Text

Core Operating Limits Rept,Palo Verde Nuclear Station,Unit 1,Cycle 3
	ML20091A497
Person / Time
Site:	Palo Verde
Issue date:	03/19/1992
From:	; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
Shared Package
ML17306A600	List: ML17306A601; ML17306A602; ML17306A604; ML20091A497;
References
	NUDOCS 9203270202
	Download: ML20091A497 (23)
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iE CORE OPERAIING LIMITS REPORT f

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

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FOR INFORMATION ONLY 3/4.2 POWER DISTRIBUTION LIMITS 3/4 2.1 LINEAR HEAT RATE i

LIMITING CONDITION FOR OPERATION f p s,' m b ;~ h. c y.o epse r t3 uwm w.sech 3.2.1 The linear heat rate limi the following methods as applicable: 10.5 k"/f t-shall be maintained by one of COLSS calculated power operating limit base a.

(when COLSS is in service); or b.

Maintaining peak linear heat rate within its limit using any operable CPC channel (when COLSS is out of service).

APPLICABILIly_: MODE 1 above 20% of RATED TrlERMAL POWER.

ACTION:

With the linear heat rate limit not being maintained, as indicated b y:

1.

COLSS calculated core power exceeding the COL 55 calculated c power operating limit based on linear heat rate; or 2.

channel (when COLSS is out of service); Peak linear within the limits and either:within 15 minutes initiate corrective action rate to Restore the linear heat rate to' within its limits within a.

, or b.

Reduce THERMAL POWER to less than or equal to 20% of RA POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

JURVEILLANCE REQUIREMENTS 4.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.1.2 THERMAL POWER is above 20% of RATED 1PERM the core power distribution with the Core Operating Limit Superviso l

onitoring (CCLS5) or, with the COLSS out of service, by verifying at least o ry System 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that the linear heat rate, as indicated en any OPERABLE Local nce per Density channel, is within its limit.

wer 4.2.1.3 actuate at a THERMAL PUWER level less than or limit based on linear heat rate.

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PALU M DE - UNIT 3 3/4 2-1 AMENOMENT NO. 18 9

CONTROLLED BY USER POWER DISTRIBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - T LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the following limits:

9 The AZIMUTHAL. POWER TILT Allowance used in the Core Protection a.

Calculators (CPCs), and.

Csn.o A A s

% <. e cmwrr g u:

u.s b.1. The lim t in TTgure.s.z-3A with COL 55 in serNeiq.s pM A

b.2. Tq 3, 0.10 with C0LSS out of service.

APPLICABILITY:

MODE I above 20% of RATED THERMAL POWER

ACTION:

With the measured AZIMUTHAL n0WER TIll determined to exceed the a.

AZlMUTHAL POWER TILT Allowance used in the CPCs within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value, b.

With the measured AZIMUTHAL POWER TILT determined to exceed the limit,i-Ii;w c :.1' A with COLS5 in service or 0.10 with COLSS out of service. T 3 pc. u k h.,c.o u epg % n g u % u p g 1.

E'ue to misalignment of either a cart-length or full-length CEA,-

within 30 minutes verify that the Core Operating Limit Supervisory System (COL 55) (when COLSS is being used to monitor the core power distribution per Specifications 4.2.1 and 4.2.4) is 3

detecting the CEA misalignment.

2.

Verify that the AZIMUTHAL _ POWER TILT is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months af ter exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and verify that the Variable Overpower Trip 5etonint has been reduced as appropriate within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHA! POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED THERMAL POWER.

See Special Test Exception 3.10.2.

PALO VERDE - UNIT 3 3/4 2-3 AMENDMENT NO. D

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FOR INFORMATION ONLY N

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v5 THERMAL POWER (COL 55 IN SERVICE)

PALO VERDE

' NIT 3 J

3/4 2-4a AMEN 0HENT NO.18

FOR INFORMATION ONLY POWER DISTRIisVTION LfMfTS 3/4.2.4 DNBR MARGIN

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_LIMI_ TING CONDITION FOR OPERATION 3.2.4 The DNBR margin shall be maintained by one of the.following methods:

Maintaining COLSS calculated core power -less than or equal to COLSS a.

calculated core power operating limit based on DNBR (when COLSS is in service, and either one or ooth CEACs are operable): or a, R h. w M. E h re n. a c3 u % s T s M Po u -l b.

Maintainin

> calculated core ~ power.less than or equal to COLSS calculated ore power operating limit based on DNBR decreased by the allowanceg:h:rir,fign;3.21-(whenCOLSSisinserviceandneither CEAC is operable); or Operating within the region'of acceptable operatioP ' Fig =:

c.

using any operable CPC channel

_ 3. 2 either one or both CEACs are ope (when COLSS is out oIservice and 4

rable); or Operating within the regiFn of acceptable operationI:f Fign; 2 d.

usinganyoperableCPCchannel(whenCOLSSisoutoIserviceand neither CEAC is operable).

