unit 2 1.08% - Unit 3 Pump Monitors The pump monitors prevent the minimum core DNBR from decreasing below 1.3 by tripping the reactor due to the loss of reactor coolant pump(s).
The circuitry monitoring pump operational status provides redundant trip protection for DNB by tripping the reactor on a signal diverse from that of the power-to-flow ratio. The pump monitors also restrict the power level for the number of pumps in operation.
Reactor Coolant System Pressure During a startup accident from low power or a slow rod withdrawal from high power, the system high pressure setpoint is reached before the nuclear over power trip setpoint. The trip setting limit shown in Figure 2.3-1A -
Unit 1 2.3-1B - Unit 2 2.3 Unit 3 for high reactor coolant system pressure (2300 psig) has been established to maintain the system pressure below the safety limit (2750 psig) for any design transient. (1)
The low pressure (1800) psig and variable low pressure (11.14 T
-4706) trip (1800) psig (11.14 Tout-4706)
(1800) psig (11.14 Tout-4706) out setpoints shown in Figure 2.3-1A have been established to maintain the DNB 2.3-1B 2.3-IC ratio greater than or equal to 1.3 for those design accidents that result in a pressure reduction.
(2,3)
Due to the calibration and instrumentation errors the safety analysis used a variable low reactor coolant system pressure trip value of (11.14 T
- 4746) out (11.14 Tout - 4746) out (11.14 Tou 4746)
Coolant Outlet Temperature The high reactor coolant outlet temperature trip setting limit (618 0F) shown in Figure 2.3-lA has been established to prevent excessive core coolant 2.3-1B 2.3-10 temperatures in the operating range.
Due to calibration and instrumentation errors, the safety analysis used a trip setpoint of 6200F.
Reactor Building Pressure The high reactor building pressure trip setting limit (4 psig) provides positive assurance that a reactor trip will occur in the unlikely event of a loss-of coolant accident, even in the absence of a low reactor coolant system pressure trip.
2.3-3 Amendments Nos. 124, 124, &
121
THERMAL POWER LEVEL,% FP
(-17.0. 107.0)
(17.0,107.0)
M = 0.944 M2=-0.944 ACCEPTAB -E 4 PUMP OPEF ATION 100
(-35.0, 90.0)
(35.0, 90.0)
-17.0 79.9)
(17.0, 79.9)
ACCEPTAB E 3 & 4 PUMP OPEF ATION
(-35.0, (35.0, 62.9)
-60
(-17.0152.4)
(17.0,52.4)
ACCEPTA8.E 2,3, & 4 PUMP OPEF ATION
-40
(-35.0,j 354 (35.0, 35.4)
I I
-20 II
-60
-40
-20 20 40 60 REACTOR POWER IMBALANCE, %
PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS UNIT 2 OCONEE NUCLEAR STATION Amendments Nos. 124,
124 & 121 2.3-9 Figure 2.3-2B
t5 I~~vactor Protectave Ss teun Tk p s1*1 intg I.1nats t
One Reactor 0
Four Realtor Thete Heactor Coulant Pulgaip.
Coolant Puilps Coolant Puemp s Operating in Operating Operat inlg Each Loop (Operat ing Power (Operating Power (Operating Power Shutdown
!!5.ci)ieu
-100% Ratede
-49% Rated)
BY s I.
Nu lear Power Max.
105.5 105.5 105.5 5.0(3)
N)
(% Rated)
- 2.
Nuclear Power Max. Based 1.07 times flow 1.07 Limes flow 1.07 times flow Bypassed on Flow (2) and Imbalance, minus reduction minus reduction minus reduction
(% Rated) due to imbalance due to imbalance due to imbalance
- 3.
Nuclear Power Hax. Based NA NA 55%
Bypassed on Pump Monitors,
(% Rated)
- 4.
High Reactor Coolant 2300 2300 2300 1720(4)
System Pressure, pasig, Hax.
- 5.
Low Reactor Coolant 1800 1800 1800 Bypassed System Pressure, psig, Min.
- 6.
Variable Low Reactor (11.14 T 4706)(1)
(11.14 T 4706)
(11.14 Tu 4106)
Bypassed Coolant System Pressure ou out out psig, Minl.
- 7.
Reactor Coolant Temp. F., Hax.
618 618 618 618
- 8.
