Text

Proposed Revisions to Tech Specs 2.3,3.2 & 3.5.2.4 to Support Cycle 4 Operation at Full Power
	ML19316A527
Person / Time
Site:	Oconee
Issue date:	05/30/1978
From:	; DUKE POWER CO.
To:	;
Shared Package
ML19316A526	List: ML19316A525; ML19316A527;
References
	NUDOCS 8001100686
	Download: ML19316A527 (23)
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_ _ _ - - _ _ - - _ _ - _ - - - - _ ,

9 ATTACHMENT 1 Proposed Technical Specification Revision Pages l

8001100 68 6

)

i level trip and associated reactor power / reactor power-imbalance boundaries by g 1.055% for 1% flow reduction.

pump Monitors The pump monitors prevent the minimum core DNBR from decreasing below 1.3 by The circuitry tripping the reactor due to the loss of reactor coolant pump (s).

monitoring pu=p 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.

The reactor trip upon loss of one pump during 4-pump operation above 80% FP is specified for Unit 1 in order to provide a minimum of 11.2% DNBR margin in the flux / flow trip setpoint to accommodate the possible reduction in thermal margin due to rod bowing. For units 2 and 3, loss of one pump trip is not required because of thermal credits from excess RC flow, i.e., by maintaining a minimum RC l

flow of 109.5% for Unit No. 2 and 107.5% for Unit No. 3, respectively.

l 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 overpower trip setpoint. The trip setting limit shown in Figure 2.3-1A - Unit 1 2.3-1B - Unit 2 2.3-1C - Unit 3 for high reactor coolant system pressure (2355 psig) has been established to maintain the system pressure below the safety limit (2750 psig) for any design transient. (1)

-4706) trip The low pressure (1800)

(1800)psig psig and variable low pressure (11.14 T(11.14 T "'-4706) )

l (1800) psig (11.14 T " -4706) setpoints shown in Figure 2.3-1A have been established to maintaEn the DNB 2.3-1B '

2.3-1C ratio greater than or equal to 1.3 for those design accidents that result in a j pressure reduction. (2,3) l Due to the calibraticn and instrumentation errors, the safety analysis used a variable low reactor coolant system pressure trip value of (11.14 T "'-4746)

(11.14 T -4746)

(11.14 Tou"'t-4746) toolant Outlet Temperature The high reactor coolant outlet temperature trip setting limit (619 F) shown in Figure 2.3-1A has been established to prevent excessive core coolant 2.3-1B 2.3-1C Due to calibration and instrumentation errors, 1 temperatures in the operating range.

the safety analysis used a trip setpoint of 620 F.

2.3-3

i 4

i i

r 3.2 HIGH PRESSURE INJECTION AND CHEMICAL ADDITION SYSTEMS Applicability _

Applies to the high pressure injection and the chemical addition systems.

Objective To provide for adequate boration under all operation conditions to assure ability to bring the reactor to a cold shutdown condition.

Specification The reactor shall not be critical unless the following conditions are met:

3.2.1 Iwo high pressure injection pumps per unit are operable except as specified in 3.3.

3.2.2 One source per unit of concentrated soluble boric acid in addi-tion to the borated water storage tank is available and operable.

This source will be the concentrated boric acid storage tank containing at least the equivalent of 980 ft of3 8700, ppm boron as boric acid solution with a temperature at least 10 F above the crystallization temperature. System piping and valves necessary to establish a flow path from the tank to the high pressure injection system shall be operable and shall have the same temperature requirement as the concentrated boric acid storage tank. At least one channel of heat tracing capable of meeting the above temperature requirement shall be in operation.

One associated boric acid pump shall be operable.