APPLICABILITY: MODE 1 above 20% of RATED THERHAL POWER.

ACTION:

With the DNBR not being maintained:

1.

As indicated by COLSS calculated core power exceeding the appropriate COLSS calculated power operating limit; or 2.

With COLSS out of service, operation outside the region of acceptable operatio f Figr: 3.2-2 :r 2.2-2A, n 19p11:210;-

within15 minutes _g,ne s

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h.h k N. c.cm.

ci9e w vz w g % t s M pe w the limits and either: initiate corrective action to increase the DNBR to within Restore the DNBR to within its limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or a.

b.

Reduce THERMAL POWER to less than or equal to 20% of RATED THi? MAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.4.1 The provisions of Specification 4.0.4 are not applicable.

4.2.4.2 POWER is above 20% of RATED THERMAL-POWER by co core pcwer distribution with the Core Operating Limit Supervisory System (COLSS)-or, with the COLSS out of service, by verifying at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that the DNBR, as indicate 1 on any_0PERABLE-DNBR channel, is within the 1imit#e" en C!gre 2.2-2 er F!ge

%psd 2.2-2A At least once pe/.a A L unblSS Margin Alarm shall be verified--

4.2.4.3 r 31 days, the C o9 % rrwe,ucw.-r.rs R59=ar to actuate at a THERMAL POWER level less than or equal to the core power operating limit _ based on DNBR.

PALO VERDE - UNIT 3 3/4 2-5 AMEMDMENT HO.18 u-.

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FIGURE 3.2 COL 55 DNBR POWER OPERATING LIMIT LLOVANCE FOR BOTH CEACs INOPERABL'E PALO VERDE - UNIT 3 3/4 2-6 AMENDMENT-HG. 10 i

FOR INFORMATION ONLY COLSS OUT OF SERVICE DNBR LIMIT LINE 2.

1 I

i 2.4 ACCEPTABLE OPERATION 2.3 NIMUM 1 CEAC OPERABLE c:

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-0.1 0.0 0.1 0.2 Oh CORE AVERAGE ASI FIGURE 3.2 2 DNBR M ARGIN OPERATING LIMIT B ASED ON CORE PROHCTION CALCULATORS 1

(COLSS OUT OF SERVICE CEACs OPERABLE)

PALO VERDE UNIT 3 3/4 2-7 AMENDMENT NO.26 t

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FOR INFORMATION ONLY

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i COLSS OUT OF SERVICE DNBR LIMIT LIN3 2

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CORE AVERAGE ASI 4

FIGURE 3.2-2A DNBR MARGIN OPERATING LIMIT B ASED ON CORE PROTECTION CALCULA (COLSS OUT OF SERVICE, CEACs INOPERABLE) l PALO VERDE - UN!T 3 3/4 2-7a AMENDMENT NO. 26 t'.

s

FOR INFORMATION ONLY POWER DISTRIBUTION LIMITS 3/4.2.5 RCS FLOW RATE i

LIMIP.'@ CONDITION FOR OPERATION 3.2.5 The actual Reactor Coolant :ystem total flow rate shall be. greater than or equal to 155.8 x 108 lbm/hr.

APPLICABILITY: MODE 1.

l ACTION:

Vith the actual Reactor Coolant System total flow rate s

POWER within the next 4 hcurs.

_ SURVEILLANCE REQUIREMENTS 4.2.5 to be greater than or equal to its limit Lat least once per 12 h i

PALO VERDE - UNIT 3 4

3/4 2SR AMENOMENT NO.18 s

CONTROLLED BY USER POWER DISTRIBUTION LIMITS

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3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE-LIMITING CONDITION FOR OPERATION 3.2.6 The reactor coolant cold leg temperature (T ) shall be within the Area-of Acceptable Operation shown in Figure L 2.3.-

c APPLICAEILITY: MODES 1* and 2*#.

ACTION:

With the reactor coolant cold leg temperature exceeding its limit, restore the temperature to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SlANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i SURVEILLANCE REQU.fREMENTS 4.2.6 The.reat: tor coolant cold leg temperature shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

s 1

See Special Test Exception 3.10.4

With K,ff greater than or equal to 1

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t PALO VERDE - UNIT 3 3/42-1l

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CONTROLLED BY USER t

580 i

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575 u.,

570 570 o

568 568 g

AREA OF ACCEPTABLE

{560 g f

562 OPERATION 555 550 552 1

540

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10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL, % OF R ATED THERMAL POWER A

FIGURE 3.2-%-

REACTOR COOLANT COLO LEG TEMPERATURE VS. CORE POWER LEVEL i

d s

i PALO VERDE - UNIT 3

/42-M

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_______________-__E_J

FOR INFORMATION ONLY POWER DISTRIBUTION LIMITS 3/4.2.7 AXIAL SHAPE INDEX LIMITINGCONDITIONFOROPERATION 3.2.7 The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the

- felleeig-limitsg spg g. g 6 h t.e,g ope %NcT. hrn MPoW.

