ML19345G313

Amend 52 to License DPR-51,modifying Tech Specs to Support Operation at Full Power During Cycle 5

ML19345G313
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/09/1981
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19345G314	List: ML19345G313 ML19345G321 ML19345G326
References
NUDOCS 8103180152
Download: ML19345G313 (38)

Text

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'g UNITED STATES NUCLEAR REGULATORY COMMISSION 3+ -

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.j WASHING TON, D. C. 20666

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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 A_RKANSAS NUCLEAR ONE - UNIT NO. 1 AMENDMENT TO FACILITY OP_ERATING LICENSE Arendment No. 52 L1;ense No.DPR-51 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Arkansas Power and Light Company (the licensee) dated January 30, 1981 as supplemented February 12 and 26,1981, complies with the standards and require-ments of the Atomic Energy Act cf 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; i

l D.

The issuance of this amendment will not be inimical to the comon dafense and security or to the health and safety of the public; and l

E.

The issuance of this amendment is in accordance with 19 CPR I' art 51 of the Comission's regulations and all applicable requirements have been satisfied.

l 810818 0 \\6D

. 2.

Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License l

No. DPR 51 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendrent No. 52, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amencment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSIOff

$* Y Robert W. Peid, Chief Operating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical 5pecifications Date of Issuance: March 9, 1981 4

o

ATTACHMENT TO LICENSE AMEi!DftENT N0. 52 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET N0. 50-313 Replace the following pages of the' Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendnent ntriber and contain vertical lines indicating the area of change.

Insert

, Remove iv iv 8

8 9

9 9b 9b 12

-12 14b 14b 15

15 35 35 35a 35a-48 48' 48a i

-48a-48al 48al'

'48b 48b-48bl

=48bb 48b2

'48bbb-48b3 48c

'48c-

.48cl 48cc 48c2 48ccc -

48c3-48c4 48c5~

l' 4

_2_

I.scrt Remove 48c6 48c7 48d 43d 48dl 48dd 48d' 48ddd 48d3 48e 48e 48f 48f 489 489 48h 48h 48i

LIST OF FIGURES o ge a

Title Nunber 9a 2.1-1 CORE PROTECTION SAFETY lit 1IT 9b 2.1'- 2 '

CORE PROTECTION SAFETY LIMITS 9c 2.1-3 CORE PROTECTION SAFETY LIMITS 14a

'2.3-1 PROTECTIVE SYSTEll MAXIMUM ALLOWABLE SETP0 INT 14b

'2.3-2 PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS 3.1.2-1 REACTOR COOLANT SYSTEtt HEATUP AND C00LD0HN LIMITATIONS 20a 3.1.2-2 REACTOR COOLANT SYSTEM NORiiAL OPERATION-HEATUP LIMITATIONS 20b 3.1. 2-3 '

REACTOR C00LANT SYSTE!!, NORMAL OPERATION-COOLDOWN LIMITATIONS 20c

'3.1.9-1 LIMITING PRESSURE VS TEMPERATURE FOR CONTROL R0D DRIVE 33 OPERATION WITH 100 STD CC/ LITER H O 2

3.2.1 BORIC ACID ADDITION TANK YOLUME AND CONCENTRATION VS. RCS 35a AVERAGE TEMPERATURE 3.8i.2-1A R00 POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 0 TO 60 EFPD-48b ANO.1, CYCLE 5, 3.5-2-1B-R0D POSITION LIMITS FOR FOUR-EIMP.0PERATION FROM 50 TO 200+ 10 48bl EFPD-ANO-1, CYCLE 5 3.5.2-lC.

R0D POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 200 + 10 48b2

~

T0~400.1 10 EFPD-ANO-1, CYCLE 5 3.5.2-1D -

. R0D POSITION LIMITS FOR FOUR-PUMP OPERATION FROT1100 + 10 48b3 TO 435 1;10 EFPD-ANO-1, CYCLE.5

-3.5.2-2A R0D POSITION LIMITS FOR THREE-PUf1P OPERATION FROM 0 TO 60 48c EFPD-Atl0-1, CYCLE 5 3.5.2-2B R00 POSITION LIMITS'FOR THREE-PUMP OPERATION FR0ft 50 TO 200

~

48c1 i(10 EFPD-ANO-1, CYCLE' 5

'3.5.2-2C R0D POSITION LIMITS FOR THREE-PUMP OPERATION FROM 200 + 10

~~

48c2 TO 400_ i 10 EFPD-ANO-1, CYCLE 5 3.5.2-2D-ROD POSITI0t! LIMITS FOR THREE-PUMP OPERATION FROM 400 + 1048c3.

~

.T0 435 +-10 EFPD-ANO-1, CYCLE 5 iy Amendment No.