If the concentrated boric acid storage tank with its associated flowpath is unavailable, but the borated water storage tank is available and operable, the concentrated boric acid storage tank shall be restored to operability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or the reactor shall be placed in a hot shutdown condition gnd be borated to a shutdown margin equivalent to 1% Ak/k at 200 F within the next twelve hours; if the concentrated boric acid storage tank has not been restored to operability within the next 7 days the reactor shall be placed in a cold shutdown condition within an additional 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . I If the concentrated boric acid storage tank is available but the l borated water storage tank is neither available nor operable, the 1 l

borated water storage tank shall be restored to operability within one hour or the reactor shall be placed in a hot shutdown condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in a cold shutdown condition within an additional 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l l

3.2-1

! l I

L t

Bases The high pressure injection system and chemical addition system provide control of the reactor coolant system boren concentration. (1)

This is normally accomplished by using any of the three high pressure injection pumps in series with a boric acid pump associated with either the boric acid mix tank or the concentrated boric acid storage tank. An alternate I method of boration will be the use of the high pressure injection pumps taking suction directly from the borated water storage tank. (2)

The quantity of boric acid in storage in the concentrated boric acid storage tank or the borated water storage tank is sufficient to borate the reactor coolant system to a 1% Ak/k subcritical margin at cold conditions the worst (70 F) time with the maximum worth stuck rod and no credit for xenon atOconee 1 Cycle 4, Oconee 2, in core life. The current cycles for each unit, Cycle 3, and Oconee 3, Cycle 4 were analyzed withonly Since the most limitingcycles the present case were selected as the basis for all three units. A minimum the specifications will be re-evaluated with each reload.

' analyzed,3 of 980 fc of 8,700 ppm boric acid in the concentrated boric acid storage tank, or a minimum of 350,000 gallons of 1800 ppm boric acid The in therequirements volume borated water include storage tank (3) will satisfy the requirements.

a 10% margin and in addition allow for a deviation of 10 EFPD in the cycle I

length. The specification assures that two supplies are available whenever the reactor is critical so that a single failure will not prevent boration to a 1 cold condition. The required amount of boric acid can be added in several ways.

' Using only one 10 gpm boric acid pump taking suction from the concentrated boric acid storage tank would require approximately 12.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months to inject the required boron. An alternate method of addition is to inject boric acid from the borated water storage tank using the makeup pumpf. The required boric acid can be in-jected in less than six hours using only one of the makeup pumps.

The concentration of boron in the concentrated boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.

For this reason and to assure a flow of boric acid is available when needed, these tanks and their associated piping will be kept at leastThe 10 Fboric above acidthe 1

concen-crystallization temperature for the concentration present.

tration of 8,700 ppm in the concentratgd boric acid storage tank corresponds to a crystallization temperature of 77 F and therefore a temperature require-Once in the high pressure injection system, the concentrate ment of 87 F.

is sufficiently well mixed and diluted sot that normal system temperatures assure boric acid solubility.

REFERENCES l -(1) FSAR, Section 9.1; 9.2 (2) FSAR, Figure 6.2

, i (3) Technical Specification 3.3 3.2-2

[

i

g. If within one (1) hour of determination of an inoperable rod, .

i it is not determined that a 1%Ak/k hot shutdown margin exists combining the worth of the inoperable rod with each of the other rods, the reactor shall be brought to the hot standby condition until this margin is established.

h. Following the determination of an inoperable rod, all rods shall be exercised within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and exercised weekly until the rod problem is solved.

i. If a control rod in the regulating or safety rod groups is declared inoperable, power shall be reduced to 60 percent of the thermal power allowable for the reactor coolant pump combination.

j. If a control rod in the regulating or axial power shaping groups is declared inoperable, operation above 60 percent of rated power may continue provided the rods in the group are positioned such that the rod that was declared inoperable is maintained with-in allowable group average position limits of Specification 3.5.2.2.a and the withdrawal limits of Specification 3.5.2.5.c.

3.5.2.3 The worths of single inserted control rods during criticality are limited by the restrictions of Specification 3.1.3.5 and the control rod position limits defined in Specification 3.5.2.5.