COLSS OPER^0LE

-0.27 5 ^. S.27

=b.

00LSS OUT OF SEP" ICE-(EPC) _

"Or2O 5 ASI 5 0.20 APPLICABILITY:

MODE 1 above 20% of RATED THERMAL POWER *.

ACTION:

g y m % % m s ope w Tr a og t.r uxT s u po.g.

N No.

With the core avarage AXIAL SHAPE INDEX outsideg its abwee limi restore the core average ASI to within its limit within 2-hours or reduce. T less than 20% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

MAL POWER to SURVEILLANCE P.EQUIREMENTS i,

4.2.7 The core average AXIAL SHAPE INDEX shall be determined to be within its limit at least once per 12 hocrs using the COLSS or any OPERABLE Core Protection Calculator channel.

+

See Special Test Exception 3.10.2.

i

+

e, 3

PALO VERDE - UNIT 3 3/42-%

SMENOMENT NO. 26 e

FOR INFORMATION ONLY POWER DISTRICUT. ION LIMITS 3/4.2.8 PRESSURIZERPRE550g LIMITING CONDITION FOR OPERATION 3.2.8 The pressurizer pressure shall be maintained between 2025 psia and 2300 psir..

APPLICABILITY:

MODES 1 and 2.

ACTION:

4 With the pressurirer pressure outside its above limits, restore the pressure to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i SURVEILLANCE REQUIREMENTS co 4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

a

\\b PALO VERDE - UNIT 3 3/4 2-R AMENDMENT NO. 27 e 0.2h.

CONTROLLED BY USER EMEAGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER TANK LIMITING CONDITION f0f OPERATION 3.5.4 The refueling water tank (RWT) shall be OPERABLE with:

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a.

A minimum borated wat.er volume as specified in Figur,A14-of Specification 3.1.2.5, and Q

b.

A boron concentration between 4000 and 4400 ppm of boron, and c.

A solution temperature between 60 F and 120*f.

l APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION-l With the refueling w~ter tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.5.4 The RWT shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the contained borated water volume in the tank, and 2.

Verifying the boron concentration of the water, b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWT temperature when the (outside) air temperature is outside the 60 F to 120 F range.

PALO VERDE - UNIT 3 3/4 5-8

i FOR INFORMATION ONLY SCiiVITY CCuffiOL SYSTEMS RASES MOVABLE CONTROL ASSEMBLIES (Continued) and load maneuvering.

operation of tha N555 (base load maneuvering, etc.) and from CEA insertions are determined and a consistent set of radial peaking factors defined.

mined based upon the assumed mode of operation used a means of preserving the assumptions on CEA insertions used.

e determined from analysis. fled serve t.c. limit the behavior of the radial peakin The limits speci-radial xenon redistribution effects to those accommodated in the a ounds Long and Short Term Insertion Limits of Specifications 3.1.3.6 and 3 1 3 7 The specified for the plant which has been designed for primarily base loaded operation but which has the ability to accommodate a limited amount of load maneuvering, the Shutdown CEA Insertion Limits of Specification 3.1 a

minimum 5HUTOOWN MARGIN is maint W :

ejection accident are limited to r eptable levels.1, and (2) the potential effects of a CEA e

Transient Insertion Limits is not permitted since such operation could ha eLon effects on the core power distribution which could invalidate assumptions us to determine the behavior of the radial peaking factors 1

functions, respectivelThe PVNGS CPC ar:t COLSS systems are responsible Operating Limit (POL) y, of the reactor core.

COL 55 monitors the DNB Power-r ng and various operating parameters to help the operator main-tain plant operation within the limiting conditions for operation (LCO) ing within the LCO guarantees that in the event of an Anticipated Operati Operat-Occurrence (A00), the CPCs will provide a reactor trip in time to orevent onal acceptable fuel damage.

un-g n o g o,a % n q u %.a,

u Loss of Flow (LOF) and CEA misoperation transients.The COLS5 ecount for Service (C005 the monitoring function is performed via the CPWhen tne C L55 is Out of DNER in conjun)c, tion with.'echnical Specification C005 Limit L calculation of and 3.2 2a) which restricts the reactor power sufficiently to preserve the R0P (Hgwes-3.4-s--

(Control Elernent Assembly Calculator) sensitivity reduct performed.

This task involved setting many of the inward single CEA deviation en penalty factors to 1.0.

An inward CEA deviation event in effect would not be accompanied by the application of the CEA deviation penalty in either the CPC ONB and LHR (Linear Heat Rate) calculations for those CEAs w penalty factors.

accounted for separately.The protection for an inward CEA deviation event is thus PALO VERDE - UNIT 3 B 2/4 1-6 AMEN 0 MENT NO.

18 e

F.O.R. INFORMATION ONLY REACTIVITY CONTROL SYSTEMS BASES

(

.7 MOVABLE CONTROL ASSEMBLIES (Continued)Q L t ogs ops \\* vtag N

penalty factors to each of the DNB and LHR calculations o

penalty factor, is applied upon detection of the event.

