ML20062C680

Amend 31 to Facil Oper Lic DPR-41,changing Tech Spec Re Refueling of Cycle 5 Oper & Auth Oper w/25 Percent Tubes in Plugged Condition

ML20062C680
Person / Time
Site:	Turkey Point
Issue date:	09/22/1978
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062C674	List: ML20062C670 ML20062C676 ML20062C680 ML20062C696 ML20062C700
References
NUDOCS 7811130083
Download: ML20062C680 (13)

Text

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,4- UNITED STATES 3'

• NUCLEAR REGULATORY COMMisslON j . Q) } WASHINGTON. D. C. 20555 Y' . ~

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FLORIDA POWER AND LIGHT COMPANY

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DOCKET NO. 50-251  ;

t TURKEY POINT NUCLEAR GENERATING STATION UNIT NO. 4 l I

AMEN 0 MENT TO FACILITY OPERATING LICENSE l

ce e No bP-41 l

1. The Nuclear Regulatory Commission (the Commission) has found that:  !

A. The application for amendment by Florida Power and Light  !

Company (the licensee) dated June 19, 1978, supplemented '

on July 10 and 20, August 9 and 16, and September 13, 1978, complies with the standards and requirements of the ,

Atomic Energy Act of 1954, as amended (the Act), and the  !

Commission's rules and regulations set fortn in 10 CFR I Chapter I; '

B. The facility will operate in conforuity with the application, f the provisions of the Act, and the rules and regulations of  !

the Commission; pd C. There is reasonacle assurance (i) that the activities authorized by this amendment can be conducted without  !

endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance  ;

with the Commission's regulations; i D. The issuance of this amendment will not be inimical to i the common defense and security or to the health and l safety of the public; and (

l E. The issuance of this amendment is in accordance with 10  !

CFR Part 51 of the Commission's regulations and all applicable i requirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 3.B and 3.0 of the Facility Operating License No. DPR-41 are hereby amended to read as follows:

3.8 Technical Soecifications i l

The Technical Specifications contained in Appendices i a and B, as revised through Amendment No. 31, are hereby incorocrated in the license. The licensee stiall operate  ;

the facility in accordance with the Technical Specifications.  !

3.0 Steam Generator Ooeration O i. Tur*ey point unit 4 shaii be brought to the coid  !

shutdown condition in order to perfor cn inspection i of the steam generators after six eqcivalent months of Cycle 5 operation from September 22, 1978. Nuclear i Regulatory Commission (NRC) approval shall be obtained  ;

before resuming power operation following this inspection.

For the purpose of this requirement, equivalent operation is defined as opergtfon with a reactor coolant temperature greater than 350 F.

2. Reactor coolant to secondary leakage through the steam  !

generator tubes shall be limited to 0.3 gpm per steam ,

generator. With an steam generator tube leakage greater than this limf t, the reactor shall be brought to the '

cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The leaking tube (s) shall be evaluated and plugged prior to resuming  ;

power operation.  ;

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3. The concentration of radiciodine in the reactor coolant  ;

shall he limited to 1.0 microcurie / gram during nomal oneration and to 30 microcuries/ gram during power j transients. '

I 4 Reactnr operation shall be teminated and HRC approval shall be obtained prior to resuming operation if orimary to secondary leakage attributable to the denting phenomena is detected in 2 or more tubes during any 20 day period.

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5. The Metal Impact Monitoring System (MIMS) shall be  !

continued in operation with the capability of detecting  :

loose objects. If the MIMS is out of service in other  !

than cold shutdown or refueling mode of operation, j this fact shall be reported to the NRC. Any abnormal  ;

indications from the MIMS shall also be reported to t the NRC by telephone by the next working day and by  !

a written evaluation within two weeks. ,

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6. Following each startup from below 350*F, core barrel f movement shall be evaluated using neutron noise techniques.

