Text

Proposed Tech Specs to Allow Reduced Power Operation as Function of RCS Total Flow Rate for Flow Rate Reductions of Up to 5% Below Currently Specified Flow Rate
	ML18011A430
Person / Time
Site:	Harris
Issue date:	05/11/1994
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML18011A429	List: HNP-94-038, Application for Amend to License NPF-63,revising TSs to Allow Reduced Power Operation as Function of RCS Total Flow Rate for Flow Rate Reductions of Up to 5% Below Currently Specified Flow Rate; ML18011A430;
References
	NUDOCS 9405180047
	Download: ML18011A430 (31)
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ENCLOSURE 5

SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT REACTOR COOLANT SYSTEM (RCS)

FLOW RATE TECHNICAL SPECIFICATION PAGES qggggg'0047 440511~

PDR ADOCK 05000400; "1

P PDR

IHOEX 2.0 SAFETY LIMITS ANO LIMITIHG SAFETY SYSTEM SETTINGS SECTION 2.1 SAFETY LIMITS P10C 2.1.1 REACTOR CQR............................

~---"~.------------

2.1.2 REACTOR COOLANT SYSTEM PRESSURE.."

~.--.---. ~-"-".".-"---

FIGURE 2. 1-Z.

0 REE P

I ERATIO

> ~H I <>~<<~ <t'~ <Lokl+f2935+ gp~ ~ (i g >~ g

2. 2 LIMITI e 'Y

/

2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS.

~. ~ ~...

~.-" ~ ~

TABLE 2.2-1 REACTOR TRIP SYSTEM IHSTRUMEHTATION TRIP SETPOIHTS"-.

PAGE 2-1 2-1 2.-2 2-1 2-4 BASES SECTION 2.1 SAFETY LIMITS 2.1. 1 REACTOR CORE.......................... "-..

~ -"-"- - - -"" ~ ~

2.1.2 REACTOR COOLANT SYSTEM PRESSURE......... ~...----. ~ ~ "----

~ ~

2.2 LIMmHG SAFETY SYSTEM S~E; HGS 2.2. 1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOIHTS....

~ ~ - ~ ~ ~

~ ~ - ~ ~

PAGE B 2-1 a z-z B 2-2 SHEARON HARRIS - UNIT 1

ENDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.2 POWER DISTRIBUTION LIMITS PAGE 3/4.2.1 AXIAL FLUX DIFFERENCE....................................

3/4 2-1 FIGURE 3.2-1 (DELETED)...................e........................

3/4 2-4 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR " FQ(Z)

~

~ ~ ~ o ~ ~ ~ ~

~ ~

~

~ ~

~

3/4 2-5 FIGURE 3.2-2 (DELETED). ~ ~ ~ ~...

~ ~ ~. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

. ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~

3/4 2-8 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~

~ ~ ~

3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO. ~.. ~ ~ ~ ~ ~ ~. ~ ~ ~ ~

~ ~

~ ~ ~

~ ~ ~ ~

~ ~

~

~ ~ ~

3/4 2-11 3/4.2.5 B

ET FtgUgg g.g-g AlLOgQ Me'ASuREb RQCVDRMOu7SYS~&f 707AC.FLOW Rp7g yg~up pDNE'R-7pREE LOOPS

/nl OPEZA7/DN 3/42./ab 3/4. 3 I NSTRUMENTATION 3/4 ~ 3 ~ 1 REACTOR TRIP SYSTEM INSTRUMENTATION~

~ ~

~ ~ ~ ~ ~ ~

~ ~ ~ ~

~

3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION...................

3/4 3

2 TABLE 3.3-2 (DELETED)............os

~...........o................o.

TABLE 4'-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..... ~..............o........

3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.................o....e..........

~ ~

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~ ~ ~ ~ ~

~ ~

~ ~ ~ ~ ~ ~

~ ~

~ ~ ~

TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRI P SETPOINTS.

~ ~ ~ ~

~ ~

~ ~ ~ ~

~ ~

~

TABLE 3.3-5 (DELETED).........................

~..............o.

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.

3/4.3. 3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations.

~ ~" ~ ~ ~ ~ ~ - ~ ~

~ ~ ~

3/4 3-9 3/4 3-11 3/4 3-16 3/4 3-18 3/4 3-28 3/4 3-37 3/4 3-41 3/4 3-50 SHEARON HARRIS " UNIT 1

Amendment No.