Th first, a static redistribution penalty, is applied linearly-as a-function of The econc, a xenon CEA drop.

The expected margin degradation for the inward CEA ime after the for which the penalty factor has been reduced is accounted for in two eviation event TheR0PMreservedinCOLSSisusedtoaccountfor wa.ys. _

tion.

is required.

a-In addition, the part length CEA maneuvering is restricted in s

accordance with 4;;r: 3.14to justify reduction of the PLR deviation pe factors.

ib dM 6 h W o9ER The technical specification permits plant operation if both CEACs are r Q R EPoe inoperable for safety purposes after this period.

ered 1

PALO VERDE - UNIT 3 8 3/4 1-7 AMENDMENT NO. - 18 w

FOR-INFORMATION ONLY 3/4.2 POWER O!STRIBUTION LIM 1f5 i

BASES t

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3/4.2.1 LINEAR HEAT RATL the peak temperature of the fuel cladding will not exceed 220 Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the local Power Density cha in the Core Protection Calculators core power distribution and are capa(CPCs), provide adequate monitoring of the ble of' verifying that-the linear heat rate does not exceed its limits.

monitoring the cors power distribution-and calculating a core p limit corresponding to the allowable peak-linear heat-rate.

Reactor operation at or below this calculated zwer level assures that the limitspf 13.5 k"/ft are not exceeded.

we%6 A h <.ou cetN% tr w srs g eo The COLSS calculated core power and the COLSS esiculated core power operating limits based on linear heat rate are continuously monitored and displayed to the operator.

core power exceeds the core power operating limit.A COLSS alarm is annuncia This provides adequate-margin to the linear heat rate-operating limit for normal steady-state opera-tion.

Normal reactor power transients or equipment failures which do not require a reactor trip may result-in this core power operating limit being-exceeded.

In the event this occurs, COLSS alarms will'be annunciated.-

event which causes the COLSS limit to be exceeded results in cond If the Protective Instrumentation. approach the core safety limits, a reactor trip will be initi The COLSS calculation of the linear heat rate confidence level, that the maximum linear heat rate ca l

~

j conservative with respect to-the actual maximum linear heat rate existing in the core.

These penalty factors are determined from the uncertainties uncertainty, axial densificationassociated with planar radial peaking measure processing, rod bow, and core: pow,er measurement. software algorithm.modelling, co Parameters required to maintain the operating limit power level based on linear heat rate, margin to CNS, and total core power are also monitored b CPCs.

Therefoce, in the event that the COLSS is not being used the linear heat. rate limit can be maintained by utilizing any op,erable CPC operation within' channel.

with the CPC d rtup test acceptance criteria are also inclu i

PALO VERDE - UNIT 3 B 3/4 2-1 AMENDMENT No.

18 w

FOR INFORMATION ONLY P_0VER DISTRIBUf!ON LIMITS BASES 3/4.2.2 PLANAR RADIAL PEAKING FACTORS Limiting the values of the PLANAR RADIAL PEAKING FACTORS (f C

COLSS and CPCs to values equal to or greater than the measured PEAKING FACTORS (F ") provides assurance that the limits calculate xy and the CPCs remain valid.

determining the measured PLANAR RADIAL PEAKING FACTODS. Data at 20% of RATED THERMAL POWER is assumed in determining the PLAN PEAKING FACTORS.

The 20% RATED THERMAL POWER threshold is flux detector system being inaccurate below 20% core power.due to the neutron at low power is too large to obtain usable detector readings.

Core noise level FACTORS provides assurance that the PLANAR RA The periodic CC 55 and the CPCs remain valid throughout the fuel cycle.

ured PLAT.M RADIAL PEAKING FACTORS after each fuel loading prior toDet mee exceeding 70% of RATED THERMAL F0WER provides additional assu core was properly loaded.

3/4.2.3 AZIMUTHAL POWER TILT -

gg 4g _

]g E mr The limitations on t A

POWER TILT are provided to ensure that design safety margins are intained.

the limit-in figur:

An AZIMUTHAL POWER TILT greater than service is not expected and if it should occur 3.2%with COLSS in service those conditions required to identify the cause, of the tiltoperation is restricted to only I

normally calculated by COLSS.

The tilt is POWER is assumed by the CPCs in its input to COLSS for calcul AZIMUTHAL POWER TILT. The 20% RATED THERMAL POWER threshold is du neutron flux detector system being inaccurate below 20% core power.e to the noise level at low power is too large to obtain usable detector readings Core surveillance requirements specified when COLSS is out of service provide The acnyable means of detecting the presence of a steady-state tilt.

necessary to explicitly account for power asymmetries because the radial It is peaking factors used in the core power distribution calculations are base an untilted power distribution.