3.5.2.4 Quadrant Power Tilt

a. Except for physics tests, the maximum positive quadrant power tilt s'alln not exceed the Steady State Limit of Table 3.5-1 during power operation above 15% full power.

b. If the maximum positive quadrant power tilt exceeds the Steady

' State Limit but is less than or equal to the Transient Limit of Table 3.5-1, then:

l

1. Either the quadrant power tilt shall be reduced within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to within its Steady State Limit or

2. The reactor thermal power shall be reduced below the power level cutoff (as specified in Specification 3.5.2.5) and further reduced 2% thermal power for each 1% of quadrant power tilt in excess of the Steady State Limit, and the Nuclear Overpower Trip Setpoints, based on flux and flux /

flow imbalance, shall be reduced within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by 2%

thermal power for each 1% tilt in excess of the Steady State Limit. If less than four reactor coolant pumps are in operation, the allowable thermal power for the reactor coolant pump combination shall be reduced by 2% for each ,

l 1% excess tilt.

3.5-7

h

c. Quadrant power tilt shall be reduced within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to with-in its Steady State Limit or,

1. The reactor thermal power shall be reduced within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than 60% of the allowable power for the reactor coolant pump combination and the Nuclear Overpower Trip Setpoints, based on flux and flux / flow imbalance, shall be reduced within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 65.5% of the thermal power value allowable for the reactor coolant pump combina-tion.

d. If the quadrant power tilt exceeds the Transient Limit but is less than the Maximum Limit of Table 3.5-1 and if there is a simultaneous indication of a misaligned control rod then:

1. Reactor thermal power shall be reduced within 30 minutes at least 2% for each 1% of the quadrant power tilt in ex-cess of the Steady State Limit.

2. Either quadrant power tilt shall be reduced within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to within its Transient Limit or,

3. The reactor thermal power shall be. reduced within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than 60% of the allowable power for the reactor coolant pump combination and the Nuclear Overpower Trip Setpoints, based on flux and flux / flow imbalance, shall be reduced within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 65.5% of the thermal power value allowable for the reactor coolant pump combination.

l

e. If the quadrant power tilt exceeds the Transient Limit but is '

less than the Maximum Limit of Table 3.5-1, due to causes other than simultaneous indication of a misaligned control rod then:

1. Reactor thermal power shall be reduced within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than 60% of the allowable power for the reactor coolant pump combination and the Nuclear Overpower Trip Setpoints, based on flux and flux / flow imbalance, shall be reduced within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to 65.5% of the thermal power value allowable for the reactor coolant pump com-bination.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Subsequent reactor operation is permitted for the purpose of measurement, testing, and corrective action provided the thermal power and the Nuclear Overpower Trip Setpoints allowable for the reactor coolant pump combination are restricted by a reduction of 2% of thermal power for each 1% tilt for the max-imum tilt observed prior to shutdown,

g. Quadrant power tilt shall be monitored on a minimum frequency of once every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during power operation above 15% full power.

3.5-8

i i

! 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 c' apply to inoperable safety rod limits in Technical Specification 3.5.2.2.

4

b. Except for physics tests, operatin3 rod group overlap shall be 25%

5% between two sequential groups. If this limit is exceeded, I corrective measures shall be taken immediately to achieve an accept-able 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. Position limits are specified for regulating and axial power shap- '

l ing control rods. Except for physics tests or exercising control I rods, the regulating control rod insertion / withdrawal limits are specified on figures 3.5.2-1A1 and 3.5.2-1A2 (Unit 1); 3.5.2-1B1, i i

3.5.2-1B2 and 3.5.2-1B3 (Unit 2); 3.5.2-1C1, 3.5.2-1C2 and 3.5.2-1C3 1 (Unit 3) for four pump operation, and on figures 3.5.2-2A1 and 3.5.2-2A2 (Unit 1); 3.5.3-2B1, 3.5.2-2B2 and 3.5.2-2B3 (Unit 2);

l 3.5.2-2C1, 3.5.2-2C2 and 3.5.2-2C3 (Unit 3) for two or three 4

pump operation. Also, excepting physics tests or exercising control l rods, the axial power shaping control rod insertion / withdrawal limits I are specified on figures 3.5.2-4A1, and 3.5.2-4A2 (Unit 1); 3.5.2-4B1, 3.5.2-4B2, and 3.5.2-4B3 (Unit 2); 3.5.2-4C1, 3.5.2-4C2, and 3.5.2-4C3 i (Unit 3).