650 238 paig 640 p*ie U

g 620 l96 prig 610 600 590 580 0.0 0.1 0.2 0.3 OA 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 POWER (fraction of nominai)

FlGURE.2.1-1 REACTOR CORE SAFETY LllVllT>>THREE LOOPS lN 0 AT ON flail <EAslN<> RLs FLow J j'299,5'fo &f'M x (f Dt e,)3 l

SHEARON HARRIS - UNIT I 2-2 Amendment No.+

TABLE 2.2-1 REACTOR TRIP SYSTEH INSTRUHEHTATIOH TRIP SETPOINTS FUNCTIONAL UNIT TOTAL ALLOWANCE (TA)

Z SENSOR ERROR (S)

TRIP SETPOINT ALLOWABLE VALUE l.

Hanual Reactor Trip N.A.

NiA N.A.

H.A.

2.

Power Range, Neutron Flux a.

High Setpoint b.

Low Setpoint 3.

Power Range, Neutron Flux, High Positive Rate 7.5 8.3 1.6 4.56 0

4.56 0

0.5

<109Z of RTP~

See No& 7 o

<5X of RTP~ with a time constant

>2 seconds

<111.1Z of RTP**

See hbtE 1 1X of RTP~

<6.3X of RTP** with a time constant

>2 seconds 4.

Power Range, Neutron Flux, High Negative Rate 1.6 0.5

<5Z of RTP~ with a time constant

>2 seconds

<6.3X of RTP** with a time constant

>2 seconds 5 ~

Intermediate

Range, Neutron Fl.ux 17.0 8.41 0

<25X of RTW*

<30.9X of RTP--

6.

Source

Range,

.Neutron Flux 7.

Overtemperature hT 8.

Overpower hT 9.

Pressurizer Pressure"Low 10.

Pressurizer Pressure-High ll.

Pressurizer Water Level-lligh 17 0 8.7 4.7 5.0 7.5 8.0 10.01 0

<10 cps 1.50 2.21 5.01 1.9 1.5 0.5 See Note 3

>1960 psig

<23S5 psig 2.18 1.5

<92X of instru-ment span 6.02 Note 5

See Note 1

<1.4 x 10 cps See Note 2

See Note 4

>1946 psig

<2399 psig

<93.8X of instru-ment span

<="RTP = RATED THERHAL POWER

TABLE 2.2-1 Continued ABLE NO ATIONS NOTE 3:

(Continued)

K, 0.002/'F for T > T" and Ke = 0 for T x T",

As defined in Note 1, Indicated T, at RATED THERHAL POHER (Calibration temperature for IIT inatrumentat on, a 580.8'F),

As defined in Note 1, and I

CD fz(hI)

=

0 for all EI.

NOTE 4:

The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3% hT span.

NOTE 5:

The sensor error for temperature is 1.9 and

1. 1 for pressure.

NOTE 6:

The sensor error for steam flow is 0.9, for feed flow is 1.5, and for steam pressure is 0.75.

NOTE 7:

This value is associated with measured RCS flow > [293,540 gpm x (1.0 + Cz)].

Technical Specification 3/4.2.3 requires this setpoint to be reduced at the rate of 1.5% of RTP for each 1% that measured RCS flow is below [293,540 gpm x (1.0 + Cz)].

POWER DISTRIBUTION L1MITS g

)~<< ~ i4)

ZA5cH 3/4 ~ 2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The Reactor Co ant System (RCS) total flo rate and F>H shall be maintained as folio a.

RCS t al flow rate ) 293,540 gpm (1-0

+ C1)

T and b.

F

(

FA (1.0

+

PF H (1.0-ere:

F

= F<~ limit at TED THERMAL POWER specified i the CORE RTP OP RATING ITS REPORT {COLE), plant proc dure PLP-106, PF<H

= Power F ctor Multipler for F<H specifi d in the

COLR, R

ED THERMAL POWER Enthalpy rise hot channel fa or obtained by using the movable incore detectors t

obtain a power distribution map, with the measured alue of the nuclear enthalpy rise hot channel factor

)

increased by an allowance of X

dH to account for me urement uncertainty, and Cl

= Measurement u

ertainty for core flow as describ in the Bases.

APPLICABILITY:

MODE l.