The AZDtfiHAL POWER TILT is equal to (P

/P tilt untilt)4.0 where:

at any core location in the presence of a tilt to the unti location is of the form:

P

/Puntilt = 1 + T g cos (0 - e )

tilt q

o where:

T is the peak fractional tilt amplitude at the cere periphery g is the radial normalizing factor

)

0 is the azimuthal core location o is the azimuthal core location of maximum tilt s

PALO VERDE - UNIT 3 B 3/4 2-2 AMENDMENT NO.14 w

FOR INFORMATION ONLY POWER DISTRIBUTf0N LIMITS BASES k

AZIMUTHAL POWER TIL -Tq (Continued)

Pgj)g/Puntilt is the ratis of the power at a core location in the presence of a tilt to the power at that location with no tilt.

The AZIMUTHAL POWER TILT allowance used in the CPCs is value of CPC addressable constant TR-1.0.

3/4.2.4 DNBR MARGIN The limitation on DNBR as a function of AXIAL SHAPE INDEX represents a conservative envelope of operating conditions' consistent with'the safety ana sis tssumptions which have been analytically demonstrated adequate to main-tain an acceptable minimum DNBR throughout all anticipated operational occur-Operation of the core with a ONBR at or above this limit provides rences.

assurance that an acceptable minimum DNBR will be maintained in the event of a loss of finw transient.

Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the DNBR channels in the C distribution and are-capable of verifying that the DNBR limits.

The COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit corresponding to the allowable minimum DNBR.

The COLSS-calculation of core power operating limit based on DNBR includes appropriate penalty factors which provide, with a 9 probability / confidence level, that the core power limits core power limit.

These penalty factors'are determined from the uncertaintles associated with planar radial peaking measurement, engineering heat flut, sta parameter measurement, software algorithm modell_ina, computer processina bow, and core' power measurement.

Parameters required to main Q g A h c.owopm g u m. rod?

4 are also monitored by the CPCs.

int'hemargin-toDNBadtotalT6FpoweE' being used, operation within_the lim re, in the event that the COLSS is not-

. Fi;= 2. 2-2 r.d 2.2. 2E can be maintained by utilizing a predeterminedlNBR as a function of AX1AL SHA and by monitoring the CPC trip channels.

The above listed uncertainty and of 20% of RATED THERMAL' POWER. penalty factors are also included i the neutron flux det1ctor system being less accurate below 20% c Core noise level at low power is too large. to-obtain usable detector read tions to-accommodate the effects of rod bow.A DNBR penalty _ factor h The amount of rod bow in each assembly is-dependent upon the average burnup experienced-by that assembl Fuel assemblies that incur higher average burnup will experience a greater magnitude of rod' bow.

Conversely lower burnup assemblies will experience less rod bow.-

In' design calculations,,the penalty for each batch required to com-pensate for rod bow is determined from a batch's maximum average assembly burnup applied to the batch's maximum integrated plana A

associated with each batch, accounting for the offsetting margins due to the lower radial power peaks in the higher burnup batches.

PALO VERDE - UNIT 3 B 3/4 2 AMEN 0HENT NO. 18

CONTROLLED BY-USER ADMINISTRATIVE CONTROLS

(

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)-

(

The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for. calculating the dose contribution from liquid and gaseous effluents are given in Regula-tory Guide 1.109, Rev.1, October 1977.

The Semiannual-Radioactive Effluent _ Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a.

Container volume, b.

Total curie quantity (specify whether determined by measurement or estimate),_

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

Type of container (e.g., LSA, Type A, Type B, large. Quantity), and e.

f.

Solidification agent or absorbent (e.g., cement, urea formaldehyde).

(

The Semiannual Radioactive Effluent Release Reports shall include a list and descripti'an of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the -reporting period.

The Semiannual Radioactive Effluent Release Reports shall' include any changes made curing the reporting period to the PROCESS CONTROL FC0 GRAM and to the OFFSITE DOSE CALCULATION MANUAL, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use IR5G & 2, census pursuant to Specification 3.12.2.

7 'PECIAL REPORTS S

6.9.2 Special reports shall be submitted to the Regional-Administrator of the Regional Office of the NRC within the time period specified for each report.

6.9.3 Violations of the requirements of the fire protection program _ described in the Final Safety Analysis-Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire-shall be-reported in accordance with 10 CFR 50.73.

+

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at-least the minimum period indicated.

C PALO VERDE - UNIT 3 6-20

I INSERT 2 CORE OPERATING LIMITS REPORT 6.5.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each roload cycle or any remaining part of a reload cycle.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, and are as follows:

"C-E Method for Control Element Assembly Ejection Analysis,"

CENPD-190-A, January, 1976; "The ROCS and DIT Computer Codes for Nuclear Design,"

CENPD-266-P-A, April, 1983;

" INCA /CECOR Power Peaking Uncertaintf," CENPD-153-P, Revision 1-P-A, May, 1980;

" Safety Evaluation Report Related to the Final Design of the Standard Nuc. lear Steam Supply Reference Systems CESSAR System 80, Docket No.