l 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 i within two hours. The minimum shutdown margin required by Specifi-cation 3.5.2.1 shall be maintained at all times.

d. Except for physics tests, power shall not be increased above the t power level cutoff as shown on Figures 3.5.2-1A1, and 3.5.2-1A2 j (Unit 1), 3.5.2-1B1, 3.5.2-1B2, and 3.5.2-1B3 (Unit 2), and 3.5.2-1C1, 3.5.2-1C2, 3.5.2-1C3 (Unit 3), unless the following requirements are met:

(1) The xenon reactivity shall be within 10 percent of the value for operation at steady-state rated power.

(2) The xenon reactivity worth has passed its final maximum or i

minimum peak during its approach to its equilibrium valve for operation at the power level cutoff.

3.5.2.6 Reactor power imbalance shall be monitored on a frequency not to exceed ]

two hours during power operation above 40 percent rated power. Except I for physics tests, imbalance shall be maintained within the envelope j i

defined by Figures 3.5.2-3A1, 3.5.2-3B1, 3.5.2-3B2, 3.5.2-3B3, 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.

3.5-9 9

-+ - , - - ,. , ,, , - y ..g. ,

3.5.2.7 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.

Bases The power-imbalance envelope defined in Figures 3.5.2-3A1, 3.5.2-3B1, 3.5.2-3B2 ,

3.5.2-3B3, 3.5.2-3C1, 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 1

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 (quadranttilt, rod position, and imbalance) must be at their limits while simultaneously all other engineering and uncertainty f actors are also at their limits.**

is introduced by application of: Conservatism I

a. Nuclear uncertainty factors

b. Thermal calibration c.

d. Fuel densification power spike factors (Unita 1 and 2 only)

Hot rod manufacturing tolerance factors l e.

Fuel rod bowing power spike factors The 25% t 5% overlap between successive control rod groups is allowed since the i worth of a rod is lower at the upper and lower part of the stroke. Control rods l

are arranged in groups or banks defined as follows:

Group Function 1

Safety 2

Safety 3 Safety 4 Safety 5 Regulating 6

Regulating )

7 j 8 Xenon transient override ;

APSR (axial power shaping bank)

The rod position criteria: limits are based on the most limiting of the following three ECCS power peaking, shutdown margin, and potential ejected rod worth.

Therefore, rod positioncompliance limits. with ;he ECCS power peaking criterion is ensured by the The minimum available rod worth, consistent with the rod position limits, provides for achieving hot shutdown by reactor trip at ar.y time, [

1 assuming position the highest worth control rod that is withdrawn remains in the full out (1).

The rod position limits also ensure that inserted rod groups will not contain single rod worths greater than 0.65% Ak/k at rated power. These values have accident.

rod ejection been shown to be safe by the safety analysis (2,3,4,5) of hypothetical A maximum single inserted control rod worth of 1.0%Ak/k

- Actual operating limits depend on whether or not incore of e used and their respective instrument calibration errors. xcore detectors are l The method used to define the operating limits is defined in plant operating procedures. ;

f 3.5-10

is allowed by the rod position limits at hot zero power. A single inserted control rod worth of 1.0%ak/k at beginning-of-life, hot zero power would result in a lower transient peak thermal power and, therefore, less severe environmental consequences than a 0.65%Ak/k ejected rod worth at rated power.

Control rod groups are withdrawn in sequence beginning with Group 1. Groups 5,6, and 7 are overlapped 25 percent. The normal position at power is for Groups 6 and 7 to be partially inserted. ,

l The quadrant power tilt linits set forth in Specification 3.5.2.4 have been established to prevent the linear heat rate peaking increase associated with a positive quadrant power tilt during normal power operation from exceeding 9.00% for Unit 1. The limits shown in Specification 3.5.2.4 5.10% for Unit 2 l 7.50% for Unit 3 are measurement system independent. The actual operating limits, with the l appropriate allowance for observability and instrumentation errors, for each measurement system are defined in the station operating procedures.

