ML19323G363

Tech Spec Changes to Section 3/4.2 Re Power Distribution & Average Planar Linear Heat Generation Rate

ML19323G363
Person / Time
Site:	Brunswick
Issue date:	05/23/1980
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19323G359	List: ML19323G358 ML19323G363 ML19323G365
References
NUDOCS 8006020237
Download: ML19323G363 (9)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

f3 3/";2 POWER DISTRIEUTION LIMITS ,

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3/*.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITI':S CONDITION FOR OPERATION 3.2.1. All AVERAGE PLANAR LINEAR HEAT GENERATION RATES ( APLHGR's) for eacn type of fuel as a function of AVERAGE PLANAR EXPOSURE snell not exceed the limits shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5, or 3.2.1-6.

APPLICA3ILITY: CONDITION 1, wnen THERMAL POWER > 25% of RATED THERMAL POWER.

ACTION:

With an APLHGR exceeding the limits of Figure 3.2.1-1, 3.2.1-2, 3.2-1-3, 3.2.1-4, 3.2.1-5, or 3.2.1-6, initiate corrective action within 15 minutes l

and continue corrective action so that APLHGR is within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POL'ER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REOUIREMENTS 4.2.1 All APLHGR's shall be verified to be equal to or less than the applicable limit determined frem Figure 3. 2'.1 -1, 3. 2 .1 - 2 , 3. 2.1 - 3,

3. 2.1-4, 3. 2.1-5, or 3. 2.1-6 : t

a. At least once per 24 hcurs,

b. Whenever THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, and

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

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FUEL TYPE P8DRB285 (P8x8R)

MAXIMUM AVERAGE PLANAR LINEAR llEAT GENERATION RATE (MAPLilGR)

VERSUS AVERAGE PLANAR EXPOSURE 3

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FUEL TYPE P8DRB26511 (P8x8R)

MAXIMUM AVERAGE PLANAR IiNEAR HEAT GENERATION RATE sMAPLilGR)

VERSUS AVERAGE Pl_aAR EXPOSURE FIGURE 3.2.1-6

POWER O!STRIBUTION LIMITS 3 /4. 2. 2 APRM SETPOINTS LIMIT!NG CONDITION FOR OPERATION

. 3.2.2 The flew biased APRM scram trip setpoint (S) and red block trip set-point (Sgg) shall be established according to the following relationships:

S 1 (0.66W + 54%) T Sgg 1 (0.66W + 42%) T where: 5 and 5,0 are in percent of RATED THERMAL POWER, W = Loop recirculation flow in percent of rated flow, T = Lowest value of the ratio of design TPF divided by the MTPF obtained for any class of fuel in the core (T 1 1.0),and Design TPF for 8x8 fuel = 2.45.

Design TPF for 8x8R fuel = 2.48.

Design TPF for P8x8R fuel = 2.48. l APPLICABILITY: CONDITION 1, when THERMAL POWER > 25% of RATED' THERMAL POWER.

ACTION:

With S or S g exceeding the allowable value, initiate corrective action within15m1$utesandcontinuecorrectiveactionsothat5and5 are within the required limits withip. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWEk0to less than 25% 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 />'.

SURVEILLANCE REOUIREMENTS 4.2.2 The MTPF for each class of fuel shall be determined, the value of T calculated, and the flow biased APRM trip setpoint adjusted, as required:

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. Whenever THERMAL POWER has been increased by at least 15% of

, RATED THERMAL POWER and steady state operating conditions

. have been established, and

. Initially anc at least once per 12 hcurs when re react:r is cperating with a LIMITING CONTROL ROC PATTEP." #:r 'iTPF.

BRUNSWICK-L' NIT 1 3/4 2-6

POWER DISTRTBUTTON LIMfTS -

3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR), as a function of core flow, shall be eaual to or greater than MCPR x the Kfshown in Figure 3.2.3-1 where MCPR values are: l

- ._ BOC3* to EOC3** E0C3-2000 M!iD/t

- 2000 MWD /t to EOC3 (8x8 fuel) 1.24 1.30 (8x8R fuel) 1.24 1.30 (P8x8R fuel) 1.30 1.32 APPLICABILITY: CONDITION 1, when THERMAL POWER > 25% RATED THERMAL POWER ACTION:

With MCPR less than the applicable limit determined from Figure 3.2.3-1 ,

initiate corrective action within 15 minutes and continue corrective action so that MCPR is equal to or greater than the applicable limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWER TO LESS THAN 25% 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 />.

SURVEILLANCE REOUIREMENTS 4.2.3 MCPR shall be determined to be equal to or greater than the applicable limit determined from Figure 3.2.3-1 :

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. Whenever THERMAL POWER has been increased by at least 15%

of RATED THERMAL POWER and steady state operating conditions have been established, and

c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is Operating with a LIMITING CONTROL ROD PATTERN for MCPR.