STN 50-470,"

NUREG-0852 (November 1981),

Supplements No. 1 (March 1983), No. 2 (September 1983), No.-3 (December 1987);

" Modified Statistical Combination of Uncertainties,"

CEN-356(V)-P-A, Revision 01-P-A, May, 1988.

The core operating limits shall be determined so that all' applicable limits (e.g., fuel thermal-mechanical limits, core thermalhydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the: safety analysis are met.

The_ CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC' Document Control Desk with copies to the Regional Administrator and Resident Inspector.

=

3~

u 1

ENCLOSURE 2 l

)

CORE OPERATING LIMITS RFsPORT PALO VERDE NUCLEAR GENERATING STATION (I'VNGS)

UNIT 1 CYCLE 3 INDEX PAGE l

AFFECTED PVNGS TECHNICAL SPECIFICATIONS.

1 CORE OPERATING LIMITS.

1 REFERENCES...

4 1.lST OF FIGURES.

5 LIST OF TABLES....

16 1

)

l l

i

CORE OPERATING LIMITS REPORT PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 1 CYCLE 3 l

This Core Operating Limits Report for PVNGS Unit 1 Cycle 3 has been prepared in accordance with the requirements of Technical l

Specification 6.9.1.

The core operating limits have been l

developed using the NRC approved methodologies specified in References 1 through 5.

AFFECTED PVNGS TECIINICAL SPECIFICATIONS 1) 3.1.1.2 6) 3.1.3.7 Shutdown Margin Part Length CEA Kn_1 - Any CEA Insertion Limits Withdrawn 7) 3.2.1 2) 3.1.1.3 Linear Heat Rate Moderator Temperature Coefficicnt 8) 3.2.3 Azimuthal Power 3) 3.1.2.7 Tilt -T q l

Boron Dilut4on Alarms 9) 3.2,4 4) 3.1.3.1 DNBR Margin Movable Control Assemblies - CEA 10) 3.2.7 Position Axial Shape Index l

5) 3.1.3.6 Regulating CEA Insertion Limits CORE OPFR ATING LIMITS l

The cycle-specific operating limits for the specifications listed are presented below.

111. 2 - Shnulown Ma_Isin Kg - Any_CEA WitlldI.a.lin The Shutdown Margin shall be greater than or equal to that shown in Figure 1.

Page 1 of 21 1

LL

UNIT I CYCLE 3 CORE OPERATING I,IMITS REPORT CORE OPER ATING 1 IMITS. CONTINUED 1.1.1. 3 - ModeIAtar TenTarat ure Coe_t ficient The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown on Figure 2, 3_m1. 2. 7

.foron Dilution Alarms With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 1 through 5.

3 L3.1 - Monble_ Control _Assembli.es - CEA_P.caition With one or more full-length or part-length CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.

LL11_. __ Regulating __CEA Inaution_Limita One or more CEAC's OPERABLE: The regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 4 when the COLSS is IN SERVICE or shown on Figure 5 when the COLSS is O_UI OF SERVICE.

l L _1_,_ L 7 - Eart_LengLh_CEA In s erti_on_ Limits l

One or more CEAC's OPERABLE: The part length CEA groupa shall be limited to the insertion limits shown on Figure 6.

3.2.1 - Linear Heat Rate l

The linear heat rate limit of 13.5 kW/ft shall be maintained.

3,1 3 - AnimuthAl_' _xar_Iilt

-T y The AZIMUTHAL POWER TILT (T ) shall be less than or q

equal to the limit in Figure 7 with COLSS IN SERVICE.

Page 2 of 21 L

UNIT I CYCLE 3 CORE Ol'ERATING LIMITS REPORT CORE OPERATING LIMITS. CONTINUED L2 d - DNBB Margin COLSS IN SERVICE and Both CEAC's INOPERABLE - Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in i

Figure 8, l

COLSS OUT OF SERVICE and Either One or Both CEAC's are OPERABLE - Operating within the region of acceptable operation of Figure 9 using any operable CPC channel.

i COLSS OUT OF SERVICE and CEAC's INOPERABLE - Operating within the region of acceptable operation of Figure 10 using any operable CPC channel.

L 2. 7 - A>;iaL_Shap.e_lndex The core average AXIAL SHAPE INDEX (ASI)-shall be maintained within the following limits:

t

(

l COLSS OPERABLE

-0.28 s ASI s 0.28 COLSS OUT OF SERVICE (CPC)

-0.20 s ASI $ 0.20 Page 3 of 21

. _. _ _ = _. _ _. _ _ _

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT l

l REFERENCES 1.

"C-E Method for Control E ement Assembly Ejection Analysis,"

CENPD-190-A, January, 1976, 2

"The ROCS and DIT Computer Codes for Nuclear Design,"

CENPD-266-P-A, April, 1983.

3.

" INCA /CECOR Power Peaking Uncertainty," CENPD-153-P, Revision 1-P-A, May, 1980.