High Reactor Building 4
4 4
4 Pressure, psig, flax.
(1) lout is in degrees Fahrenheit (oF).
(2)
Reactor Coolant System Flow, %.
(3) Administratively controlled reduction set only during reactor shutdown.
(4)
Automatically set when other segments of the RPS are bypassed.
'fable 2.i-Ill (D
IlUni t 2 Heaictor
'rutective System Trip Settinjg Limts (D
One heactor Foura-Heactor Three Reactor Coolant Pump Coulant Pumps Coolant Pumps Operating in Operat ing Operating Each Loop (Operating Power (Operating Power (Operating Power Shutdown Uhs Segmlient
-100% Rated)
-75% Rated)
-49% Rated)
Bypass
- 1.
Nuclear Power Hax.
105.5 105.5 105.5 5.0
(% Rated)
- 2.
Nuclear Power Max. Based 1.07 Limes flow 1.07 times flow 1.07 times flow Bypassed on Flow (2) and Imbalance, minus reduction minus reduction minus reduction
(% Rated) due to imbalance due to imbalance due to imbalance
- 3.
Nuclear Power Max. Based NA NA 551 Bypassed o
Pump Monitors, (% Rated)
- 4.
High Reactor Coolant System 2300 2300 2300 1720 (4 Pressure, psig, Hax.
S.
Low Reactor Coolant System 1800 1800 1800 Bypassed Pressure, psig, Hin.
6..
Variable Low Reactor Coolant (11.14 T 4706)(1)
(11.14 T 4706)(1)
(11.14 T
- 4706)(1 Bypassed System Pressure psig, Hin.
out out out
- 7.
Reactor Coolant Temp. F.,
Hax.
618 618 618 618
- 8.
High Reactor Building 4
4 4
4 Pressure, psig, Oax.
(1) T is in degrees Fahrenheit (*Y).
(2)
Reactor Coolant System Flow, %.
(3) Administratively controlled reduction set only during reactor shutdown.
(4)
Automatically set when other segments of the RPS are bypassed.
Fable 2. 3-1t (1
tll it
(
Heactor Protective Systelm Iri Setting Limaits One Reactor Four Reactor Three Reactor Coolant Pump 0
Coolant Pumps Coolant Pumps Operating in O(perating Operat ing Each Loop (Operating Power (Operating Power (Operating Power Shutdown RPS Segment
-100% kAted)
-75% Hat
-49% Rated)
Bypass I.
Nuclear Power Hax.
105.5 105.5 105.5 5.0
(% Rated)
- 2.
Nuclear Power Max. Based 1.08 times flow 1.08 times flow 1.08 Limes flow bypassed on Flow (2) and Imbalance, minus reduction minus reduction minus reduction
(% Rated) due to imbalance due to imbalance due to imbalance
- 3.
Nuclear Power Max.
Based NA NA 55%
Bypassed N_
on Pump Monitors, (% Rated)
- 4.
High Reactor Coolant System 2300 2300 2300 1720 (4 Pressure, psig. Hax.
- 5.
Low Reactor Coolant System 1800 1800 1800 Bypassed Pressure, psig, Hin.
6z Variable Low Reactor Coolant (11.14 T 4706)(1)
(11.14 T out-4706)(1)
(11.14 T out-4706)(1)
Bypassed System Pressure,psig, Hin.
out 7..
Reactor Coolant Temp. F., Max.
618 618 618 618
- 8.
High Reactor Building 4
4 4
4 Pressure, psig, Max.
(1)
Tout is in degrees Fahrenheit (eF).
(2) Reactor Coolant System Flow, %.
(3)
Administratively controlled reduction set only during reactor shutdown.
(4)
Automatically set when other segments of the BPS are bypassed.
