ML19320A167

Proposed Tech Spec 3.5 Re Parameter Changes & Mods Required for Cycle 3 Operation

ML19320A167
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/28/1977
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19320A164	List: ML19320A163 ML19320A167
References
NUDOCS 8004210469
Download: ML19320A167 (17)

Text

.-

,. n  :

9 Thermal Power Level, %

UNACCEPTABLE OPERATION (-40,112) (26.112) 112 _

i ACCEPTABLE 4 PUNP

, OPERATION - J 00 85.6

(-70.ao) (-vo, s s. s) (26,ss.s 2

ACCEPTABLE

- 80 ( 53, so )

3 & 4 PUNP OPERATION

(-s4.s4)

_ 58.6 - . 60 '

3

(-v sa. s) (2s,ss.s (55,55)

(-us,us)

ACCEPTABLE 2,3 & 4 PUMP OPERATION - 40 (93.'3)

- 20 i . . ,

-80 60 -40 20 0 20 40 60 80 Power Imaalance, %

CURVE REACTOR COOLANT FLOW (GPN) 1 374,880 2

280,035 3

184,441 ARKANSAS POWER AND LIGNT CORE PROTECTION SAFETY LIMITS 9b i m e 2.1-2 goo 4210

The power level trip set poi nt produced by the power-to-flow ratto provides both high power 1ccel and low flow protection in the event the reactor power level ane rcases or the react or coolant , flow rate decreases. The power level trip set point produced by the power to flow ratio provides overpower DNil protection 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 pemissible low flow rate. Typical power level and low flow rate combinations for the pump situations of Table 2.3-1 are as follows:

1. Trip would occur when four reactor coolant pumps are operat ing if power is 106.0 percent and reactor flow rate is 100 percent n p' rat e is 94.3 percent and power level is 100 percent.

O g  % or flow U g Trip would occur when three reactor coolant pumps are operating n ,,

'f rp wer is 79.1 percent and reactor flow rate is 74.7 percent 0 9 _T A T fl

• T8tc 15 7 .7 Percent and Power level is 75 percent.

v ~ '

1. If would occur when one reactor coolant pump is operating in each loop (total of two pumps operating) if the power is 52.3 percent and reactor flow rate is 49.2 percent or flow rate is 46.2 percent and the power level as 49.0 percent.

The flux / flow rat ios account for the muimum calibration and instrumentation errors and the maximum variat ion fron the aserage value of the RC flow signal in such a manner that the reactor prot ect ive system receives a conservative indication of the RC flow.

.g le penalty in reactor coolant flow through the core was taken f: r an open core vent valve because of the core vent valve surveillance program during

,, each refueling outage. For safety analysis calculations the maxista cali-bration and inst mmentation errors for the power level were used.

The power-imbalance boundaries are established in order to prevent reactor l thermal limits from being exceeded. "Ihese themal limits are either power )

peaking kW/ft limits or DNBR limits. The reactor power imbalance (power in {

top half of core minus power in the bottom half of core) reduces the power '

-level trip produced by the power-to-flow ratio so that the boundaries of {

Figure 2.3-2 are produced. The power-to-flow ratio reduces the power level trip associated reactor power-to-reactor power imbalance boundaries by 1.060 percent for a 1 percent flow reduction. .

B. Pump monitors In conjunction with the power imbalance / flow trip, the pump moni-itors prevent the minimum core DNBR from decreasing below 1.3 by trip-ping the reactor due to the loss of reactor coolant pump (s). The pump monitors also restrict the power level for the number of pumps in operation.

C. RCS Pressure During a startup accident from low power or a slow rod withdrawal from high power, the system high pressure trip set point is reached before the nuclear overpower trip set point. The trip setting limit 4

12 Amendment No. 21 l

Thermal Power Level, ".

120 --

,0 (-19,106) 1 06 (14,106)

+N 100-- #,

(-26,99) ACCEPTABLE 4 y PUMP OPERATION '#,

(-19,79.1) 80..79.1 (4080) m(ig,79.8) >

(-26,72.1) t ACCEPTABLE 3&4 PUMP OPERATION 60._

(-19,52.1) 52.1 (14.52.1) ,(42,53.2)

(-26,45.1)<

40._

ACCAPTABLE 2,3 0

D 84 PUMP D OPERATION 3 ,(42,26.1) 3'9 20 .

'T 7 7 .T il 11 Il ll

, . . . i . . . . .

50 40 -30 -20 -10 0 10 20 30 40 50 Power imoalance, ",

ARKANSAS POWER AND LIGHT CONPANY UNIT I PROTECTIVE SYSTER MAXINUN ALLOWAOLE SETPOINTS Figure 2.3-2 14b

. ,m i.. I f . 6 on t ro l rod in the regulat inr, or axial power shaping group

• des tared inoperable per Specificat ie.n 4.~.I.2. operation above t0 percent of the therwal power allowable for the reactor coolant pump enmhination may continue provided the rod- in the group are positinned such that the rod that was deleared inop.erable is con-tained within allowable group average position limits of Specifica-tion 4.7.1.2 and the withdrawal limits of Specificat ion 3.5.2.5.3.

3.5.2.3 The worth of single inserted control rods during criticality are limited by the restrictions of Specification 3. t.3.5 and the Control Rod Position Limits defined in Specification 3.5.2.5.