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( 4. This license anendment supercedes the Orders for Modification of License dated August 3 and 11,1977 and March 8 and June 7,1978 and is ,

effective as of the date of its issuance. [

FOR THE NUCLEAR REGULATORY COMMISSION f i

1 $Y$$

Darrell G. Eisenhut, Assistant Director I for Systems and Projects  !

Division of Operating Reactors

Attachment:

Changes to the Technical Specifications  !

O, Date of Issuance: September 22, 1978  !

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ATTACHitENT TO LICENSE AMENDMENT NO. 38  ;

l To THE TECHNICAL SPECIFICATIONS  ;

FACILITY OPERATING LICENSE NO. OPR-31  ;

i DOCKET NO. 50-250 l

. i Reolace the following page(s) of the Appendix "A" Technical Specifications with the enclosed page(s). The revised page is identified by Amendment  !

number and contains vertical lines indicating the area of change. l

(') Remove Replace l 2.3-2 2.3-2  ;

2.3-3 2.3-3  :

3.2-3 3.2-3 Figure 3.2-3 Figure 3.2-3  !

3.1-7 3.1-7 B3.2-4 B3.2-4  ;

B3.2-6 B3.2-6  :

Add Figure 2.1-lb l

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 31 TO THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. OPR-41 DOCKET N0. 50-251

(]) Replace the following page(s) of the Appendix "A" Technical Specifications with the enclosed page(s). The revised page is identified by Amendment number and contains vertical lines indicating the area of change. '

Remove Replace 2.3-2 2.3-2 2.3-3 2.3-3 3.2-3 3.2-3 Figure 3.2-3 Figure 3.2-3 3.1-7 3.1-7 '

B 3. 2-4 B3. 2-4 B3.2-6 83.2-6 9

Add Figure 2.1-lb

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. 20 40 60 80 100 120 140  ;

RATEDPOWER(PERCENT) ,

i REACTOR CORE THERMAL AND liYORAULIC SAFETY LIMITS, ,-  ;

THREE LOOP OPERATION l Figure TS 2.1-Jb  !

Amendment Nos. 3c a 31  :

. . j Reactor Coolant Temeerature l

Overcompara- l 1 AT, [Ky - 0.0107 (T-574) + 0.000453 (P-2235) - f (a q) ]

..ture AT AT,= Indicated AT at rated power, F

- T = Average temperature, F .

F = Fressuriser pressure, psig I I

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f(Aq) = a fanation of the indicated differenca I p-between top and bottom detectors of the r

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power-range nuclear ion chambers; with gains f to be selected based on nessured instrument i I

response during startup tasta such that: ,

f I** (4g qb) within +10 percent and -14 Percent where qg and qb are the percent [

power in the top and bottom halves of the l care respectively, and q g + 9b is total core power in percent of rateri power, l f(Aq) = 0. '

l O l For each percent that the magnittide of (q, j

~ 9b) exceeds +10 percent, the Delta-T trip setpoint shall be automatically reduced j hy 3.5 percent of its value at incarin power.

For each percent that the magnitude of (qg l

- 9 b) exceeds -14 percent, the Delta-T  !

trip setpoint shall he automatically reduced

. by 2 percent of itis value ac incaria pause.

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E 1 (nree Loop Operation) = 1.095*  :

(Two Loop Operation) = 0.88 "I = 1.095 for steam generator tube plagging i 25 percent i

2.3-2 Amendment Nos. 38 & 31

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Over-power AT 1 AT, 1.11 *- K -K2 (T - T') - f (aq)  !

AT, = Indicated AT se raced power, F T

= Average temperature, F ,

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T' = Indicated average temperature at nomini conditions and raced power, F Kg =.O for decreasing average temperat:me, 0.2 sec./F for increasing average temperature K

2

= 0.00068+for T equal to or more than T'; F O for T less than T'

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p,,. = Rate of change of temperature, F/see f(Aq) = As defined above , , ,

Pressurizer f

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Low Pressurizer oressure - equal to or greater than i 1835 pais. -

High Pressurizer pressurn - equal to or less than i 1385 peig. ,  !

i High Pressurizer water level - equal to or less than  !