ACTION:

With RCS total flow ate or F<H outside the above lim':

Withi 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months eithert 2 ~

Restore RCS total flow rat and F<H to within the ab e

laments, or Reduce THERMAL POWER o less than 50X of RATED HERMAL POWER and reduce t Power Range Neutron Flu - High Trip Setpoint to less an or equal to 55X of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SHEARON HARRIS - UNIT 1

3/4 2-9 Amendment No.~

PO CO FOR OP 0

b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of nitially being outs e the above limits, v ify through incore f mapping and RCS t 1 flow rate determi tion that F~ and S total flow rate a

restored to within e above limits, or r duce TfKRMAL POWER less than 5% of RAT HKRMAL POWER wi the next, 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months c ~

Ident and correct the ause of the out-of-1 t condition prior to incr asing THEBMAL PO above the reduced POWER limf.t re ired by ACTION

.2. and/or bos above; ubsequent POWER OP ON y proceed pro ed that F~ and indic ed RCS total flow ra are demonstrated, rough incore flux ma ing and RCS total fl rate determinati

, to be within accep le limits prior to e ceding the followin POWER levels:

1.

2 A nominal 50% of TED TfKRMAL POWER, A nominal 75$

RATED THERMAL POWER and Within 24 h s of attaining great than or equal to 95% of RATED POWER.

4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 F~ shall be determined to be within acceptable limits:

a.

b.

Prior to operation above 75% of RATED THERMAL POWER after each fuel

loading, and At least once per 31 Effective Full Power Days.

4.2.3.3 The RCS total flow rate shall be verified to e with n the a reojions op res&'ek or persoissinfe, operation oi'igsrs 9.<"3:

s a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by the use of main control board instru-mentation or equivalent, and

/

b.

At least once per 31 days by the use of process computer readings or digital voltmeter measurement.

4.2.3.4 The RCS total flow rate indicators shall be sub]ected to a GUNNEL CALIBRATIONat least once per 18 months.

4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement at least once per 18 months.

The measurement instrumentation shall be calibrated within 21 days prior to the performance of the calorimetric flow measurement.

SHEARON HARRIS - UNIT 1 3/4 2-10 Amendment No.

INSERT TO PAGE 3/4 2-9 THRU 3/4 2-10 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and THERMALPOWER shall be maintained within the'region of permissible operation shown on Figure 3.2-3 for three loop operation and F~ shall be maintained as follows:

a.

F~ a f"

[1.0 + PF~ (1.0-P)]

Where:

F ATP PF~

F~ Limit at RATED THERMALPOWER specified in the CORE OPERATING LIMITS REPORT (COLR),

plant procedure PLP-106, Power Factor Multiplierfor F~ specified in the COLR, THERMALPOWER RATED THERMALPOWER APPLICABILITY: IVIODE 1.

ACTION:

Enthalpy rise hot channel factor obtained by using the movable incore detectors to obtain a power distribution map, with the measured value of the nuclear enthaipy rise hot channel factor F~

increased by an allowance of 4% to account for measurement uncertainty.

a.

With the combination of RCS total flow rate and THERMALPOWER within the region of prohibited operation shown on Figure 3.2-3 or F~ outside the limits given in 3.2.3a.:

1.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

a)

Restore the combination of RCS total flow rate and THERMAL POWER to within the region of permissible operation, and F~ to within the limits given in 3.2.3a., or b)

Restore the combination of RCS total flow rate and THERMAL POWER to within the region of restricted operation and comply with ACTION b. below, or

~

q

~

INSERT TO PAGE 3/4 2-9 THRU 3/4 2-10 (CON'T) c)

Reduce THERMALPOWER to less than 50/o of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55/o of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

With the combination of RCS total flow rate and THERMALPOWER within the region of restricted operation (flow rate less than

[293,540 gpm x (1.0 + C,)], which includes measurement uncertainty for core flow, Cas described in the Bases), within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months reduce the Power Range Neutron Flux-High Trip Setpoint to below the nominal setpoint by the same amount (/o RTP) as the power reduction required by Figure 3.2-3 and maintain F~ at a value that is less than or equal to the value of F~ at RATED THERMAL POWER.

C.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being within the region of prohibited operation show'n on Figure 3.2-3 either:

Verify through RCS total flow rate determination and incore flux mapping that the combination of RCS total flow rate and THERMALPOWER are restored to within the region of permissible operation, and F~ to within the limits given in 3.2.3a., or 2.