52

. a' 3.5.2-2E R0D POSITION LIMITS FOR TWO-PUMP OPERATION FR3M 0 TO 60 ETPD-ANO-1, CYCLE 5 48c4 3.5.2-2F R00 POSITION LIMITS FOR TWO-eUMP OPERATI0fl FROM 50 TO 200 +-

48c5 10 EFPD-AN0-1, CYCLE 5 3.5.2-2G R0D POSITI0fl LIMITS FOR TWO-PUMP OPERATI0fl FR0f1200 + 10 TO 400 + 10 EFPD-Atl0-1, CYCLE 5 48c6 3.5.2-2H R0D POSITION LIMITS FOR TWO-PUMP OPERATION FROM 400 + 10 TO 435 + 10 EFPD-Atl0-1. CYCLE 5 48c7 3.5.2-3A' OPERATI0flAL POWER IMBALAtlCE ENVELOPE FOR OPERATION FROM 0 TO 60 EFPD-AN0-1, CYCLE 5 48d OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION FROM 50 TO 3.5.2-3B 200 + 10 EFPD-ANO-1, CYCLE 5 48dl 3.5.2-3C OPERATIONAL POWER IMBALAllCE EllVELOPE FOR OPERATION FROM 200 +-

48d2 10 TO 400 + 10 ' EFPD-ANO-1, CYCLE 5 3.5.2-3D OPERATIONAL POWER IPEALANCE ENVELOPE FOR OPERATION FROM 400 +-

48d3 10 TO 435 + 10 EFPD-Atl0-1, CYCLE 5 3.5.2-4 LOCA: LIMITED MAXIMUM ALLOWABLE LINEAR HEAT RATE 48e 3.5.2-4A ASPR POSITION LIMITS FOR OPERATION FROM 0 TO 60 EFPD-ANO-1, CYCLE 5 48f 3.5.2-4B ASPR POSITION LIMITS FOR OPERATION FROM 50 TO 200 + 10 EFPD-

~

ANO-1, CYCLE 5~~'

48g 3.5.2-4C APSR POSITION LIMITS FOR OPERATION FROM 200 + 10 TO 400 +-

48h 10 EFPD-ANO-1, CYCLE 5

~~

3.5.2-4C~

APSR POSITION LIMITS FOR OPERATWI FROM 400 + 10 TO 435 +-

481 10 EFPD-ANO-1, CYCLE 5 3.5-4-1 INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE INDICATION53a 3.5.4-2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT INDICATION 5?o 3.5.4-3 INCORE INSTRUMENTATION SPECIFICATION 53c 119 6.2-1 MANAGEMENT ORGAllIZATION CHART 6.2-2 FUNCTIONAL-0RGANIZATION FOR PLANT OPERATION 120 4

' Amendment No. 52 i

y e

DNBR of 1.3 corresponds to a 95 percent probability at a 95 percent confi-dence level that DNB will not occur; this is considered a conservative mar-gin to DNB for all operating conditions.

The difference between the actual core outlet pressure and the indicated reactor coolant system pressure has been considered in determining the core protection safety limits. The difference in these two pressures is nominally 45 psi; however, only a 30 psi drop was assumed in reducing the pressure trip set points to correspond to the clevated location where the pressure was actually measured.

The curve presented in Figure 2.1-1 represents the conditions at which a minimum DNBR of 1.3 is predicted.

1hc curve is the most restrictive com-hination of 3 and 4 pnp curves, and is based upon the maximum possible thermal power at 106.5% design flow per applicable pump status. This curve is based on the following nuclear power peaking factors (2) with potential fuel densification effects; F = 2.56; F

= 1.71; F = 1.50.

q AH z

These design limit power peaking factcrs are the most restrictive calculated at full power for the range from all control rods fully withdrawn to maximum allowable control rod insertion, and for the core DNBR design basis.

The curves of Figure 2.1-2 are based on the more restrictive of two thermal limits and include the effects of potential fuel densification:

1.

The 1.3 DNBR limit produced by a nuclear power peaking factor of FN = 2.56 or the combination of the radial peak, axial peak, l

and!hepositionoftheaxialpeakthatyieldsnolessthan 1.3 DNBR.

2.

The combination of radial and axial peaks that prevents central fuel melting at the hot spot. The limit is 20.1 kW/ft.

Power peaking is not a directly observable quantity, and therefore, limits have been established on the basis of the reactor power imbalance produced by the power peaking.

I The flow rates for curves 1. 2, and 3 of Figure 2.1-3 correspond to the ex-pected minimum flow rates with four pumps, three pumps, and one pump in each loop, respectively.

The curve of Figure 2.1-1 is the most restrictive of all possible reactor coolant pump maximo thernal power combinatiens shown in Figure 2.1-3.

The curves of Figure 2.1-3 represent the conditions at which a minimum DNilR of 1.3 is predicted at the maximum possible thermal power for the number of reactor coolant pumps in operation or the local quality at the point of mini-mum UNBR is equal to 22 percent (l), whichever condition is more restrictive.

