Text

Proposed Tech Specs,Changing Bundle Heat Generation Rate Info for Third Cycle
	ML20206H124
Person / Time
Site:	River Bend
Issue date:	11/18/1988
From:	; GULF STATES UTILITIES CO.
To:	;
Shared Package
ML20206H120	List: ML20206H124; ML20206H138; RBG-29376, Application for Amend to License NPF-47,revising Tech Specs to Change Bundle Heat Generation Rate Info for Third Cycle. Rev 0 to 23A5934 Supplemental Reload Licensing Submittal for River Bend Station,Reload 2,Cycle 3, Encl.Fee Paid;
References
	NUDOCS 8811230093
	Download: ML20206H124 (8)
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D 3/4.2 POWEROISTRIBUTIbNLIMITS ntiCE.1YED 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE OCT 29 ic87 SOC LIMITING CONDITION FOR OPERATION 3.1.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown_in ras 1 2 1-1, 3. 2.1-2, 3. 2.1-3, 3. 2.1-4, 3. 2.1-5, ead 3. 2.1-6, l (3,.l. T-7,"a3d, ,.F 1 f.S APPLICABILITW lPETATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

ACTION: cyc 1-7 o 3 .

its of Figure 3.2.1-1, 3.2.1-2, 3.2.1-3, With an APL ex eed ng t 3.2.1-4, 3.2.1-5,.ae 3.2.1-6,J' initiate corrective action within 15 minutes and restore APLHGR to within the required limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 25% of RATED THERHAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . .

SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal t'o or less than'the limits deta mined Jrn= rinures 3,2.1-1, 3. 2.1-2, 3. 2.1-3, 3. 2.1-4, 3. 2.1-5, . nae 3. 2.1-6: l

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ce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and

c. Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with a '.1MITING CONTROL ROD PATTERN for APLHGR.

d. The provisions of Specification 4.0.4 are not applicable.

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The limits on Figures 3.2.1-7 and ^^3.2.1-8 are to be used +A ^ - ^

only for

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G011230093 8G1110 FDR ADOCK 030004'38 P PDC .

3/4 2-1 Amendment No. A s-RIVER BENO - UNIT 1

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AWRAGE' PLANAR EXPOSURE (GWd/t)

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3.2.1-7 WAXIMUM AWRAGE PLANAR UNEAR HEAT GENERATION RATE (MAPtHGR) WRSUS AWRAGE PLANAR EXPOSURE - BS3228 3/4 2-68

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AWRAGE PWAR EXPOSURE (GWd/t)

FIGURE 3.2.1-8 MA)0 MUM AWRAGE PLANAR UNEAR HEAT GENERA 110N RATE (MAPt.HCR) YERSUS AWRAGE PLANAR EXPOSURE - 85322C 3/4 2-6c

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u POWER O!STRIBUTION LIMITS

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3/4.2.4 LINEAR HEAT GENERATION RATE LIMITING CON 0! TION FOR OPERATION 4.4Y/ 8 3.2.4 Tha t HEAT G NERA ION RA E (LHGR) shall not exceegk 13 .4

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APPLICA8TL :TY:~ OPERA 110 MAL CON 0! TION 1, when THERMAL POWER is greater than er equal to 20% of RATED THERMAL POWER.

ACTION:

With the LHGR of any fuel rod exceeding the Italt, initiate corrective action within 15 minutes and restore the LHGR to within the limit w thin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or i

reduce. THERMAL POWER to les: :. nan 25% of RATED THERMAL POWE: eithin the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.4 LHGR's shall be determined to be equal to or 1bss than the limit:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . *

b. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and

c. Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating on a LINITING CONTROL R00 PATTERN for LHGR.

! d. The provisions of Specification 4.0.4 are 6ot applicable..

GE6X8EB Fuol in an

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RIVER BEND UNIT 1 3/4 2-11 1

RECEIVED OCT 2 91987 SDC 3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section assure that the peak cladding temper-ature following the postulated design basis loss-of-coolant accident will not exceed the 2200*F limit specified in 10 CFR 50.46.