Verify through RCS total flow rate determination and incore flux mapping that the combination of RCS total flow rate and THERMALPOWER are restored to within the region of restricted operation and comply with ACTION b. above, or 3.

Reduce THERMALPOWER to less than 5/o of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

d.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMALPOWER above the reduced THERMALPOWER limit required by ACTION a.1.c) and/or c.3), above; subsequent POWER OPERATION may proceed provided that the combination of THERMALPOWER and indicated RCS total flow rate are demonstrated through RCS total flow rate. comparison to be within the regions of restricted or permissible operation shown on Figure 3.2-3 and that F~ is demonstrated through incore flux mapping to be within acceptable limits prior to exceeding the following THERMALPOWER levels:

1.

A nominal 50/o of RATED THERMALPOWER, 2.

A nominal 75/o of RATED THERMALPOWER, and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMALPOWER.

33.0 Prohibited Operetlon Region 32.0 l 100.0, 32.13 x ll.o - C1 ) )

31.0 U

30.0 CC 29.0 Permissib)e Operation Region Restricted Operetion Region l 100.0. 29.364 x l1.0 + C1 ) )

28.0 l 92.6. 27.89 x ll.o + C1 ) )

27.0 88.0 90.0 92.0 94,0 98.0 98.0 100.0 102.0 104.0 Power {% RTP)

Figure 3.2-3 Allowed Measured Reactor Coolant System Total Flow Rate versus Power-Three Loops in Operation SHEARON HARRIS - UNIT 1

3/4 2-10b Amendment.

No.

POWER DISTRIBUTION TS BASES HEAT FLUX HOT CHANNEL FACTOR.

AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued c.

The control rod insertion limits of Specifications

3. 1.3.5 and 3.1.3e6 are maintained; and d.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

F~ will be mainta' within its limits prov ed Con 1

ons a.

roug above are main ned.

The combination o

e RCS flow requirement a

he measuremen f F~ ensures that the c ulated DNBR will not be b

w the design R value.

The relaxati of F~ as a function of TH L POWER all s changes in the radial wer shape for all permissi e rod insertion mits.

(

aC<

I+ rf When an F~ measurement is taken, an allowance for measurement error must be applied prior to comparing to the F"" limit(s) specified in the CORE OPERATING LIMITS REPORT (COLR).

An allowance of 4% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System.

Margin is maintained between the safety analysis limit DNBR and the design limit DNBR.

The margin is more than sufficient to offset any rod bow penalty and transition core penalty.

When an F, measurement is taken, an allowance for both experimental error and manufacturing tolerance must be made.

An allowance of 5% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System, and a

3%

allowance is appropriate for manufacturing tolerance.

The hot channel factor F,M(Z) is measured periodically and increased by a cycle and height dependent power factor V(Z) to provide assurance that the limit on the hot channel factor, F,(Z), is met.

V(Z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core.

The V(Z) function is specified in the COLR.

SHEARON HARRIS - UNIT 1 8 3/4 2-4 Amendment Ne~

INSERT TO B 3/4 2-4 F~ will be maintained within its limits provided Conditions a. through d. above are maintained.

The combination of measured RCS flow rate and THERMALPOWER must be maintained within the regions of permissible or restricted operation as shown in Figure 3.2-3 to ensure that the combination of RCS flow rate and THERMAL POWER are within the ranges considered in the mechanical and safety analyses and, along with the measurement of F~, to ensure that the calculated DNBR will not be below the design DNBR value.

The relaxation of F~ as a function of THERMAL POWER when in the region of permissible operation allows changes in the radial power shape for all permissible rod insertion limits.

For the FSAR Chapter 15 analyses reliant on the Power Range Neutron Flux - High Trip Setting trip function, reduction of the Setpoint by the same percentage as the required power reduction in Figure 3.2-3 (1.5% RTP per 1% RCS flow rate) ensures DNBR margin is maintained.

When in the region of restricted operation, defining ZT, as the equivalent hT at 100% RTP and

[293,540 gpm x (1.0 + C,)] (which includes measurement uncertainty for core flow) results in an effective OTBT setpoint reduction and maintains DNBR margins for those analyses reliant upon the OTQT trip. The additional restrictions on F~ when in the region of restricted operation ensure that the margins gained by the power and setpoint reductions are not reduced by the normally allowable increases in radial peaking at reduced power levels.