Amendment No. 21, E2

i Usang a local quality limit cf 22 percent at the point of minimum DNBR as a ba.*as for curve 3 of Figure 2.1-3 is a conservat ive ers terion even though the qualtty at the exit as higher than the quality at the point of minimus Dh8R.

The DNBr. as calculated by the BAW-2 cor elation continually inerrsases from point of minimu:. Gi3R, so that the exi t DNBR is always higher and is a function of the pressure.

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 applicable cycle minus a credit of 1% for the flow area reduction f actor used in the hot channel analysis. All plant operating limits are presently based on an original method (3) of calculating rod bowing penalties that are more conservative than those that would be obtained with new approved procedures (4).

For the current cycle of operation, this sub-rogation results in a DNBR margin in excess of 3.8", which is partially used to offset the reduction in DNBR due to fuel rod bowing.

The maximum thermal power for three-pump operation is 86.42 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 instru=entation error.

The maximum thermal power for other reactor coolant pump conditions is pro-duced in a similar manner.

For each curve of F1;ure 2.1-3, a pres sure-temperature point abece and to the left of the. curve would result in a DNBR greater than 1.3 or a locas quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation.

Curves 16 2 of Figure 2.1-3 are the most restrictive because any pressure / temperature point above and to the left of this curve will be above and to the left of the other curve.

RIFE RINCES (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized water, BAW-10000A, May, 1976.

(2) FSAR, Sect i on 3. 2. 3.1.1.c (3)

D. F. Ross and D. G. Eisenhut (NRC) memorandum to D. B. Vassallo and K. R. Goller (NRC) on " Interim Safety Evaluation Paport on the Ef fects of Fuel Rod Bowing on Thermal Fbrgin Calculations for Light Water Reactors" dated December 8,1976.

(4)

L. S. Rubenstein (NRC) letter to J. H. Taylor (B&W) on " Evaluation of Interim Procedure for Calculating DNBR Reduction Due to Rod Bow" da ted October 18, 1979.

I Amendment No.JM)r,g 52 9

9 4

Core Protection Safety Limits (Tech Spec Figure 2.1-2)

POWER. @R, %

(

'4*

i }

M2

-0.77 I'20*00'I12}

II2 N - 9.66 ACCEPTABLE l4 PUMP l

(-45,100) lCPERATicii

- - 100 1

(38,100)

I I

i 8

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l l

86.42 l

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g ACCEPTABLE 80 I

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8 l 3 8 4 PUME

(-45,74.42) l OPERATION (30s74.42)

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60 s

59.74 l

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ACCEPTABLE g

I 2, 3, 8 4 PUNP l

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(30,47.I4)

(-45,47.14) i OPERATION l

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i 40 e

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UNACCEPTABLE l

l UNACCEPTABLE i

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OPERATION I

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REACTOR POWER INBALANCE be %

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Amendment flo.,QMJTM 52 9b Babcock & Wilcox

4 The power level trip setpoint produced by the power-to-flow ratio p

{

provides both high power level and low flow protection in the event the reactor power level increases or the reactor coolant flev rate l

decreases. The power level trip setpoint produced by the power-to-l flow ratio provides overpower'DNB protection for all modes of pump f

operation. For every flow rate there is a maximum permissible power

[

level, and for every power level there is a minimum permissible low i

flow rate. Typical 4;wer level and low flow rate combinations for the pump situations sf Table 2.3-1 are as follows:

i T

L 1.- Trip would occur when four reactor coolant pumps are operating if l

power is 107 percent and reactor flow rate is 100 percent or flow rate is 93.45 percent and power level is 100 percent.

2.

Trip would occur when three reactor coolant pumps are operating i

if power is 79.92 percent and reactor flow rate is 74.7 percent or flow rate is 70.09 percent and power level is 75 percent.

j i

1 3.

Trip would occur when one reactor coolant pump is operating in each loop.(total of two pumps operating) if the power is 52.64 i.

i percanc and reactor flow rate is 49.2 percent or flow rate is j

45.79 percent and tb power level is 49.0 percent.

7 The flux / flow ratios account for the maximum calibration and instrumentation.

. errors'and the maximum variation from the average value of the RC flow signal i

in'such a manner that the reactor protective system receives a conservative l

i indication of the RC flow..

t No' penalty 71n reactor coolant flow through the core was taken for an open core vent valve because of the core vent valve surveillance program during ca.h refueling outage. For safety analysis calculations the maximum calibra-tion and instrumentation errors for the power level were used.

[

1The power-imbalance. boundaries'are established in order to prevent reactor L

thermal. limits fron'being exceeded.

These thermal limits are either power l

l peaking kW/f t, limits 1 or DNBR limits. - The reactor power ' imbalance (power in top. hisif of! core minus ' power in bottom half of core) reduces the power level

' trip produced by the power-to-flow ratio so that the boundaries of Figure

~

r

.,The power-to-flow ratio reduces the power level trip

.2.'3-2 are produced.

associated with~ reactor power-to-reactor power imbalance boundaries by 1.07 l

h percent for.a ILpercent flow reduction.