The quadrant tilt and axial imbalance monitoring in Specification 3.5.2.4 and 3.5.2.6, respectively, normally will be performed in the process computer. The two-hour frequency for r;ienitoring these quantities will provide adequate surveillance when the computer is out of service.

Allowance is provided for withdrawal limits and reactor power imbalance limits to be exceeded for a period of two hours without specification violation.

Acceptable rod positions and imbalance must be achieved within the two-hour time period or appropriate action such as a reduction of power taken.

Operating restrictions are included in Technical Specification 3.5.2.5d to prevent excessive power peaking by transient xenon. The xenon reactivity must be beyond its final maximum or minimum peak and approaching its equilibrium value at the power level cutoff.

_ REFERENCES I

FSAR, Section 3.2.2.1.2 FSAR, Section 14.2.2.2 FSAR, SUPPLEMENT 9 B&W FUEL DENSIFICATION REPORT i

BAW-1409 (UNIT 1)

BAW-1396 (UNIT 2)

BAW-1400 (UNIT 3) 5 0conee 1, Cycle 4 - Reload Report - BAW-1447, March 1977, Section 7.11.

3.5-11

TABLE 3.5-1 Quadrant Power Tilt Limits Steady State Transient Maximum Limit Limit Limit Unit i 6.03 9.44 20.0 Unit 2 3.41 9.44 20.0 Unit 3 5.00 9.44 20.0 3.5-11a

110

( B2.1,102) (174.1,102),, ,,(212.6,102) 100 -

RESTRICTED GPERail0NS REGICN 90 - NOT (174.1,00) , (212.G.90)

RESTRICTED -

ALLCKED REGION POWER (251.4,80) 80 -

LEVEL (161.2,80)

SHU100nN CUTOFF m 70 MARGIN (151.4,70)

=

0 LIMIT (300,70)

= 60 -

o 50 -

J' (29,50)

PERMISSIBLE OPERATING REGION 30 -

20 w (0,15) 10 -

0 . ( '!} t t t i i t i i e i e i

~

t 0 20 40 60 60 100 120 140 160 180 200 220 240 260 280 300 Roc tridex, 5 Wit' : ta, e t i e i i

t t i i 0 25 50 75 100 0 25 50 75 100 Group 5 Group 7 I I f I I O 25 50 75 100 Group 6 .

e ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 0 TO 100 + 10 EFPD OCONEE 3 butnath; OCONEE NUCLEAR STATION D'

Figure 3.5.2-1c1 m

110 (164.9,102) (174.1.102) (232.102) 100 -

it 0 RESTRICIED REGION

~ OPERATION IN THIS 90 ,(174.1,90)

REGION IS NOT ALLOWED (232,90)

POWER I.EVEL B0 -

CUTOFF p&x (161.2,80)

(251,4,80) 70 -

[

SHUT 00$N EARGIN

3 60 n

_. LIMIT &

50 .

(90,50)

PERMISSIBLE OPERATING 2

REGION a 40 -

a.

30 -

1 20 _ ( 0,13)

(30,15) 10 -

RESTRICIED REGION O f i t i f i 1 i e i i i i 0 20 40 60 80 100 120 140 160 180 200 220 240 250 280 300 !

Red Indet, '. Withdrawn i i t e i t_ t 0 i i 25 50 75 1 100 0 Grcup 5 25 50 75 100 Grcup 7 . 4 i I i l i 0 25 50 75 100 Group D l

ROD POSITION LIMITS !

FOR FOUR-PUMP OPERATION j FROM 100 + 10 TO 235 + 10 EFPD OCONEE 3 s

counain OCONEE NUCLEAR STATION

'N {

Figure 3.5.2-102 !

3.5-16. !