POWER DISTRIBUTION LI.".ITS BASES HEAT FLUX HOT CHANNEL FACTOR.

AND RCS F'OW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

When RCS fLou rate is measured, no additional alLouance is necessary prior to comparison uirh the Limic of Specification 3.2.3.

A normal RCS flowrace error of 2.1X will be included in CL, which wiLL be modified as discussed below.

The measuremenc error Eor RCS cocal ELow race is based upon performing a

precision heac balance and using che resulc ro calibrate che RCS Elou rare indicators.

Porencial fouling of che feeduacer vencuri which might not be decected could bias che resulc from che precision heac balance in a non-conservar.ive manner.

Therefore, a penalcy oE 0. LX Eor undetected fouling oE the Eeedwacer

vencuri, raises che nominal flow measuremenc allowance, Cl, to 2.2X for no venruri fouLing.

Any fouling which might bias che RCS flow rate measuremenc greacer chan 0.1X can be detected by monitoring and trending various plant performance parameters.

IE detected, accion shall be caken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quancified and compensaced for in the RCS Elou rate measurement or che venturi shaLL be cleaned co el.iminare che fouling.

j-ps&1 (nod/

The 12-hour periodic surveillance of indicated RCS fLow is sufficient co detect only flow degradac,ion chat. could lead co operation outside che.accepr."

able r egion oE operacion.

3/4.2.4 UADRANT'POWER TILT RATIO The qUADRANT POWER TILT RATIO Limit assures chat che radial power distribution sarisfies che design values used in che power capability analysis Radial power distribucion measuremencs are made during STARTUP testing and Pe<<od ically during pouer operation.

The Limit of 1.02, ac which corrective acc,ion is required, provides oNB and linear heat generar.ion race procection wich x-y plane power cslts

~

A L<m>c>ng tilt of 1.02$

can be rolerated before che margin for uncertainty

<n Fq

~s depleted

~

A limit oE 1.02 was selected co provide an aLlowance for che uncertainty associated with the indicated power tilt~

The 2"hour time allowance for operation with a cilt condition greater chan

'.02 buc Less chan 1.09 is provided to allow identificacion and correccion of a dropped or misaligned concrol rod.

In che event such accion does n<<

correcr.

the cilc,, the margin Eor uncercaincy on F~ is reinscaced by reducing che maximum aLloued power by 3X for each percent, of tilt in excess oE SHEARON HARRIS - UNIT 1

B 3/4 2-5 Amendment No.~

INSERT TO B 3/4 2-5 The upper limit on measured RCS flow rate in Figure 3.2-3

[321,300 gpm x (1.0 - C,)] protects the mechanical design flow of 321,300 gpm per FSAR Table 5.1.0-1.

INDEX 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE.........................-.-.

~......

2.1.2 REACTOR COOLANT SYSTEM PRESSURE...............-...--.......

FIGURE 2.1-1 REACTOR CORE SAFETY LIMITS - THREE LOOPS IN OPERATION WITH HEASURED RCS FLOW a [293,540 GPH x (1.0 + C,)]

PAGE 2-1 2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2. 1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS.....-........

TABLE 2.2-1 REACTOR TRIP SYSTEH INSTRUMENTATION TRIP SETPOINTS...

2-1 2-4 BASES SECTION 2.1 SAFETY LIMITS

2. 1. 1 REACTOR CORE...................................

~

~ ~

~

2. 1.2 REACTOR COOLANT SYSTEM PRESSURE............................

PAGE 8 2-1 B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS.......-......

B 2-2 SHEARON HARRIS - UNIT 1 Amendment No.

4 3/4.2.4 3/4.2.5 QUADRANT POWER TILT RATIO............................

DNB PARAHETERS.................................

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREHENTS SECTION 3 4. 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................................

FIGURE 3.2-1 (DELETED).."................. ~...........

3/4e2e2 HEAT FLUX HOT CHANNEL FACTOR - Fo(Z)o

~

FIGURE 3.2-2 (DELETED)................,..............

3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL F

ACTOR'S

~

~ t ~

~

~ ~

~

~ o

~

FIGURE 3.2-3 ALLOWED MEASURED REACTOR COOLANT SYSTEM TOTAL FLOW RATE VERSUS POWER - THREE, LOOPS IN OPERATION......