/

B.

Pump Monitors i

In conjunction'wich the power imbalance / flow trip, 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 pump.

~

l monitors also restrict:the power level'for the number'of pumps in v

[-

operation;

'C; 1RCS Pressure-During a startup accident from low power or a slow rod withdrawal s

. from high power, the system high-pressure. trip setpoint' is reached '

before?the nuclear overpower trip setpoint. The trip settingL11mit Babcock &Wilcox TAmendmentuNo M M M.

52g 12:

1

,a, ya.-

>~&-

~-

Protective System Maximu:n Allowable Setpoints l

l (Tech Spec Figure 2.3-2)

POWER, & %

EA 120 (11.107)

(-15.5.107) 107 i

N2 = -0.92 Mg = 0.83 ACCErYABLE gl I

(24.95)

(-30,95)

',0PERATiOM I

g g

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79.92 80 l

I ACCEPTABLE l

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(-30,67.92) 10rERATION i

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l 60 l

~

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t i

'i2 64 l

ACCEPTA BL E 3

l l

l l

2. 3 & 4 1

40 l (24.40.64)

(-30,40.64)

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I l0PERATiON g

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UNACCEPTABLE l

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OPERA 710N UNACCEPTABLE l~

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OPERATION

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20 40 60 POWER IMBALANCE, %

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l Amendment No.,EQ f, g d 52 14b Babcock a Wilcox

N 2

ct Reactor Protection System Trip Setting Limits S

(Specifictions Table 2.3-1) s

a 6

Four RC pumps operating Three RC pumps operating One RC pump operating in (nominal operating (nominal operating each loop (nominal Shutdown power, 100%)

power, 75%)

operatina power, 49%)

bypass Nuclear power. % of 105.5 105.5 105.5 5.0" rated, max Nuclear power based on 1.07 times flow minus 1.07 times flow minus 1.07 times flow minus Bypassed b

flow.and imbalance. I reduction due to in-reduction due to im-reduction due to in-of rated, men balance (s) balance (s) balance (s)

Nuclear power based on NA NA 55 Bypassed p ep monitors, % of l

rated, mex*

Migh RC system pressure, 2300 2300 2300 1720*

pois, max Low RC system Rressure, 1800 1800 1800 Bypassed pois, min 4

d d

d Variable low RC system 11.75 T,,g - 5103 11.75 T,,g - 5103 11.75 T,,g - 5103 Bypassed pressure, poig, min RC temp, F, max 619 619 619 619 High reactor building 4(18.7 psia) 4(18.7 psia) 4(18.7 psia) 4(18.7 pois) pressure, poig, max

• Automatically set when other seRments of the RPS (as specified) are bypassed.

Reactor coolant system flow.

"The pump monitors also produce a trip on (a) loss of two RC rumps in one RC loop, and (b) loss of one or two RC pumps during 8

two-pump operation.

d p.

T is given in degrees Fahrenheit (F).

&E o*

s

$:ininici volunes (including a 10'. ssfety (scror) as specified by Figure 3.2 1 for the horic seid addition tar.1 or 44,549 gallor.s of 2270 ppm boron as boric acid solution in thc borated water storage tank (31 will each satisfy this requirement. The speca facatton assures that adequate supgilies are available whenever the resetor is bested shove 200 F so thst a single (silure will not prevent borstion to a cold condition. The minimum volumes of boric acid solu-tion given include the boron necessary to account for xenon decay.

The principal method of sdding boron to the prim.ary system is to pump the con-centrated boric acid solution (8700 ppm boron, minimum) into the makeup tank using the 25 gpm boric seid pumps.

The alternate method of addition is to inject boric scid from the boro-ated water stursge tank using the makeup pumps.

Concentration of boron in the boric acid addition tank may be higher than the concentration which would crystalli:.. at ambient conditions.

For this reason and to assure a flow of boric acid is available when needed this tank and its 0

associated piping will be kept 10 r sliove the crystallization tempersture for the concentration present. Once in the makeup system, the concentrate is suffi-ciently well mixed and diluted 50 that normal system temperatures assure boric acid solubility.

REFERENCES (1)

FSAR, Section 9.1; 9.2 (2)

FSAR, Figure 6-2 (3)

FSAR, Section 3.3

- Amendment flo. gg '52 35

. = -

Boric Acid Addition Tank Volume and Requirements Vs RCS Average Temperature (Tech Spec Figure 3.2-1) 6000 lll2 GAL 8700 PPM 8 OPERATION ABOVE AND TO 9500 PPMB THE LEFT OF THE CURVES Is ACCEPTABLE 5000 lillGAt

i 12000 PPMB 4000 hhh3 GAL

/

W

/

3

/!hbGAL E

/

2h6 GAL

~

j 3000

• 500F

/

287')G AL e

=

f hhhGAL

/

2

/

2000 400F I

/

1673 GAL

/

300F

/

1000 974 GAL

/ 300F

/

698 GAL

/

/

1 1

f 200 300 400 500 600 RCS AVERAGE TEMPERATURE (F)

Babcock &Wilcox Amendnent llo. g 52 35a m

v

+,w

,..m v-

=

3.