• Beginning of Cycle 3

• • End of Cycle 3 BRUNSWICK - UNIT 1 3/42-7

TABLE 3.3.4-2

$ C0tlTROL R00 WITilDRAWAL BLOCK IllSTRUMEtlTATION SETP0 lilts k U

-.t.i.l'. FullCTION AND INSTRUllENT TRHtBER TRIP SETP0 lilt ALL0llABLE VALUE

1. APRf1(C51-APRM-Cll.A,B,C,0,E,F) _

a. Upscale (Flow Biased) 1 (0.66 W + 42%) T* s (0.66 41 + 42%) T*

b. Inoperative NA MIPF flA MIFF

c. Downscale > 3/125 of full scale > 3/125 of full scale

d. Upscale-(Fixed) < 12% of RATED TilERf1AL P0 lier < 12% of RATED TilERMAL POWER

2. R00 BLOCK M0tilTOR (C51-RBM-Cll.A,0)

a. Upscale < (0.66W + 41%) T* < (0.66 W t 41%) T* l

h. Inoperative NA MIPF flA MIPF

c. Downscale > 3/125 of full scale > 3/125 of full scale

3. S0lldCE RANGE MONITORS (C51-SRM-K600A,B,C,0) y

a. Detector not full in NA 5

NA 6

b. Upscale 1 1 x 10 cps s 1 x 10 cps

c. Inoperative NA NA

d. Downscale > 3 cps

> 3 cps .

4. IllTElti1EDI ATE RANGE MONITORS (C51-IRM-K601 A,8,C,D,E,F ,G,II)

a. Detector not full in NA HA

h. Upscale . < 100/125 of full scale < 108/125 of full scale

c. Inoperative NA NA

d. Downscale > 3/125 of full scale > 3/125 of full scale

• T=2.45 for 8x8 fuel.

T=2.48 for~8x8R fuel.

T=2.48 for P8x8R fuel. l 0

3/4.2 POWER DISTRIBUT10ft LIf1ITS B'ASES ti The specifications of this section assure that the peak cladding temoerature following the postulated design basis loss-of-coolant accident will not exceed the 2200'F limit specified in the Final Acceptance Criteria (FAC) issued in June 1971 considering the postulated effects of fuel pellet densification.

3/4.2.1 AVERAGE PLAilAR LIf1 EAR HEAT GEi1EPATI0t1 RATE This specifi:ation assures that the peak cladding tempera'.ure following the postulated design basis loss-of-coolant accidenn will not exceed the limit specified in 10 CFR 50, Appendix K.

The peak cladding temperature (PCT) following a postulated loss-of-coolant accident is primarily a function of the average heat genera-tion rate of all the rocs of a fuel assembly at any axial location and is dependent only seconcarily on the rod to rod power distribution within a 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 densification. 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 Specifica-tion APHGR is this LHGR of the highest powered rod divided by its local peaking factor. The limiting value for APLHGR is shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5, and 3.2.1-6. l The calculational procedure used to establish the APLHGR shown'en Figura 3.2.1-1 thru 3.2.1-6 is based on a loss-of-coolant accident analysis.l 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 prcsented in Reference 1. Differences in this analysis ccmpared to previous analyses perfomed with Reference 1 are: (1) The analyses assumes a fuel assembly planar power consistent with 10h of the MAPLHGR shown in Figures 3.2.1-1, and 3.2.1-2; (2) Fission product decay is computed assuming an energy release rate of 200 MEV/ Fission; (3) Pool boiling is assumed after nucleate boiling is lost during the flow stagna-tion period; (4) The effects of core spray entrainment and counter-current flow limitation as described in Reference 2, are included in the reflooding calculations.

A list of the significant plant inout carameters to the loss-of-cociant accident analysis is presented in Bases Table 5 3.2.1-1.

BRUNSWICK-UNIT 1 B 3/4 2-1

~

. POWER DISTRIBUTIOil LIMITS .'

BASES 3/4.2.2 APRM SETPOIrlTS .

The fuel cladding integrity safety limits of Specification 2.1 were based on a TOTAL PEAKTNG FACTOR of 2.45 for 8x8 fuel and 2.48 for 8x8R and P8x8R fuel. The scram setting and rod block functions of the APRM instruments must be adjustad to ensure that the MCPR does not become less than 1.0 in the degraded situation. The scram settings and rod block settings are adjusted in accordance with the formula in this specification when the combination of THEREM. POWER and peak flux indi-cates a TOTAL PEAKING FACTOR greater than 2.45 for 8x8 fuel and 2.48 for 8x8R and P8x8R fuel. The method used to determine the design TPF shall be consistent with the method used to determine the MTPF.

3 /4. 2. 3 MIftIMUM-CRfU CAL POWER RATIO The required operating limit MCPR's at steady state operating conditions as specified'.in Specification 3.2.3 are derived from the Established

~ '

fuel cladding; integrity' Safety t MCPR of 1.07, and an analysis of abnormal operational transients For any abnent.a1 operating tran-sient analy, sis evaluation with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decr. ease below the Safety Limit.MCPR at any time during the transient assuming instrument trip. setting as given in Specification 2.2.1. .

To assure that the fuel cladding integrity Safety Limit is not exceeded during any anticipated abnormal operational transient, the most limiting transients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO (CPP). The type of transients evaluated were loss of flow, increase in pressure and power, positive reactivity insertion, and coolant temperature decrease.

The limiting transient which determines the required steady state MCPR limit is the turbine trip with failure of the turbine by pass. This transient yields the largest a MCPR. When added to the Safety Limit MCPR of 1.07 the required minimum operating limit MCPR of Specification 3.2.3 is obtained. Prior to the analysis of abnonnal o erational tran-sients an initial fuel bundle MCPR was determined. This carar.eter is based on the. bundle flow calculated by a GE multi-channel steady sjate flow districution medel as described in Secticn 4.a of itECO-20360' I and On core parameters snown in Reference 3, respense to Iters 2 and 9.

BRUNSWICK-UNIT 1 S 3/4 2-3 i l

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