PAGE 3/4 2-1 3/4 2-4 3/4 2-5 3/4 2-8 3/4 2-9 3/4 2-10b 3/4 2-11 3/4 2-14 3 4.3 INSTRUMENTATION 3/4.3.1 TABLE 3.3-1 TABLE 3.3-2 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION..................

REACTOR TRIP SYSTEM INSTRUMENTATION.................

DELETED)...........................................

(

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREHENTS..........................-........

3/4 3-1 3/4 3-2 3/4 3-9 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION......................................

3/4 3-16 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION TRIP SETPOINTS.......................

3/4 3-28 3/4 3-37 TABLE 3.3-5 TABLE 4.3-2 3/4.3.3 (DELETED).

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~

~

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RfQUIREMENTS............

3/4 3-41 MONITORING INSTRUMENTATION Radiation Monitoring For P1ant Operations............

3/4 3-50 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION......................................

3/4 3-18 SHEARON HARRIS - UNIT 1 Amendment No.

-'rnurnrax

, NILTraarraras

' rrrrr@Etirarrs

., $ErrrIrarrrs rarhrRRmrrrrr

,urrrrrraru

'iTrrarrrarrs

., Srraarrrrrrl Irrr%lrrrr5

., srrrraIrrrL)

IrrrrrERErrR rrurrrrrra~

"rrrurrrrrra

.,rrrrrrrrrrm srrrarrrrrrS

,,ERSSRSSRESER

I 4

TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS b.

Low Setpoint 3.

Power

Range, Neutron Flux, High Positive Rate 4.

Power Range, Neutron Flux, High Negative Rate 5.

Intermediate

Range, Neutron Flux FUNCTIONAL UNIT 1.

Manual Reactor Trip 2.

Power Range, Neutron Flux a.

High Setpoint TOTAL ALLOWANCE

~TA 1

N.A.

7.5 8.3 1.6 1.6 17.0 4.56 0

4.56 0

0.5 0

8.41 0

~ 109% of RTP" See Note 7

~ 25% of RTP

( 5% of RTP with a time constant a 2 seconds

~ 5% of RTP" with a time constant a 2 seconds

( 25% of RTP SENSOR ERROR

~S TRIP SETPOINT N.A.

N.A.

ALLOWABLE VALUE N.A.

~ 111.1% of RTP See Note 7

~ 27.1% of RTP

( 6.3% of RTP with a time constant a 2 seconds

~ 6.3% of RTP.with a time constant a 2 seconds

~ 30.9% of RTP Source

Range, Neutron Flux 17.0 10.01 0

< 10'ps

~ 1.4 x 10 cps 7.

8.

9.

10.

Overtemperature hT 8.7 Overpower hT 4.7 Pressurizer Pressure-Low 5.0 Pressurizer Pressure-High 7.5 Pressurizer Water Level-8.0 High 6.02 Note 5

See Note 1

See Note 2

2.21 1.5 5.01 0.5 2.18 1.5 z 1960 psig

( 2385 psig

~ 92% of instrument span a 1946 psig

< 2399 psig

( 93.8% of instrument span 1.50 1.9 See Note 3 See Note 4 RTP = RATED THERMAL POWER

NOTE 3:

(Continued)

TABLE 2.2-1 Continued TABLE NOTATIONS 0.002/'F for T > T" and K, = 0 for T ~ T",

As defined in Note 1, Indicated T,, at RATED THERMAL POWER (Calibration temperature for hT instrumentation, x 580.8'F),

As defined in Note 1, and f,(bI)

=

0 for all BI.

NOTE 4:

The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3% hT span.

NOTE 5:

The sensor error for temperature is 1.9 and 1.1 for pressure.

NOTE 6:

The sensor error for steam flow is 0.9, for feed flow is 1.5, and for steam pressure is 0.75.

NOTE 7:

This value is associated with measured RCS flow ~ [293,540 gpm x (1.0 + C,)].

Technical Specification 3/4.2.3 requires this setpoint to be reduced at the rate of 1.5% of RTP for each 1%

that measured RCS flow is below [293,540 gpm x (1.0 + C,)].