Except for physics tests or exercising control rods, (a) the con-trol rod withdrawal limits are specified on Figures 3.5.2-1A, 3.5.2-1B, 3.5.2-1C, and 3.5.2-1D for four-pump operation, on Fig-ures 3.5.2-2A, 3.5.2-2B, 3.5.2-2C, and 3.5.2-2D for three-pu=p op-l eration, and on Figures 3.5.2-2E, 3.5.2-2F. 3.5.2-20, and 3.5.2-2H for two-pump operation; and (b) the axial power shaping control rod withdrawal limits are specified on Figures 3.5.2-4A, 3.5.2-45, 3.5.2-4C, and 3.5.2-4D.

If any of these control rod position lim-its are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod posi-#on. Acceptable control rod positions shall be attained within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4 Except for physics tests, power shall not be increased above the power level cut-off of 92% of the maxi =um allowable power level unless one of the following conditions is satisfied:

Xenon reactivity is within 10% of the equilibrium value for a.

operation at the maximum allowable power level and asymptot-ically approaching stability.

b.

Except for xenon free startup, when 3.5.2.5.4a applies, the reactor has operated within a range _ of 87 to 92% of the maxi-mum allowable 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 />.

3.5.2.6 Reactor Power 1mbalance shall be monitored on a frequency not to ex-ceed 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 40% rated power.

Except for physics tests, imbalance shall be maintained within the envelopes defined'by Figures 3.5.2-3A, 3.5.2-3B, 3.5.2-3C, and 3.5.2-3D.

If the imbalance is not within the envelopes defined by Figures 3.5.2-3A, 3.5.2-35, 3.5.2-3C, me? 3.5.2-3D, corrective measures shall be taken to achieve an acceptable imbalance.

If an acceptable imbalance is not achieved within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, reactor power shall be reduced until imbal-ance 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, 3.5.2-3C, and 3.5.2-3D are baseC on (1) LOCA analyses which have defined the maximum linear _ heat rate (see 1-gure 3.5.2-4) such that the maximum cladding tempera-ture will' not exceed the Final Acceptance Criteria and (2) the Protective Sys-tem Maxista Allowable Setpoints (Figure 2.3-2).

Corrective measures will be taken immediately should the indicated quadrant tilt', rod position, or imbal-ance be outside their specified boundaries.. 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 (quad-rant tilt, rod position. _ and -imbalance) must be at their ~ limits while 2 Amendment fio. f,% g g 52-4g Babcock &WilC0%

O sioultaneously all other engineering and uncertainty factors are also at their linits.* Conservatism is 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 20 15% overlap between successive control rod groups is allowed since the worth of a rod is lower at the upper and lower parts of the stroke.

Control 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

Regulating 8

APSR (axial power shaping bank)

The rod position limits are based on the most limiting of the following three criteria: ECCS power peaking, shutdown margin, and potential ejected rod worth. As discussed above, compliance with the ECCS power peaking criterion is ensured by the rod position limits. The minimum available rod worth, con-sistent with the rod position limits, provides for achieving hot shutdown by reactor trip at any tice, assuming the highest worth control rod that is wit-drawn remains in the full-out position (1).

The rod position limits also that inserted rod groups will not contain single rod worths greater ensure than 0.65% Ak/k at rated power. These values have been shown to be safe by the safety analysis (2) of the hypothetical rod ejection accident. A maximum single inserted control rod worth of 1.0% Ak/k is allowed by the rod position limits at hot zero power. A single inserted control rod worth of 1.0% ok/k at beginning of life, hot zero power, would result in a Icwer 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 20%. The normal position at power is for groups 6 and 7 to be partially inserted.

• 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 opera *.ing limits is defined in plant operating procedures.

Amendment No. 52

-48a Babcock &)Milcox s

?

r The quadrant power tilt limits set forth in Specification 3.5.2.4 have been established within the thermal analysis design base using the definition of quadrant power tilt given in Technical Specificationr, Section 1.6.

These limits, in conjunction with the control rod position limits in Specification 3.5.2.5.3, ensure that design rank heat rate criteria are not exceeded during normal operation when including the effects of potential fuel densification.

The quadrant tilt and axial imbalance monitoring in Specifications 3.5.2.4.4 and 3.5.2.6, respectively, will normally be performed in the plant computer.

The 2-hour frequency for monitoring these quantities will pro

• ride adequate surveillance when the computer is out of service.

