ML20033G794

Corrected Pages to Amend 88 to License NPF-12,re cycle- Specific Parameters

ML20033G794
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Site:	Summer
Issue date:	04/05/1990
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CORRECTION TO LICENSE AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert P,a2'S 3/4 2 6 3/4 2-6 3/4 2 6b 3/4 2 6b 3/4 2 6c 3/4 2-6c 3/4 2 8 3/4 2-8 3/4 2-9 3/4 2-9 8 3/4 2 5 8 3/4 2-5 6-18a 6-18a i

J iN)04120140 900403 PDR ADOCK OSCn>O395 P

FDC

' POWER DISTRIBUTION LIMITS

$URVEILLANCE REQUIREMENTS (Continued) i e.

With the maximum value of F (z)

K(z)

{

f over the core height (2) increasing since the previous determination of F (z) either of the following actions shall be taken:

i (1) F (2) shall be increased by 2% over that specified in l

Specification 4.2.2.2c. or I

F((z)shallbemeasuredatleastonceper7EffectiveFullPower (2) t Days until two successive maps indicate that the maximum value of F (2) f K(z) over the core height (z) is not increasing.

f.

With the relationships specified in Specification 4.2.2.2c above not i

being satisfied:

(1) Calculate the maximum percent over the core height (2) that F (2) excetds its limit by the following expression:

l q

S F (2) x W(2)*!

- 1rl x 100 for P 2 0.5 RTP F

x K(2) n

,p r

9

' F (z) x W(2)"

{

- 1, x 100 f or P < 0. 5 l

gyp

• K(2)

I l

[

i I

4 SLMMER - UNIT 1 3/4 2-6 Aniendment No. 7), 88 I

l P0wfR DISTRIBUTION LIMITS i

SURVIILLANCE RfQUIREMENTS (Continued) i L

i b.

During Base Load operation, if the THERMAL POWER is decreased below

(

NO APL then the conditions of 4.2.2.3.a shall be satisfied before i

re entering Base Load operation.

4.2.2.4 During Base Lead Operation F (z) shall be evaluated to determine if n

F (z) is within its limit by:

j n

a.

Using the movable incore detectors to obtain a power distribution

)

map at any THERMAL POWER above APLND, b.

Increasing the measured F (r) component of the power distribution g

map by 3% to account for manufacturing tolerances and further i

increasing the value by 5% to account for measurement uncertainties.

E 1

Verify the requirements of Specification 3.2.2 are satisfied.

c.

Satisfying the following relationship:

f RTP M

IQ (2) < 0 x K(z) f,7 p, gpgND P x W(2)gg

'l RTP l

)

where:

F (2) is t.he measured F (z).

The F limit is F n

g g.

P is the relative THERMAL POWER.

W(2)gg is the cycle dependent j

function that accounts for limited power distribution transients j

F}P(z)andW(z)gt encoJntered during normal operation.

K are specified in the CORE OPERATING LIMITS REPORT as per

[

Specification 6.9.1.11.

d.

Measuring F (2) in conjunction with target flux difference determination according to the following schedule:

1.

Prior to entering BASE LOAD operation after satisfying Sec-tion 4.2.2.3 unless a full core flux map has been taken in the i

previous 31 EFPD with the relative thermal power having been j

ND maintained above APL for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to mapping, and i

2.

At least once per 31 Effective Full Power Days, e.

With the maximum value of f((z)

K(z) t SUMMER - UNIT 1 3/4 2-6b Amendment No. 75. 88

. POWER DISTRIBUTION LIMITS i

l

$URVEILLANCE REQUIREMENTS (Coatinued) over the core height (2) incr6asing since the previous determination l

g of F (z) either of the following actions shall be taken g

1.

F (2) shall be increased by 2 percent over that specified in 4.2.2.4.c, or F((t)shallbemeasuredatleastonceper7EffectiveFull 2.

Power Days until 2 successive maps indicate that the maximum value of M

F (z)

K(2) over the core height (2) is not increasing, f.

With the relationship specified in 4.2.2.4.c above not being satisfied, either of the following actions shall be taken:

1.

Place core in an equilibrium condition where the limit in 4.2.2.2.c is satisfied, and remeasure F (2), or 2.

Comply with the requirements of Specification 3.2.2 for F (z) exceeding its limit by the maximum percent calculated g

over the core height (z) with the following expression:

M i

~F (z) x W(z)g g

9 0

1 >x 100 for P > APL I

RTP F

• KIII O

l

\\L P

g.