92 of full scale. I I

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Rasetor Coolant Flow .

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' t icw reactor coolant flow - equal to or greater than (

90% of normal indicated flow (

Low reactor coolant pump notar frequency - equal to or '

greater than 56.1 Ez  ;

Under voltage on reactor coolant pump notar bus - equal ' l to or greater than 60 cf normal voltage l

l Steam Canerstors Low-lov steam generator water level - equal to or

. greater than 5% of narrow range instrument scale i

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• This factor is 1.11 for steam generator tube clugging

• 13 percent This factor is 1.10 for steam generator cume plugging > 15 percent and < 19 - t This factor is 1.08 for steam ger. orator tube plugging >19% ard '

<254.

P.41s Yac or is 0.00106 for steam generator tube plugging >194 and 125%.

2.3-3 Amendment Nos.38 5 31

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reactivity insertion upon ejection greater than 0.37. A k/k at raced power.

Inoperable rod worth shall be determined within 4 weeks.  !

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b. A control rod shall be considered inoperable if l (a) the rod cannot be moved by the CRDN, or '

(b) the rod is misaligned from its bank by more than 15 inches, or t (c) the rod drop time is not met.

c. If a control rod cannot be moved by the drive mechanism, shutdown l margin shall be increased by baron addition to compensate for the with- i drawn worth of the inoperable rod. '

3. CONTROI. RCD POSITION INDICATION i i

If either the power range channel deviation alarm or the rod deviation men- l itor alarm are not operable rod positions shall be logged once per s lif t  !

y and after a load change greater than 10% of rated power. If both alarms ,

are inoperable for two hours or more, the nuclear overpower trip shall be (

reset to 93% of rated power.

6. POWER DISTRIBUTICN I,IMITS ,!

a. Hot channel factors:

With steam generator tube plugging i 25%, the hot channel factors  ;

(defined in the basis) must meet the following limits at all times except during low power physics tests:

F ( ) 1 (2.03/P)x K(Z) , for P > .5 F (2) f (4.06) x K(2), for P < .5 b" Fg N

< 1.55 {1.+ 0.2 (1-P) }

Where P is the fraction of rated power at which the core is operating:

K(2) is the function given in Figure 3.2-3; ' is the core height location of F .

4 If predicted Fq exceeds 2.03, the pewer will be limited to the rated power multiplied by the ratio of 2.03 divided by the predicted F q, or augmented surveillance of hot channel fac*ars shall be implemented.

b. Following initial loading before the reactor is operated above 75% of rated power and at regular effective full rated power monthly intervals thereafttr, power distribution maps, using the movable detector system shall be made, to confirm that the hot channel f actor limits of the spect-fication are satisfied. For the purpose of this comparison, 3.2-3 Amendment Nos. 38 & 31

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I HOT CHANNEL FACTOR-NORMALIZED OPERATING ENVELOPE (FOR STIAM GENERATOR TUBE PLUGGING - <25% and9F =2.03) l i

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BOTTOM TOP CORE HEIGHT (FT) i i

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I FIGURI 3.2-3 Amendment Nos. 33 & 31 i I

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6.. DNS PARAMETERS The following DN5 related parameters limits shall be j maintained during power operation:  !

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a. Esastor Coolant system Tavs < 578.20F ' l

b. Pressurizar Preesure > 2220 psla* ,

s. Enestor Coolant Flow > 268,500 gym + j

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t With my of the above parsanters exceeding its limit, [

i restore the parameter to within its limit within 2 l bours or reduce thermal jouer to less than 5% of rated thermal power using normal shutdown procedures.

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Compliance with a. and b. is demonstrated by verify- I ing that each of the parameters 'is within its limits at least once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i Compliance with c. is demonstrated by verifying that l the parameter is within its limits after each refuel-  ;

Ing cycle. ,

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x. .; -

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• Limit not applicable &aring either a THEINAL POWER ramp increase in l

excess of (5%) RATE THERMAL POWE1 per minute or a TWrRMAL POWER step increase in excess of (10%) EA::Z3 N49AL PQWZ1, ]

+ 3amator Coolanc flow > 268,500 gym for steam generator tube plugging

. < 13:.