1

POWER DISTRIBUTION LIMITS 3 4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR'IMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and THERMAL POWER shall be maintained within the region of permissible operation shown on Figure 3.2-3 for three loop operation and F~ shall be maintained as follows:

a.

F~ <

F"

[1.0 + PF~ (1.0-P)]

Where:

F RTP PF~

APPLICABILITY:

MODE 1.

ACTION:

F~ Limit at RATED THERMAL POWER specified in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, Power Factor Multiplier for F~ specified in the

COLR, THERMAL POWER RATED THERMAL POWER Enthalpy rise hot channel factor obtained by using the movable incore detectors to obtain a

power distribution map, with the measured value of the nuclear enthalpy rise hot channel factor F~~

increased by an allowance of 4% to account for measurement.uncertainty.

a 0 With the combination of RCS total flow rate and THERMAL POWER within the region of prohibited operation shown on Figure 3.2-3 or F~ outside the limits given in 3.2.3a.:

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

a)

Restore the combination of RCS total flow rate and'THERMAL POWER to within the'region of permissible operation, and F~

to within the limits given in 3.2.3a.,

or b)

Restore the combination of RCS total flow rate and THERMAL POWER to within the region of restricted operation and comply with ACTION b. below, or SHEARON HARRIS - UNIT 1 3/4 2-9 Amendment No.

3 4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION b.

C.

d c)

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

With the combination of RCS total flow rate and THERMAL POWER within the region of restricted operation (flow rate less than

[293,540 gpm x (1.0 + C,)], which includes measurement uncertainty for core f1ow, C as described in the Bases),

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months reduce the Power Range Neutron Flux-High Trip Setpoint to below the nominal setpoint by the same amount

(% RTP) as the power reduction required by Figure 3.2-3 and maintain F~ at a value that is less than or equal to the value of F~ at RATED THERMAL POWER.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being within the region of prohibited operation shown on Figure 3.2-3 either:

l.

Verify through RCS total flow rate determination and incore flux mapping that the combination of RCS total flow rate and THERMAL POWER are restored to within the region of permissible operation, and F~ to within the limits given in 3.2.3a.,

or 2.

Verify through RCS total flow rate determination and incore flux mapping that the combination of RCS total flow rate and THERMAL POWER are restored to within the region of restricted operation and comply with ACTION b. above, or d.

3.

Reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.l.c) and/or c.3),

above; subsequent POWER OPERATION may proceed provided that the combination of THERMAL POWER and indicated RCS total flow rate are demonstrated through RCS total flow rate comparison to be within the regions of restricted or permissible operation shown on Figure 3.2-3 and that F~ is demonstrated through incore flux mapping to be within acceptable limits prior to exceeding the following THERMAL POWER levels:

2.

3.

A nominal 50% of RATED THERMAL POWER, A nominal 75% of RATED THERMAL POWER, and Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

SHEARON HARRIS - UNIT I 3/4 2-10 Amendment No.

POWER DISTRIBUTION LIMITS 3 4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR SURVEILLANCE REQUIREMENTS 4.2.3. 1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 F~ shall be determined to be within acceptable limits:

a.

Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The RCS t'otal flow rate shall be verified to be within the regions of restricted or permissible operation of Figure 3.2-3:

a ~

b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by the use of main control board instrumentation or equivalent, and At least once per 31 days by the use of process computer readings or digital voltmeter measurement.

4.2.3.4 The RCS total flow rate indicators shall be subjected.to a

CHANNEL CALIBRATION at least once per 18 months.

4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement at least once per 18 months.

The measurement instrumentation shall be calibrated within 21 days prior to the performance of the calorimetric flow measurement.

SHEARON HARRIS - UNIT 1

3/4 2-10a Amendment No.

33.0 Proh)b)ted Operation Region 32.0 l 100.0, 32.13 x l1.0 C1 ) )

31.0 Permissible Operation Region 30.0 29.0 Restricted Operetlon Region l 100.0,29.354 x l1.0 + C1 28.0

( 92.6, 27.89 x l1.0 + C 1 ) )

27.0 88.0 90.0 92.0 94.0 98.0 98.0 100.0 102.0 104.0 Power (% RTP)

Figure 3.2-3 Allowed Measured Reactor Coolant System Total Flow Rate versus Power-Three Loops in Operation SHEARON HARRIS - UNIT 1 3/4 2-10b Amendment.

No.

POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued c.