- 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-lAl, 3.5.2-1A2, and 3.5.2-1A3 (Unit 1); 3.5.2-131, 3.5.2-132, and 3.5.2-133 (Unit 2); 3.5.2-I1, 3.5.2-1C2, and 3.5.2-1C3 (Unit 3) for four pump operation, on figures 3.5.2-ZA1, 3.5.2-2A2, and 3.5.2-2A3 (Unit 1); 3.5.2-231, 3.5.2-2B2, and 3.5.2-233 (Unit 2); figures 3.5.2-2C1, 3.5.2-2C2, and 3.5.2-2C3 (Unit 3) for three pump operation, and on figures 3.5.2-2A4, 3.5.2-2A5, and 3.5.2-2A6 (Unit 1); 3.5.2-234, 3.5.2-2B5, and 3.5.2-236 (Unit 2); figures 3.5.2-2C4, 3.5.2-2C5, and 3.3.2-2C6 (Unit 3) for two pump operation. Also, excepting physics tests or exercising control rods, the axial power shaping control rod insertion/withdrawal limits are specified on figures 3.5.2-4A1, 3.5.2-4A2, and 3.5.2-4A3 (Unit 1); 3.5.2-4B1 (Unit 2); 3.5.2-4C1, 3.5.2-4C2, and 3.5.2-4C3 (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.
Amr-endments Nos. 124
,124 121 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-lAl, 3.5.2-1A2, and 3.5.2-1A3 for Unit 1; Figures 3.5.2-lBl, 3.5.2-1B2, and 3.5.2-1B3, for Unit 2; and Figures 3.5.2-101, 3.5.2-1C2, and 3.5.2-103 for Unit 3 unless one of the following 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 3.5.2-3A1, 3.5.2-3A2, 3.5.2-3A3, 3.5.2-3B1, 3.5.2-3B2, 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.
Operational 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. 124
, 124,&
121 3.3-10
Bases Opeiation 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 misalignment, 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. When 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 3.5.2-3A1, 3.5.2-3A2, 3.5.2-3A3, 3.5.2-3B1, 3.5.2-3B2, -3.5.2-3Cl, 3.5.2-3C2 and 3.5.2-3C3 is based on LOCA analyses which have defined the maximum linear heat rate (see Figure 3.5.2-5) 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 engineering 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.124
, 124, & 121 3.5-11
POWER LEVEL (300,102) 100 (150,102)
CUTOFF-100% FP (260.90) 80-SHUTDOWN (250.80 MARGIN LIMIT RESTRICTED OPERATION U.s UNACCEPTABLE a
OPERATION (90.50)
(200.50) 40 LU ACCEPTABLE OPFATION 20 (40.15)
(90,15)
(0.10)
(0,5h 0
0 50 100 150 200 250 300 ROD INOEX,%WO 0
25 50 75 100 BANK 5 0
25 50 75 100 BANK6 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION FROM 0 to 25 (+10, -0) EFPD UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-181 Amendments Nos. 124
, 124
, & 121 3.5-16
(150.102)
POWER LEVEL (275.102) (300.102 100-CUTOFF*100% FP SHUTDOWN (250.90)
MARGIN LIMIT 80L-(240.80)
RESTRICTED OPERATION U.
UNACCEPTABLE a 60-OPERATION C6 (90,501 (200,50)
S40 LU ACCEPTABLE OPERATION 20 (40,15)
(90,15)
(0.10)
(0,5h 0
0 50 100 150 200 250 300 ROD INOEX,%WO 0
25 50 75 100 BANKS 0
25 50 75 100 BANK 6 0
25 50 75 100 BANK-7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION FROM 25 (+10, -0) to 200 + 10 EFIPD UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-1B2 Amendments Nos.
124, 124, & 121 3.5-16a
POWER LEVEL CUTOFF*100% FP (220.102)
(275,102) 0, 100 (250,90)
RESTRICTED (240,80)
OPERATION UNACCEPTABLS OPERATION
- 0.
6U LU O
(160.50)
(200.50)
SHUTDOWN ACCEPTABLE MARGIN OPERATION LIMIT 20 90,15) o 50 100 150 200 250 300 RoD INOEX.%WD 0
25 50 75 100 BANK S 0
25 50 75 100 BANK 6 25 50 75 100 BANK 7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION AFTER 200 + 10 EFPD UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-1B3 Amendments Nos.
124, 124
, &121 3.5-16b
100 (130,771 (245,77)
C6
- 60.