3.5.2.4 Quadrant tilt:

1. lixcept for physics tests, if quadrant tilt excccil 4.92% power shall be reduced immediately in below the power _ level eutoff (see Figures 3.5.2-1A and 3.5.2-1Bl. Moreover, the power lesel eutoff value

> hall be reduced 2*. for each l'. tilt in excess of 4.92% t ilt . For less than 4 pump operat ion, thermal power shall he reduced 2*. of the thermal power allowable for the reactor coolant pump combin-ation for each l'. t ilt in excess of '4.92%.

2. hithin a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the quadrant power tilt shall be reduced to less than 4.9'2% execpt for physics tests, or the following adjust- l ments in setpoints and limits shall be made:

Q D. Ihe protection system maximun allowahle setpoints (Figure D

- fl U

2.3 2) shall be reduced ."- in power foreach I'. t ilt .

h dh~ centrol rod group and APSR withdrawal limits 'shal1 be

6) jr u ed 2% in power for each 1% tilt 'in excess of 4.92%. '

%(W 0

c. The operational imbalance limits shall be reduce'd 2% in power for each 11 tilt in excess of 4.92%.

3. If quadrant tilt is in excess of 25%, execpt for physics testa or diagnostic testing, the reactor will be placed in the hot shutdown '

condition. Diagnostic tcsting during power operation with a quad-rant power tilt is permitted provided the thermal power allowable for the reactor coolant pump combination is restricted as stated -

in 3.5.'.t.1 above.

4. Quad rant tilt shall oe monitored on a minimum frequency of once every two hours during power operation above 15*. of rated power.

3.5.2.5 Cont rol rod positions:

1. Technical Specification 3.1.3.5 (safety rod withdrawal

• does not prohibit the xercising of individual safety rods as required by Table 4.1-2 or apply to inoperable safety rod limits in Technical Spec i fi ca t i on 3. 5. 2. 2.

2. Operat ing rod group overlap shall be 25% 15 between two sequential groups, except for physics tests.

Amendment No. j, 21 47 4

,. em

3. ' Except for physics tests or exercising control rods, a) the control rod withdrawal limits are specified on Figures 3.5.2-1A, 3.5.2-1B and 3.5.2-1C for four pump operation and,on Figures 3.5.2-2A, 3.5.2-2B and 3.5.2-2C for three or two pump operation and b) the axial power shaping control rod withdrawal limits are specified on Figures 3.5.2-4A, 3.5.2-4B and 3.5.2-4C. If any of these control rod position limits are exceeded, corrective measures shall ba taken immediately to achieve an acceptable control rod position. Acceptable control rod positions attained within four hours.

n 4

Except for physics tests, power shall not be increased above the power level cutoff (see Figures 3.5.2-1) unless the xenon reactivity is within 10 percent of the equilibrium value for operation at rated power and asymptotically approaching stability.

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 for physics tests, imbalance shall be maintained within the envelopes defined by Figures 3.5.2-3A, 3.5.2-3B and 3.5.2-3C. If the imbalance is not within the envelopes defined by Figures 3.5.2-3A, 3.5.2-3B and 3.5.2-3C corrective measures shall be taken to achieve an acceptable imbalance. If an acceptable imbalance is not achieved within four hours, reactor power shall be reduced until imbalance limits are met.

3.5.2.7 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the superintendent.

Bases The power-imbalance envelopes defined in Figures 3.5.2-3A, 3.5.2-3B and 3.5.2-3C are based on 1) LOCA analyses which have defined the maximum linear heat rate (See Fig. 3.5.2-4) such that the maximum clad temperature will not exceed the final Acceptance Criteria and 2) the Protective Sys. tem Maximum Allowable Set p ints (Figure 2.3-2). Corrective measures will be taken immediately should the indicated quadrant tilt, rod positior- 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.* Conserva-tism i.s introduced by application of:

a. Nuclear uncertainty factors

b. Thermal calibration

c. Fuel densification effects

d. Hot rod manufacturing tolerance factors

e. Fuel rod bowing The 25 25 percent overlap between successive control ' rod groups is al1 owed since the worth of a rod is lower at the upper and lower part of the stroke.

Control rods. are arranged in groups or banks defined as follows:

• Actual operating limits depend on whether or not incore or excore detectors are used and their respective instrument and calibration errors. The method used to define the operating limits is defined in plant operating procedures.

AAendment No. 21' 48

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, .s POWER

(% OF 2568 MWt)

-20.1.102 F I

100 - -

-21.0,92 1,92 90 - - .

-26.7,80 '

80 - -

> +10. 7 , 80 70 - -

60 --

PERMISSIBLE OPERATING REGION RESTRICTED RESTRICTED REGIGN REGION 30 - -

20 - -

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-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Power imoalance (%) ,

OPERATION POWER INBALANCE ENVELOPE FOR OPERATION FRON 0 TO 100 t 10 EFPO ARKANSAS CYCLE 3 Figure 3.5.2-3A 48d

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RESTRICTED PERNISSl8LE REGION IN RESTRICTED ON REGION 40 --

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-50 30 -20 -10 0 10 20 30 40 50 Axlal Power Imbalance OPERATIONAL POWER IN8ALANCE ENVELOPE FOR OPERATl0N FRON 100110 TO 250 t 10 EFPO ARKANSAS CYCLE 3 Figure 3.5.2-38 48cd

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-27.3.102 -

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OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION AFTER 250 t 10 EFPO ARKANSAS, CYCLE 3 Figure 3.5.2-3C 1

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