The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained; and d.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

F~ will be maintained within its limits provided Conditions a. through d.

above are maintained.

The combination of measured RCS flow rate and THERMAL POWER must be maintained within the regions of permissible or restricted operation as shown in Figure 3.2-3 to ensure that the combination of RCS flow rate and THERMAL POWER are within the ranges considered in the mechanical and safety analyses

and, along with the measurement of F~, to ensure that the calculated DNBR will not be below the design DNBR value.

The relaxation of F~ as a function of THERMAL POWER when in the region of permissible operation allows changes in the radial power shape for all permissible rod insertion limits.

For the FSAR Chapter 15 analyses reliant on the Power Range Neutron Flux-High Trip Setting trip function, reduction of the Setpoint by the same percentage as -the required power reduction in Figure 3.2-3 (1.5%

RTP per 1%

RCS flow rate) ensures DNBR margin is maintained.

When in the region of restricted operation, defining DTo as the equivalent ET at 100%

RTP and

[293,540 gpm x (1.0 + C,)] (which includes measurement uncertainty for core flow) results in an effective OTBT setpoint reduction and maintains DNBR margins for those analyses reliant upon the OTBT trip.

The additional restrictions on F~ when in the region of restricted operation ensure that the margins gained by the power and setpoint reductions are not reduced by the normally allowable increases in radial peaking at reduced power levels.

When an F~ measurement is taken, an allowance for measurement error must be applied prior to comparing to the FR~

limit(s) specified in the CORE OPERATING LIMITS REPORT (COLR).

An allowance of 4% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System.

Margin is maintained between the safety analysis limit DNBR and the design limit DNBR.

The margin is more than sufficient to offset any rod bow penalty and transition core penalty.

When an Fo measurement is taken, an allowance for both experimental error and manufacturing tolerance must be made.

An allowance of 5% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System, and a

3%

allowance is appropriate for manufacturing tolerance.

The hot channel factor F ~(Z) is measured periodically and increased by a cycle and height dependent power factor V(Z) to provide assurance that the SHEARON HARRIS - UNIT 1

B 3/4 2-4 Amendment No.

C~

(II POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued limit on the hot channel factor, Fo{Z), is met.

V{Z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core.

The V(Z) function is specified in the COLR.

When RCS flow rate is measured, no additional allowance is necessary prior to comparison with the limit of Specification 3.2.3.

A normal RCS flowrate error of 2. 1% will be included in C which will be modified as discussed below.

The measurement error for RCS total flow rate is based upon performing a

precision heat balance and using the result to calibrate the RCS flow rate indicators.

Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a non-conservative manner.

Therefore, a penalty of 0. 1% for undetected fouling of the feedwater venturi, raises the nominal flow measurement allowance, C to 2.2% for no venturi fouling.

Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by monitoring and trending various plant performance parameters.

If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

The upper limit on measured RCS flow rate in Figure 3.2-3

[321,300 gpm x (1.0 - C,)] protects the mechanical design flow of 321,300 gpm per FSAR Table 5.1.0-1.

The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation that could lead to operation outside the acceptable region of operation.

3 4.2.4 UADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts.

A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in Fo is depleted.

A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.

The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of SHEARON HARRIS - UNIT 1

B 3/4 2-5 Amendment No.

ys P

POWER DISTRIBUTION LIMITS BASES UADRANT POWER TILT RATIO Continued a dropped or misaligned control rod.

In the event such action does not correct the tilt, the margin for uncertainty on Fo is reinstated by reducing the maximum allowed power by 3% for each percent of tilt in excess of I.

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.

The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles.

The preferred sets of four symmetric thimbles is a unique set of eight detector locations.

These locations are C-8, E-5, E-ll, H-3,'-I3, L-5, L-II, N-8. If other locations must be used, a special report to NRC should be submitted within 30 days in accordance with 10CFR50.4.

3 4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR that is equal to or greater than the design DNBR value throughout each analyzed transient.

The indicated T., value and the indicated pressurizer pressure value are compared to analytical limits of 586.1'F and 2185 psig, respectively, after an allowance for measurement uncertainty is included.

The 12-hour periodic surveillance of these parameters through instrument read-out is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

SHEARON HARRIS - UNIT I B 3/4 2-6 Amendment No.

i c*

1i

~p

ML18011A430

Text

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