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE The peak cladding temperature (PCT) following a postulated loss-of-coolant accident is primarily a function of the average heat generation rate of all the rods of a fuel assembly at any axial location and is dependent only second-arily on the rod to rod power distribution withh an' assembly.'The peak clad temperature is calculated assuming a LHGR for the highest powered rod which is equal to or less than the design LHGR corrected for dentification. This LHGR times 1.02 is used in the heatup code along with the exposure-dependent steady state gap conductance and rod-to-rod local peaking factor. The Technical Specification AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) is this LHGR of the highest powered rod divided by its local peaking factor. .The Ifmiting value for APLHGR is shown in 9"= 1 ? 1-1. 1 ?.1-2, ?.2.1-2, ?.2.11 , 3.2.1-0 o

. , _ 3. 2. a.

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The daily requirement for calcuIatin'g APLHGR.when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER is sufficient since power distribu

tion shift.s are,very, slow when there have not been significant power or control rod changes. The requirement to calculate APLHGR within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the com-pletion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER ensures thermal limits are met after power distribution shifts while still allotting time for the power distribution to stabilize. The requirement for calculating APLHGR after initially determining a LIMITING CONTROL ROD PATTERN exists ensures that APLHGR will be known following a change in THERMAL POWER or power sh6pe that could place operation into a condition exceeding a thermal limit.

The calculational procedure used to establish the APENGR showny ;"ns

0. 2.1-1, 0. 2.1- 2, 0. 2.1 3, 0. 2.1 -4, 0. 2.1- 0 ud 3. 2.1 0 is based on a los s-of-coolant (

accident analysis. The analysis was performed using General Electric (GE)

Calculational models which are consistent with the requirements of Appendix K to 10 CFR 50. A complete discussion of each code employed in the analysis is presented in NEDE-20566(1) .

Differences in this analysis compared to previous analyses can be broken down as follows. ,

a. Input Changes

1. Corrected Vaporization Calculation - Coefficients in the vaporization '

correlation used in the REFLOOD code were corrected. ,

2. Incorporated more accurate bypass areas - The bypass areas in the top guide were recalculated using a more accurate technique.

8 3/4 2-1 Amendment No. 12 RIVER BEND - UNIT 1 I

DESIGN FEATURES 5.3 REACTOR CORE w

FUEL ASSEMBLIES .$f,55*S?Fthinsert5.3.b I

y 5.3.1 The reactor core shall contain 624 fuel assemblies. "- ' "" ' ---- y thcIl ::nt:in 0 feel 7:d :nd tu: w:t:r r:40, :11 :1:d =fth I4ecaley-2. Each f;;l red :h:11 h;v: ; nesinel ective fuel length ef 150 inchee. The-intt f el '

cere !: ding cht!! 5:v: i r r ter :v:r:;: :nrich::nt :f 1.25 e:f;ht p:r:ent U-235. .010:d fe:1 55:!' 5: :f=fler *= phy:ft:1 d::fgn t the 8-iti:1 ::re 10: din;. _

CONTROL R00 ASSEMBLIES 5.3.2 The reactor core shall contain 145 control rod assemblies, each consisting of a cruciform arr:y Of stainless steel tubes surrounded by a cruciform shaped stainless steel sheath. Each tube shall contain 143.7 inches of boron carbide (84C) powder.

5.4 REACTOR COOLANT SYSTEM OESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

In accordance with the code requirements specified in Section 5.2 of a.

, the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, '

b. For a pressure of:

1. 1250 psig on the suction side of the recirculation pump.

2. 1650psigfromtherecirculationpumpdischargetotheotdiet side of the discharge shutoff valve.

3. 1550 psig from the discharge shutoff valve to the jet pumps.

c.. For a temperature of 575'F.

VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 16,000 cubic feet. .

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RIVER BEND - UNIT 1 5-5

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INSERT 5.3.1 Each assembly consists of zirconium alloy fuel and water rods arranged in a nominal 8x8 array. The fuel rods contain uranium dioxide fuel pellets with active lengths generally ranging between 144 and 150 inches. These fuel assemblies are limited to those that have been analyzed with NRC approved codes and methods and have been shown to comply with all of the criteria in the latest approved revision of GESTAR(NEDE-24011-P-A-US).

O ENCLOSURE 2

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ML20206H124

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