During the physics testing program, the high flux trip setpoints are adninistra-tively set as follows to ensure that an additional safety margin is provided:

Bakock & Mcox M Dd*)Cnt ll0.52 48al i

e-g

-e-p",s r-r--any

Rod Position 1.imits for Four-Pump Operatton l

From 0 to 60 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-1A) 110

('I'UE)

100 SHUTOOWN I

U OU 90 MARGIN (271.92; LIMIT i

80 (258.80)

OPEFATION IN l

70 TH S REGION E

15 NOT RESTRICTED ALLONEO REGION g

60

~

I 8E E

50 (67.50 (175 50) a OPERATING REGION g

40 J'

30 20

( 0.13 )

10 (0,0) 0 O

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300

,0 2,0 4,0 60

{010p GROUP 7 0

10 4p 6,0 8Q 10Q GROUP 6 0

20 40 80 100 t

f t

GROUP 5 Rod index. % WO Amendment No MF8.F.52 48b Babcock a.Wilcox

Rod Position Limits for Four-Pump Operation From 50 to 200 1 10 EFPD - ANO-1 Cycle 5 (Tech Spec Figure 3.5.2-1B) 110 (134.102)

(271,102)o SHUT 00WN POWER LEVEL (271,92)

MARGIN 90 CUT 0FF LIMIT 80 (258.80)

OPERATION IN 70 THIS REGION l$ NOT RESTRICTED E

ALLOWE0 REGION 60 PERMISSIBLE g

OPERATING g

REGION (175,50) l g

50 (67,50) a p

40

.e 30 20

( 0.13 )

10 lbo 120 10 160 180 200 220 240 250 250 Ju0 (0, )'O 2b 40 6O BO

,0 2p 40 6,0 8p 10p GROUP 7 0,

2,0 40 60 8,0 10,0 0

20 40 80 100 I

f f

i f

GROUP 5 Rod index. % WO l

-l Amendnent No.J4,W,g, 52 48bl Babcock s.Wilcox

Rod Position Limits for Four-Pump Operati'an From 200 2 10 to 400 t 10 EFFD - A50-1. Cycle, 5 (Tech Spec Figure 3.5.2-1C) 110 (271.102)

(215.102) o 100 P08ER LEVEL CUTOFF i

90 SHUTOOWN N

1, 2; RESTRICIED REGION (258,80) 80 OPERATION IN Ells REGION 70 IS NOT (240.70) y ALLOWED g 60 C

- 50 (156.50)

(175,50)

PE;MISSIBLE OPERATING

,w REGION 43

e 30 20 (0.e.a

(,3,,3) iO,

0 1

I I

t 1

e e

t t

t t

(

20 40 50 50 100 120 140 160 180 200 220 240 260 260 300

,0

{0 40 q0 8.0 10,0 GROUP 7 4

29 49 10 89 190 0

20 40 80 100 GROUP 6 I

I i

I

- _I i

GROUP 5 Roo inder, % WO l

l l

l l

AmendmentNo.[.JMg,52 48b2 Babcock & Wilcox

[

i

=

o Rod Position Limits for Four-Pump Operatien From 400 2 10 to 435 2 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-ID) 110 (220,102)

(283.102) 100 RESTRICTED SHUTDOWN REGION 279.92 POBER LEVEL 90 ugpgp 80 (238.10) 70 OPERAiloh IN g

THis REGION

'S "0I

= 60 ALLOWED 3

n

50 (156,50 (175.50)

PERWISSIBLE OPERATING 40 REGION j

30 20 (83.15)

(0,8.9) 10 (80.0) 0 O

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 9

40 f0 go q0 190 GROUP 7 9

29 4p (0

qo 190 GROUP 6 0

70 40

$0 IQ0 GROUP $

a a Index, % to c

Babcock & Wilcox Amendment tio. 52 48h3

N Rod Position Limits for Three-Pump Operation From 0 to 60 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-2A) 110 100 90 1.

80 SHUTOOWN (134,77) i (250,77)

MARGIN LIMIT 70

- OPERAil0N IN TNis REGION RESTRICTED h 60 IS NOT REGION ALLOWED

.3 50 (175,50) a PERMISSIBLE OPERATING

, 40 (6 7

• 3 8 ')

REGION

$ 30 20 0,10)'

0 O

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 p

2p 4,0 s,0 8p iq0 GROUP 7 l

l 0

2p 40 6,0 8,0 10,0 l

GROUP 6 0

2,0 4,0 8,0 10,0 GROUP 5 Roa Inoex, % WO

+

Amendment'Ho.jd,g,ff,52 48c Babcock &Wilcox

Rod Position Limits for Three-Pump Operation From 50 to 200 2 10 EFPD - ANO-1. Cycle 5 (Tech Spec Figure 3.5.2-2B) 110 100 90 80 SHUTDOWN (134.77)

(250,77)

MARG lN 70 OPERATION IN LIMIT E

THIS REGION RESTRICTED 60 IS NOT REGION

=

ALLOWED

50 (175,50)

PERMISSIBLE OPERATING

,= 40 (67,38)