The limits specified in 4.2.2.4.c. 4.2.2.4.e. and 4.2.2.4 f above are not applicable in the following core plane regions:

1.

Lower core region 0 to 15 percent, inclusive.

2.

Upper core region 85 to 100 percent, inclusive.

4.2.2.5 When F (z) is measured for reasons other than meeting the requirements g

of Specification 4.2.2.2 an overall measured F (z) shall be obtained from a g

power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

SUMMER - UNIT 1 3/4 2-6c Amendment No. M, 88

P0wtR DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow I

rate and R shall be maintained within the region of allowable operation as specified in the CORE OPERATING LIMITS REPORT (COLR) tigure entitled RCS Total Flow Rate Versus R for Three Loop Operation.

Where:

F$H p,

FRTP(1.0 + PF3g(1.0 P))

THERMAL POWER b.

P = RATED THERMAL POWER,

q = Measured values of F"q obtained by using the movable incore c.

F l

detectors to obtain a power distribution map.

The measured valuesofFfg shall be used to calculate R since the RCS Total Flow Rate Versus R figure in the COLR includes measurement uncegtaintiesof2.1%forflowand4%forincoremeasurement i

of F3g, and d.

FRTP= The FN limit at RATED THERMAL POWER specified in the COLR.

g e.

PF3g = The Power Factor Multiplier specified in the COLR.

APPLICABILITY:

MODE 1.

ACTION:

With the combination of RCS total flow rate and R outside the region of accept-able operation specified in the COLR:

a.

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

1.

Restore the combination of RCS total flow rate and R to within the above limits, or 2.

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that the combination of R and RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

SUMMER UNIT 1 3/4 2 8 Amendment No. J5, (p, 75, BB

k i

POWER DISTRIBUTION LIMITS l

LIMITING _ CONDITION FOR OPERATION f

t i

ACTION.

(Continued)

[

c.

Identify and correct the cause of the out-of-limit condition prior f

to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION items a.2, and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of R and indicated RCS total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comparison, to be within the region 1

of acceptable operation specified in the COLR prior to exceeding the l

following THERMAL POWER levels:

1.

A nominal 50% of RATED THERMAL POWER, j

2.

A nominal 75% of RATED THERMAL POWER, and 3.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95% of RATED THERMAL POWER.

s SURVEILLANCE REQUIREMENTS i

I 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2,3.2 The combination of indicated RCS total flow rate and R shall be determined to be within the region of acceptable operation specified in l

the COLR.

4 a.

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

loading, and b.

At least once per 31 Effective Full Power Days, f

4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation specified in the COLR at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i

when the most recently obtained value of R obtained per Specification 4.2.3.2, l

is assumed to exist.

l 4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL 1

CALIBRATION at least once per 18 months.

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

l l

I SUMMER - UNIT 1 3/4 2-9 Amendment No. #5, 75, 88

POWER DISTRIBUTION LIMIT o

BASES t

HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RI$[

H01 CHANNEL FACTOR (Continued) 3/4.2.5 DNB PARAMETERS t

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 in the core at or above the design limit throughout each l

analyzed transient.

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

1 l

$UMMER - UNIT 1 B 3/4 2-5 Amendment No. 45, 55, 60, 75, 88

j j

ADMINISTRATIVE CONTROLS I

CORE OPERATING LIMITS REPORT (Methodology for Specification 3.1.1.3 - Moderator Temperature Coef ficient, 3.1.3.5 - Shutdown Bank Insertion Limit. 3.1.3,6 -

Control Bank Insertion Limit. 3.2.1 - Axial Flux Dif ference, 3.2.2 -

1 Heat Flux Hot Channel Factor, and 3.2.3 Nuclear Enthalpy Rise Hot I

i Channel Factor).

b.

WCAP-10216-P-A " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", June 1983 (W Proprietary),

j h

(Methodology for Specifications 3.2.1 - Axial Flux Difference t

(Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (FQ Methodology for W(Z) surveillance requirements).)

c.

WCAP-10266-P-A, Rev. 2 "THE 1981 VER$10N OF WESTINGHOUSE EVALUATION 4

MODEL USING BASH CODE", March 1987 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).

i The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear i

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 there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector, i

I i

i i

F i

SUMMER - UNIT 1 6-18a Amendment No. 88

,