110 (191.2,102) (251.4,102) 100 ~

OPERAil0N IN lHis REGl0N NOT ALL0fiED RESTRICTED 90 -

REGION >(251.4,90)

' POWER LEVEL BD CUTOFF (241.8,80)

SHUT 007:N PARGIN 00

'a

" 50 -

, (110,50) 2 -

k 40 -

PERMisslBLE OPERATING REGION 30 -

20 -

(0,7) ( ' }

l 10 (0,0) 0 ' ' ' 8 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Rod Index, % Witnarann i I I I e i I e e i 0 25 50 15 100 0 25 50 75 100 Group 5 Group 1 i I , t i 0 25 50 15 100 Group 6 ROD POSITION LIMITS r0R FOUR-PUMP OPERATION AFTER 235 i 10 EFPD OCONEE 3 nu rcate) OCONEE NUCLEAR STATION D

Figure 3.5.2-1c3 3.5-17 . _ .

i 110 OPERATION IN ( ' } ( **

100 -

THIS REGION NOT (209.0,102)

ALLDRED RESTRICTED RESTRICTEC FOR 3 PUMPS REC,10N FOR 5

90 -

(151.4,03.7) (300,93.1) 3 PUMP

% SHUT 00 fin OPER.

b EO - F.ARGIN +

g LIMIT o

70 (50,70)

[ -

o PERMISSIBLE OPERATING

[ 60 -

REGION 3 50 -

Q 3 40 -

O

" 30 -

g RESTRICTED FOR

3 PUMP OPERATION Z. 20 .

(0,15) 10 -

(0,0) 0 i i ' ' ' r ' ' ' ' i i e 1 0 20 40 00 80 100 120 140 160 180 200 220 240 260 280 300 Red index, 5 Witriarawn

1 I I t f e a t f f i 0 25 50 75 100 0 25 50 75 100 Group 5 Group 7 e ! ! I t 0 25 50 75 100 l Group B l

ROD POSITION LIMITS j FOR TWO & THREE-PUMP OPERATION i FROM 0 TO 100 + 10 EFPD j OCONEE 3 M

totunath OCONEE NUCLEAR STATION l

l I

vg, Figure 3.5.2-2C1 l

l 3.5-20 i

f 110 -

(1E49,102) (2C3.5.102;

~

RESTRICTED FOR 3 #

OPERATION IN THIS REGION OPERATION E IS NOT ALLOKE0

- 90 . (300,93.7) e E

R BD -

o E

70 SHUT 00hN MARGIN LilllT~ PERRISSIBLE OPERATlHG REGION y 60 -

2 3 50 -

(90,50) ,

2 40 -

O e

g 30 -

L' (0,13 )

(30.15) 10 - -- -RESTRICTED FOR 2f.3 PU'4P OPERATION (0,0) 0 e i i i , i i i e i i i , i 0 20 40 60 8'O 100 120 140 160 180 200 220 240 260 280 300 Red inces, % Withdrawn

, i i i i ,

e i i i 0 25 50 75 100 0 25 50 75 100 .

Group 5 Group 7 1 I i t i 0 25 50 75 100 Group 6 ,

ROD POSITION LIMITS FOR TWO & THREE-PUMP OPERATION FROM 100 + 10 to 235 + 10 EFPD

~ ~

OCONEE 3 i i OCONEE NUCLEAR STATION Figure 3.5.2-2c2 3.5-20a

110 RESil;lCTED F0P. 2 f.3 PU"P OPEllATION

gg _

(191.2.102) / (218.5.102) 90 -

(100.6.93.7)

_E g 60 -

OPERAll0!1 IN THIS REGl0t!

", 15 NOT ALL0hED c

s 70 -

E 60 -

3 PEP.MISSIBLE

=

OPERATING

- 50 - -

E REGl0f1

& (110,50) 3 40 -

~

o 30 -

~

5 E 20 -

(48,15) 10 _

I'" ,

RESTRICTED FOR 2 & 3 (0,0) PUMP OPERATION O i i , i , i , i e i , , , t 0 20 40 60 80 100 120 140 160 120 200 220 240 260 280 300 Rod Inder, t Withdrawn i i i t t i i i i j 0 25 50 75 100 0 25 50 15 100 Group 5 Grcup 7 f f I I i 0 25 50 75 100 Grcup 6 ROD' POSITION LlHITS c0R TWO r, THREE-PUMP OPERATION AFTER 235 + 10 EFPD OCONEE 3