REGION j

30 20 l

10 <

(0.10 l

0, 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0

2,0 40 6,0 8p ig0 GROUP 7 0

2,0 40 6,0 8,0 10,0 GROUP 6 l

0 20 40 100 t

i e

i l

GROUP 5 Rod Index, % 110 l

l l

Amendment No. Jg,g,g, 52 48cl Babcock s.Wilcox t

~

/

Rod Position Limits for Three-Pump Operation From 200 1 10 to 400 ! 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-2C) 110 100 90 Restricted Region 80 j

OPERATION IN r

70 THit RFGION SHUTOOWN (240,70)

C IS NOT MARGIN 5

60 ALLOWE0 LIMl7 8

m 50 x

PERMISSIBLE 40 (156.38)

OPERATING REGION

=

l 30 i

l l

20 (83.11) 10 (0. 7 )

0 i

t i

i i

(

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300

,0 2,0 40 60 8,0 10,0 GROUP 7 0

KO 49 40 8,0 1p0 GROUP 6 0

20 40 100 e

e i

f GROUP 5 Rod index, % WO 1

AmendmentNo.)

% 52 48c2 Babcock & Wilcox

Rod Position Limits for Three-Pump Operation From 400 i 10 to 435 1 10 EFPD - Ah0-1. Cycle 5 (Tech Spec Figure 3.5.2-2D) 110 100 0

Restricted Region (220.77) y (232.77) 70 SHUTOOWN P

MARGIN 0

Lllili 60 OPERATION IN I

E THIS REGION R

50 IS NOT ALLORED 40 (156.38)

PFRNISSIBLE OPERATING 30 REGION 20 10 (83.11 )

l 0

e r

0 20 4C 60 80 100 120 140 ISO 180 200 220 240 260 280 303 Roa inder. % 50

(

20 4,0 6,0 8,0 100 GROUP 7 0

20 4,0 60 80, 100 j

I f

f f

i GROUP G

,0 2,0 4,0 60 80 100 GROUP 5 l

l5 l

/

~

Amendment No. 52

'48c?

Rod Position Limits for Two-Pump Operation From 0 to 60 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-2E) 110 100 90 80 70 C"

60

~

OPERATION IN ShUTOOWN (134.52)

(182.52) iP.!S REGION MARGIN 50 IS NOT

. LIMIT at ALLOWED 40 PERMISSIBLE 30 (67.26)

OPERATING REGION 20 - (0. 7) 10 i

e i

e 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0,

2,0 j0 6,0 8,0 10,0 GROUP 7 0

20 4,0 6,0 8,0 10,0 GROUP 6 6, - 80 10p 0

0 2,0 40 GROUP 5 R00 incts % RO

/

/

F Amendment No.52 48c4 Babcock s Wilcox

Rod Position Limits for Two-Pump Operatfor From 50 to 200 2 10 EFPD - ANO-1. Cycle 5 (Tech Spec Figure 3.5.2-2F) 110 100 90 80 4

70 E

60 0

(134.52)

- 50 OPERATION IN SHUTOOWN (182.52)

THIS REGION MARGIN IS NOT llMli f 40 ALLOWED E

PERMISSIBLE 30 (67.26)

OPERATING 20 REGION 10 (0.7) 1 (0,0) 0 '

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0,

20 4,0 6,0 BQ 1,00 GROUP 7 0,

2,0 40 SQ 8,0 10,0 GROUP 6 0

20 40 80 100 t

t t

t a

GROUP 5 Roo Index % WD g

i Amendment No. 52 48c5 Babcock 4.Wilcox

)

Rod Position Limits for Two-Pump Operation From 200 t 10 to 400 1 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-2G) 110 100 90 80 70

.~

E 60 g

R OPERATION IN SHUTCOWN (215.52)

E 50 THIS REGION NARGIN IS NOT LIMIT u

ALL0nED t

40

~

PERMISSIBLE 5

OPERATING 30 (156.26)

REGION l

20 l

10

-(0.5)

_ (83,83 a

0 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Q

2,0 4p 40 40 100 0

20 4,0 6,0 8,0 100 0

20 40 80 100 GROUP 6 I

1 GROUP 5 R00 Index, % to I

1 I

l l

l Babcock & Wilcox Amendment tio. 52 48c6

. ~ -

Rod Position Limits for Two-Pump Operation From 400 10 to 4351 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-2H) 110 100 90 80

.{

70 5

0 60 1

n 50 SHUTOOWN MARGIN 40 OPERATION IN LIMIT THIS REGION IS NOT 30 ALLOWE0 (156.26)

PERMISSIBLE 20 OPERATING 10 - (0,5)

_ (g3,g) 4 0

i i

i i

I i

e i

i i

i i

i i

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300

,0 2,0 40 6g go Iq0 GROUP 7

,0 2p 4p go go 10,0 GROUP 6 g

20 4p 1,00 GROUP 5 Rod index, % WD Amendnent No. 52 48c7 Babcock & Wilcox

t.