4.

" Safety Evaluation Report Related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No.STN 50-470," NUREG-0852 (November 1981),

Supplements No. 1 (M&rch 1983), No. 2 (September 1983), No. 3 (December 1987).

5.

" Modified Statistical Combination of Uncertainties,"

l CEN-356(V)-P-A Revision 01-P-A, May, 1988.

l Page 4 of 21

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT LIST OF FIGURES l

1. Shutdown Margin Versus Cold Leg Temperature.

2. Allowable MTC Modes 1 and 2.

l

3. Core Power Limit After CEA Deviation.

l l

4. CEA Insertion Limits vs Rennal Power (COLSS In Service).

5. CEA Insertion Limits vs Thermal Power (COLSS Out of Service)

6. Part Length CEA Insertion Limit vs Thermal Power.

7 Azimuthal Power Tilt Limit vs Thermal Power (COLSS In Service).

8. COLSS DNBR Power Operating Limit Allowance for Both CEACs Inoperable,

9. DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEACs Operable) l

10. DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEACs Inoperable) l l

Page 5 of 21

l UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT 7

(500, 6.5),

6 5

REGION OF h

ACCEPTABLE

^

OPERATION h4 l

(350, 4.0) 8 e

3 0

3 s

4 REGION OF h

UNACCEPTABLE OPERATION 5

2 U!

l 0

0 100 200 300 400 500 600 COLD LEG TEMPERATURE ('F) 1 FIGURE I SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE Page 6 of 21 i

0.5 i

i

\\

i 1

\\

~

(0% 0.5) 7, i

O i

e (100E 0.0) 2q OC n

,C 0.5

~

f*

n

\\

~1 i

r" 1

c cf M

I O

J D

\\

wn 7

E, h

O u

-1 o

0 y% '

b 3

3 C

W k

9 13 0O

-1.5 y

y ALLOWABLE MTC A

H 0

E y

Cy e

-2 W

m E

m S

q

~

I6 4m H

x 8

C

-2.5 9

3W (OE -2.8) 4 y

b

~3

~~

i V

(100E -3.5)

-3.5 i

i I

i z

s O

10 20 O

40 50 60 70 80 W

T pos LEVEL, % OF RATED T11NML

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT FIGURE 3 CORE POWER LIMIT AFTER CEA DEVIATION

30 l

I I

I i

5 j

(60 MIN,20%)

C'$ 20

$ 2 M.J hI E8

% 10 5*

bxm 2b 3e 0

{t i

5 I

I I

I i

0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES

WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL POWER PER tills LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED Page.8 of 21 i

y

._,y,

. = _ - _.

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT o-R-

~S-Doyo_

o-8-

m Ci z

b@-

R-N 2

~

I a

o$S-Q o-b FC w

-d o_

N

~~

Pd a

m z

mh D

O GEOUP 3 @ 60" o

A s,v3 D

U m

m8-S-

Z A.

4 3

mz o

[m M8-o-

[C _ ]

O V

O do Z

's z

3 o_

o-O m

m 9

b B $

o 2

\\

/!

8 g"

t

/

o8_

o_

a 8-u-

I

/k

.........i n8-R-

GROUP 5 y 60"i STEADY ShATE l g

~

j

@g_

/

SHORT TE 0

INSERTIDN LINTIT l

.......\\,.....................-......J........[108 "

GROUP 5 @

o O-LONG TERhi STEADY STATE lhSERTibN LIMIT R-l o

e

=

b.

9 vi v.

9 N.

o e

o o

o FRACTION OF RATED THERMAL POWER Page 9 of 21

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT o-

?-

g-Bo

@ 8-o-

R- <

M k

9 2

a _ "$ s - p

~

$ 8-o-

!S iG 8-Z 95 o-ma

~

U RW mM GLOUP3 @ 60" o

m @-

0- {

lfo g

b o

o o_m

$ g_

o p

o-ge$

3 MO z o o

o~

OM U~

m A

Pe W

e

=t o ~

U~

U y

g j

g*

TRANSIENT JNSERTION LIMIT l

i o

@ 8-g o-t I

o_

a_

~

f l

~

ROUP 5 @ 60" 8

u na n. nan n ),n n u,5 n 8-0-

un m

l SHORT TERM STbDYh o

Y)(nnua.. TATE bSERTION I'IMIT S

$ 8-uann]nunuNuurn]nnon)

GROUP 5 @ :. 08" LONG TERM STEADY

~

STATE INSERTION LIMIT b-o m

h 9-v1 v.

n N

c.

o o

o e

o o

FRACTION OF RATED THERMAL POWER Page 100f 21

UNIT 3 CYCLE 3 CORE OPERATING LibilTS REPORT 0

1

-l l

I I

i l

~

10 20 30 40 j

i 50 I

e TRANSIENT INSERTION Llhi!T (75.0 INCHES) 70 E3 k

80

@3 Y

RESTRICTED 0

UNACCElvrABLE e

h OPERATION OPERATION 100 g

s 6

g 110 0

P o

~

LONG TERhi STEADY STATE INSERTION LlhfIT 120

$a (112.5 INCHES)

H g

130 140 I

I I

l l

10 0 8

O.