Reactor Coolant Flow ~> 263,130 gym for steam generacce tube plugging

> 15 and 1 192.

Reactor Coolant Flow > 255,075 gym for steam generator cube plugging

> 15% and $ 25 .

3.1 -7 Amendment Nos. 38 & 31

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An upper bound envelope as defined by the normalized peaking factor axial dependence of Figure 3.2-3 has been determined to be consistent with the

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technical specifications on power distribution control as given in Section 3.2.  !

l When an 47 asasurement is taken, both experimental error and manufacturing  !

t tolerance must be allowed for.' Five percent is the appropriate experimental

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uncertainty allowance for a full core map takan with the movable incore l

detector fluz mapping system and three percent is the appropriate allowance l

for meaufacturing tolerance.

• In the specified limit of E g, there is an 8 percent allowance for uncertain-ties wnich means that normal operation of the core is expected to result in  !

[g11.55/1.08. The logic behind the larger uncertainty in this case is that (a) normal perturbations in the radial power shape (e.g., rod =4 ==14sa- .i ment) affect [g, in most cases without necessarily affecting F , (b) although the operator has a direct influence on F through movement of rods, and can limit  ;

' 9 q it to the desired value, he has no direct control over F' g and (c) an error in the predictions for radial power shape, which may be detected during

[

startup physics tests can be compensated for in 7, by tighter axial control,  !

but compensation for g E is less readily availabiw When a measurement of l

[g is taken, experimental error must be allowed for and 4% is the appro-l

{~} priaca allowance for a full core map takan with the movable incere detector  !

fluz mapping system.  !

i Measurements of the het ek=a==1 factors are required as part of start-up  ;

physics tests, at least once each full rated power month of operation, and  ;

whenever abnormal power distribution conditions require a reduction of core (l power to a level based on ==aanM hot eh====1 factors. The incore map l emiran following initial loading provides confirmation of the basic nuclear l l

l l

1 33.2-4 Amendment Nos 38 & 31

Flux Difference (4$) and a reference value which corresponds to the full i

design power equilibrium value of Axial Offset (Axial Offset = A$/ fractional power). The reference value of flux difference varies with power level and burnup but expressed as axial offset it varies only with burnup.

The technical. specifications on power distribution control assure that the F nyper bound envelope as defined by Figure 3.2-3 is not exceeded and zenon distributions are not developed which at a later time, would cause f;reater local power p-Ws even though the flux difference is then within c'se limits specified by the procedure.

Q The target (or reference) value of flux difference is determined as follows.

At any time that equilibrium zenon conditions have been establisbed, the in-dicated flux difference is noted with part length rods withdrawn from the core and with the full length rod control rod bank more chan 190 steps withdrawn (i.e., normal rated power operating position appropriate for the cima in life.

Control rods are usually withdrawn farther as burnup proceeds). This value, divided by the fraction of design power at which the core was operating is the

design power value of the ta'rget flux difference. Yalues for all other core power levels are obtained by multiplying the design power value by the fractional power. Since the indicated equilibrium value was noted, no allowances for azcore detector errer are necessary and indicated deviation of 3 +5% AI are permitted from the indicated reference value. During periods J where extensive load following is required, it any be tapractical to establish the required core conditions for measuring the target flux difference every rated power month. For this reason, methods are permitted by Ices 6c of Section 3.2 for updating the target flux differences. Figure 33.2-1 shows a typical construction of the target flux difference band at BOL and Figure 33.2-2 shows the typical variation of the full power value with burnup.

Strict control of the flux difference (and rod position) is not as necessary during part power operation. This is because xenon distribution control at part power is not as significant as the control at full power and allowance has been made in predicting the heat flux peaking factors for less strict con-trol at part power. Strict control of the flux difference is not possible during certain physics casts or during the required, periodic excore calibra-33.2-6 Amendment Nos. 38 & 31