, OCONEE NUCLEAR STATION Figure 3.5.2-2c3 ,

t 3.5-20b '

/

P: iter, 5 of 2508 n'Wt RESTRICTED REGION

-19,102 '

- 100

-22.5,00 -- SO 3-20,90 30,00 -- 80 o 20,00

-- 70 60

-- 50

-- 40 PERMISSIDLE OPERATING

-- 30 REGION

-- ;D

-- 10 i t i , , , ,

50 -40 30 -20 -10 0 10 20 30 40 50 Axial Poner Iccalance,~5 OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION FROM 0 TO 100 + 10 EFPD i OCONEE 3 i i

$ninani OCONEE NUCLEAR STATION W'

Figure 3.5.2-3c1 l

3.5-23 __

I

Po*er, s cf 25CE n t RESTRICTED REGION 22,102 A *

-- 100 30,so - - 90 3 20,90 36,80 .c, -- 80 4,. 20,80

-- 70 60

-- 50 PERMISSIBLE OPERATING -- 40 REGION 30

- - 20

-- 10 I f f f f f f f l

-50 40 30 20 10 0 10 20 30 40 50 4xial Poner le::alance, 5 OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION FROM 100 + 10 TO 235 + 10 EFPD OCONEE 3 eat swin OCONEE NUCt. EAR STATION sg, Figure 3.5.2-3C2 3 5-23a

i Power, 5 cf 256B Ht RESTRICTED REGION

-2 G ,102 A '

-- 100

-39,90 -- 90 > 25,90 30,80 o -- 60 0 25,80

-- 70

-- CO PERMISSIBLE OPERAT il:G

-- 50 REGION

- 40

. - 30

-- 2 0

-- 10 l t I f f f f f I f

-50 40 -30 20 -10 0 10 20 30 40 50 .

Axial Power I:noalance, 5 OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION AFTER 235 1 10 EFPD OCONEE 3 i OCONEE NUCLEAR STATION ig, l Figure 3.5.2-3C3 I

y 3 5-23b

(

100 -

RESTRICTED REGION .

90 -

19.1.90 80 - '

~

j

=

100,70

% 60 -

'o

- 50 -

PE R.'JISS I BLE d OPERATING

$ 40 -

REGION 3C -

20 -

10 -

0 ' ' ' t i i e r i 0 10 20 30 40 50 60 70 80 S0 100 APSR, 5 Vitnarawn '

E APSR POSITION LIMITS FOR OPERATION FROM 0 TO 100 + 10 EFPD OCONEE 3 otst roaa OCONEE NUCLEAR STATION D

Figure 3.5.2-4C1 l

3.5-231

23,102 100 -

RESTRICTED 90 - - 25.5,90 REGICH EQ -

5,80 70 -

, 100,70 E '

= 60 - i

= * !

~

E 50 -

a l

40 -

E PERMISSIBLE 30 - OPERATING REGION 20 -

~

10 -

0 ' ' ' ' ' ' ' ' '

O 10 20 30 40 50 60 70 80 90 100 APSFi, 5 tilnataan 1

APSR POSITION LIMITS FOR OPERATION FROM 100 + 10 to 235 + 10 EFPD OCONEE 3 peurcare OCONEE NUCLEAR STATION sg, Figure 3.5.2-4c2 3.5-23J

o i

25.5.102 100 - RESTRICTED REGION

,00 SD -

- 64.4,80 80 -

g 10 - , 100,70 m

l N 60 O

h% *

,. 50 -

5 40 - PER!f.1SS IBLE OPERATING REGION .

30 -

20 -

10 -

t I I I ' I I I '

O 0 10 20 30 40 50 60 70 80 90 100 .

APSR, 5 Witnarawn APSR POSITION LIMITS FOR OPERATION AFTER 235 + 10 EFPD OCONEE 3 b

nut mate; OCONEE NUCLEAR STATION Figure 3.5.2-4c3 3.5-23k

l l

1

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i ATTACRIENT 2 I Ocenee 3 ;ycle 4 Reload Report BAW - 1490 l

ML19316A527

Text

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