4 Operational Power Imbalance Envelope for Operation From 0 to 60 ETPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-3A)

. 110 o (25.102)

(-18,102)g

, igg

( 5,92)

(-19,92) 90

(-26,80) 80 (32,80)

PERMISSIBl.E RESTRICTED RESTRICTED OPERATING REGION REGION REGION 60

.. 50 g- - 40 x

5g- - 30 20 at -

5 E- - 10 i

a e

I I

I e

I i

-40

-30

-20

-10 0

10 20 30 40 Axial Power imoalance, %

48d Babcock & Wilcox AmendmentNo.%K,%52

Operational Power Imbalance Envelope for Operation From 50 to 200 2 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-3B)

- 110

(-24.102) c 100 o ( 5.102)

(25.92)

(-24.92)

.. 90

(-34.80)

. 80 (32.80)

PERillSSIBLE OPERATING RESTRICTED RESTRICTED REGION REGION REGION

-- 60

- - 50

- - 40 E

3 - - 30 N

g-20 M

.$ - - 10 l.

E a.

I I

I I

l f

f f

f

-40

-30

-20

-10 0

10 20 30 40 Axial Power imcalance %

I i

l e

Amendment No. p (,K,g, 52 48d1 Babcock 4 Wilcox

I Operational Power Imbalance Envelope for Operation From 200 1 10 to 400 ! 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-3C) 110

(-19,102) 0 00

(-23,92)

(25,92)

(-32,80 80 (32,80)

PERMISSIBLE OPERATING RESTRICTED RESTRICTED REGION REGION REGION 60 50

- - 40 K

- 30 g-2 5- - 20 a

f- - 10 e

i I

I I

I t

j t

-40

-30

-20 0 10 20 30 40 Axial Power imoalance %

l Babcock 8.Wilcox AmendmentNo.JI,/,g,52 48d2

Operational Powe.- Imbalance Envelope for Operation From 400 1 10 to 435,2 10 EFFD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-3D) 110

(-16.102)

C

.. 100 (16,92)

(-16,92) 90

(-32,80) 80 (24,80)

PERWISSIBLE RESTRICTED RESTRICTED OPERATING REGION REGION REGION BD 50 40 E

=

g-30 0

5-20 x

10 E

1 9

i e

I e

I f

-40

-30

-20

-10 0

10 20 30 40 Axial Power imbalance %

Amenchent No. 52 ~

48d3 B&d Wilm i

LOCA Limited Maximum Allowable Linear IIcat Rate (Tech Spec Figure 3.'5.2.4) 21 20 0

19 N

e 18 k

[

BALANCE OF CYCLE cc l"

jf 2

16

=

FIRST 50 EFPD s

/

i

/

=

E 14 13 12 0

2 4

6 8

10 12 Axial Location of Peak Power from Bottom of Core, ft I

Amendnent No J,52 48e Babcock & Wilcox t'

(.

APSR Position Limits for Operation From 0 to 60 EFFD - ANO-1. Cycle 5 (Tech Spec Figure 3.5.2-4A) 110 i

(2,102)

(41,102) 00 RESTRICTED

('

90 d>

-80 (0.80) 70 E

PERMISSIBLE 60 OPERATING g

R REGION E

50 (100.50) x 40 2

30 20 10 i

0 i

O 10 20 30 40 50 60 70 80 90 100

% Withdrawn AmendmentNo.g,52-48f Babcock 8.Wilcox

l l

APSR Position Limits for Operation From 50 to 200 ! 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-4B) 110 (9,102) 100 RESTRICTED

• I'

}

REGION 90 (41,80) gg (0,80) 4 70 C

=

60 FERMISSIBLE

=

OPERATING REGION 50 (100,50) o te y

40 J'

30 20 10 0

i i

i 0

10 20 30 40 50 60 70 80 90 100 l

% Withdrawn l

l Amendment No.%,pf 52 48g Babcock 4 Wilcox i

l APSR Position Limits for Operation From 200 2 10 to 400 1 10 EFPD ~ ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-4C) 110 (13.5.102)

. (41,102) 100 RESTRICTED (13.5.92)

REG 10H 90 (41,80)

(0,80) t 80 i

70 (100,70)

~

E PERMISSIBLE gg g

OPERATING g

REGION 50 a

d 40 E

o 30 20 10 0

2 30 40 50 60 70 80 90 100

% Wit.norawn s

Babcock s.Wilcox

- Amendment No. JI,34 52 48h

APSR Position Limits for Operation From 400 2 10 to 435 2 10 EFPD - ANO-1, Cycle 5 (Tech Spec Figure 3.5.2-4D) 110 100 90 80 70 APSR INSERTION NOT ALLOWED IN THIS TIME INTERVAL jf 6 0 E

~

50 de -

40 5

x 30 20 10 0

l 0

10 20 30 40 50 60 70 80 90 100 APSR, % Withdrawn Amendment No. 52' 481 Babcock & Wilcox I

.