8 8

o o

FRACTION OF RATED THERhiALPOWER FIGURE 6 PART LENGTH CEA INSERTION LIhilT VERSUS THERhfAL POWER Page 11 of 21

l l

UNIT 1 CYCLE 3 CORE OPERATING LIMrrS REPORT FIGU> E 7 AZIMUTHAL POVMR TIUr LIMIT vs. THERMAL POWER (COLSS IN SERVICE) 100 l

I I

90 80 U

70 g

w H

60 REGION OF UNACCEPTABLE g

W OPERATION

s 50 2

h 40 E2 30 20 10 l

REGION OF ACXIFTABG OPERATION 0

I I

i l

20 30 40 50 60 70 80 90 100 1

PERCENT OF RATED THERMAL POWER l

l l

l

[

Page 12 of 21

UNIT 1 CYCLE 3 CORE OPERATING LIMITS ITEPORT FIGURE 8 COLSS DNBR POWER OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE 100 I

I I

20% @

POWER 75 d

is

3..

50 I

8

!E 25 d

w 1

I I

I O

25 20 15 10 5-0 COLSS DNDR POWER OPERATING LIMIT REDUCTION

(% OF RATED THERMAL POWER) l i

l Page 13 of 21 t

~.

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT COLSS OUT OF SERVICE DNBR LIMIT LINE 2.5 I

I I

2.4 ACCEPTABLE OPERATION 2.3 MINIMUhi ! CEAC OPERABLE ce caZ 32.2 E

E 2

(-0.2, 2.15)

(0.2, 2.15)

M 2.1 l

l 2.0 UNACCEPTABLE OPERATION I

l 1.9 1.8 l

l t

l l

-0.3

-02

-0.1 0.0 0.1 0.2 0.3 CORE AVERAGE ASI FIGURE 9.

DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE)

Page 14 of 21

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT COLSS OUT OF SERVICE DNBR LIMIT LINE 2.5 i

i i

i ACCEPTADLE OPERATION

^8 2.4 (0.2, 2.4) _

(0.05,2.4) 2.3

$zQ E

2 2.2

/

s 3

(-0.2, 2,2) 2 NU 2.1 UNACCEPTABLE OPERATION 2.0 l

1.9 i.

I I

i i

i

-03

-0.2

-0.1 0.0 0.1 0.2 0.3 CORE AVERAGE ASI FIGURE 10 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs INOPERABLE)

Pagel5 of 21

i UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT l

l LIST OF TAllLES l

1. Required Monitoring Frequencies for Backup Baron Dilution Detection as a Function of j

Operating Charging Pumps and Plant Operational Modes for K g > 0.98.

e l

2. Required Monitoring Frequencies for Back.up Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 2 K g > 0.97.

e

3. Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 2 K g > 0.96.

e

4. Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function e '

Operating Charging Pumps and Plant Operational Modes for 0.96 2 K g > 0.95.

e

5. Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for K g s 0.95.

e I

Page 16 of 21

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT TABLE 1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTICN AS A FUNCTION OF OPERATING CilARGING PUMPS AND PLANT OPERATIONAL MODES FOR K,g> 0.98 8

OPERATIONAL MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I hour ONA ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I hour ONA ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months I hour ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes. SCS = Shutdown Cooling System CNA = Operation Not Allowed j

Page 17 of 21-l

UNIT I CYCLE 3 CORE OPERATING LIMITS REPORT TABLE 2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OFOPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 2 K rr> 0.97 e

OPERATIONAL MODE O

1 2

3 3

12 hou s 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Ihour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 not on SCS 8 houa 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Ihour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 & 5 ou SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed l

l l-l j

Page 18 of 21

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT TABLE 3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 2 l' g> 0 96 y

E E8 OPERATIONAL MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Ihour 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months I hour 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Ihour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Netes: SCS = Shutdown Cooling System ONA = Operation Not Allowed l

Page 19 of 21 l

_=

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT

)

TABLE 4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CilARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 2 K,g> 0.95 OPERATIONAL MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 5 hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Ihour 4 not on SCS 12 hcurs 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours Ihour 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 5 hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I hour 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes: SCS = Shutdown Cooling System ONA n Operation Not Allowed l

Page 20 of 21 a.

UNIT 1 CYCLE 3 CORE OPERATING LIMITS REPORT TABLE S REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CilARGING PUMPS AND PLANT OPERATIONAL MODES FOR K g 5 0.95 e

Number of Operat' g Charging Pumps m

OPERATIONAL MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 6 hours 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1,5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 6 hours 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6 hours 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours Ihour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 6

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8 hours 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 2 hours Notes:. SCS = Shutdown Cooling System Page 21 of 21

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ML20091A497

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