LU UNACCEPTABLE OPERATION RESTRICTED (90.50)
OPERATION (200.50) 0 U
aSHUTDOWN MARGIN ACCEPTABLE LIMIT
-OPERATION 20 (30,15)
(90,15)
(0,10)
(0.5) 0 50 100 150 200 250 300 ROD INDEX.%WO 0
25 50 75 100 BANK 5 0
25 50 75 100 BANK 6 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION FROM 0 to 25 (+10, -0) EFPD UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-2B1 Amendments Nos. 124, 124, & 121 3.5-19
100 80 -(0.7 S(130,77)
(236.77)
UNACCEPTABLE OPERATION LURESTRICTED OPERATION (90,50)
(200,50) 0 SHUTDOWN MARGIN ACCEPTABLE LIMIT OPERATION 20 (30.15)
(90,15)
(0.10)
(0,5) 0 0
50 100 150 200 250 300 ROD INDEX,%WO 0
25 50 75 100 BANKS 0
25 50 75 100 BANK6 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION FROM 25 (+10, -0) to 200 + 10 EFPO UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-2B2 Amendments Nos. 124
, 124
& 121 3.5-19a
UI 100 RESTRICTED OPERATION 8021077)
(300,77)
(236.77) 96 0
a(16050)
(200,50)
UNACCEPTABLE O
OPERATION U
40 us SHUTDOWN ACCEPTABLE MARGIN OPERATION LIMIT 20 (90.15)
(0,5h a
50 100 150 200 250 300 ROD INOEX,%WO 0
25 50 75 100 BANK 5 0
25 50 75 100 BANKS a
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION AFTER 200 + 10 EFPO UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-2B3 Amendments Nos. 124 124
& 121
100 80 U.
so-.
(205.52)
(300.52) 0 (80.52)*
(200,50) c ;40 RESTRICTED W
SHUTDOWN OPERATION MARGIN ACPTABLE LIMIT OPERATION 20 UNACCEPTABLE OPERTION (50, 15)
(90,
- 15)
(0.10)
(0.5)<
a 50 100 150 200 250 30 ROD INOEX,%WO 0
25 50 75 100 BANK 5 0
25 50 75 100 BANK 6 0
25 50 75 100 1ANK 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 0 to 25 (+10, -0)
EFPO UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-2B4 Amendments Nos. 124
, 124
, & 121 3.5-19c
100 80 L6a
-60 LU (203.52)
(300.52) 480,52)
(200,50) a 0 RESTRICTED SGUTDOWN OPERATION ACCEPTABLE MARGIN OPERATION 20 UNACCEPTABLE OPERATION (50,15)
(90.15)
(0.10)
(0.5) o 50 100 150 200 250 300 RO INDEX,%WO 0
25 50 75 100 BANK5 0
25 50 75 100 BANK 6 0
25 50 75 100 SANK 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 25 (+10, -0) to 200 + 10 EFPO UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-2B5 Amendments Nos.
124,124
, &121 3.5-19d
100 80 RESTRICTED OPERATION s0 LU (203.52)
(300.52 UNACCEPTABLE (200,50) a OPERATION SHUTDOWN ACCEPTABLE MARGIN OPERATION LIMIT 20 (110,15)
(0.5) 0 0
50 100 150 200 250 300 ROD INDEX,%WD 0
25 50 75 100 BANK 5
0 25 50 75 100 BANK 6 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION AFTER 200 + 10 EFPO UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-286 Amendments Nos.
124,
124, & 121 3.5-19e
REACTOR POWER,%FP
(-18.2, 102.0)
-10 (25.0,102.0)
(-27.3, 90.0)
ACCEP"ABLE (30.0,90.0)
OPERA TION
(-32.2, 80.0)
.80 60 RESTRICTED OPERATION RESTRICTED OPERATION 40 20
-100
-80
-60
-40
-20 0
20 4a 60 80 100 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE FROM 0 to 25 (+10, -0) EFPD UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-381 A=endments Nos. 124
, 124
, & 121 3.5-22
REACTOR POWER,%FP
(-30.0, 102.0) 100 (25.0,102.0)
(-35.0,90.0)
ACCEPABLE (30.0,90.0)
OPERATION
-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 OCONEE NUCLEAR STATION Figure 3.5.2-3B2 Amendments Nos. 124
,124
, & 121 3.5-22a
(9.1, 102)
(40,102) 40(9.1,90) 80 (19.1. 80)
(40,80)
RESTRICTED OPERATION (0,70)
U.
a60 60.60)
O O
0 ACCEPTABLE OPERATION 20 0
20 40 60 80 100 APSR POSITION.%WD APSR POSITION LIMITS FOR OPERATION 0 EFPO to EOC UNIT 2 OCONEE NUCLEAR STATION Figure 3.5.2-4B1 Amendments Nos.
124, 124, & 121