View source for L-77-172, Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted as Result of Re-evaluation of ECCS Cooling Performance Calculated in Accordance with Approved Westinghouse Evaluation Model

{{Adams
| number = ML18227D839
| issue date = 06/08/1977
| title = Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted as Result of Re-evaluation of ECCS Cooling Performance Calculated in Accordance with Approved Westinghouse Evaluation Model
| author name = Uhrig R
| author affiliation = Florida Power &amp; Light Co
| addressee name = Stello V
| addressee affiliation = NRC/NRR
| docket = 05000250, 05000251
| license number = DPR-031, DPR-041
| contact person = 
| case reference number = L-77-172
| document type = Legal-Affidavit, Letter type:L, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Safety Evaluation
| page count = 38
}}

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Mr.      Victor Stello'ROM:          4=
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Florida Miami, Fla Power & Light:. Company DATC Of" DOCUt'ICIfT 6/8/77 DATE nCCEIVCD Mr. Robert         ED  Uhrig                                                6/13/77 ETTEn                                     ~oronfzED                         pnop                             ,INPUT FoflM                     IQUMOEn OF COPIES fIECEIVCD henIOINAL.."'>>
CfcoPv DEScnIPTION
                                               ~NcL'ASSIFIED,                                  l gc      g~C~
specs'~
ENCLOSUfiE "II lf Amdt, to-OI/change                  to Appendix A tech I
                                                                                                                             ,sunmitted as a result of a re-evaluation of ECCS cooling performance.,;
                                                                                                         . notorized 6/8/77 ' ~ ~ ~
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IV 0      e Regulatory'ocks+                   l!
FLORIDA POWER & LIGHT COMPANY June 8, 1977 L-77-172 Office of Nuclear Reactor Regulation                                           II Attention: Mr. Victor Stello, Director                                   AO Division of Operating Reactors                             'ggl (0 U. S. Nuclear Regulatory Commission                                           ~$ 7 Washington, D. C. 20555

==Dear Mr. Stello:==
u.>.
Re:   Turkey Point, Units 3 and 4 Docket No. 50-250 and 50-251 Proposed Amendment to Facility O~eratin Licenses DPR-31 and DPR-41 In accordance with     10 CFR    50.30, Florida Power & Light Company (FPL) submits      herewith     three (3) signed originals and forty (40) copies      of  a   request   to amend Append'x A of Facility Operating      Licenses     DPR-31   and DPR-41.
This proposal is being submitted as a result of a re-evaluation of ECCS cooling performance calculated in accordance with an approved Westinghouse Evaluation Model. The proposed change is described below and shown on the accompanying                  Technical Specification pages bearing the date of              th's   letter     in the lower right hand. corner.
Pa e  3.2-3 Specification 3.2.6.a is revised such tnat the limit on the Heat Flux Hot     is Channel Factor (Fq) from 2.22 to for both   Units  3  and   4      reduced
: 2. 20 for steam ger.gator   tube  plugging  in  excess of 10%.
Pa es  B3.2-4 and B3.2-6 Pages  B3.2-4 and B3.2-6 present the basis fo" the revised limit on Fq for both Units 3 and 4.
PEOPLE... SERVING PEOPLE

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Office of Nuclear Reactor Regulation
'Attention: Mr. Victor Stello, Director Page Two The proposed    amendment has been reviewed by the Turkey Point.
Plant Nuclear Safety Committee and the Florida Power 6 Light Company Nuclear Review Board.
not  involve   an           unreviewed They have concluded that it does safety question. A safety evaluation is attached.
Very truly yours,
 ,~g.-C'~
E. Uhrig g/l'obert Vice President REU/WAK/cmp Attachments I
cc:   Mr. Norman C. Moseley, Region              II Robert Lowenstein, Esquire

reactivity insertion u~ .-. =-'.ection greater than 0.3Z 4 k/k at rated po.eQ:oopeeahle rod worth shall be determined withitn -'eeks.
: b. A control zod shall be cons="ezed inoperable             if (a) the zod cannot be moved by the CRT/, or (b) the rod is misaligned zro its ban'c by more than 15 inches, o" (c) the rod drop time is not net.
: c. If  a contzol rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate          f'r the withdrawn worth of the. inoperable rod.
: 5. CONTROL ROD POSITIO'.I     INDICATION If either    the power range channel deviation alarm or 1
the rod deviation monitor alarm are not operable rod   '
   ~ positions shall be logged once per shift and after a load change greater than 10% of rated power.             If both are inoperable for'wo hours or moze,. the nuclear       'larm overpower trip shall be reset to 93% of rated power.
: 6. POLER DISTRIBUTIO'8      LIMITS
: a. At  all   times except during low power physics tests, th'e hot channel factors defined in the basis must e
meet the following limits:
F (Z) < (2.22/P) x K(Z) zor P > .5 F (Z) < (4.44) k K(Z) for 'P < .5 q
F~    < 1.55    fl + 0  2 (1-P)1 where   P   is the'raction of rated power at which the core is operating. K(Z) is the function given 'in Figure 3.2-3 and Z is the core height location of Fg For tube plugging in excess of 10@,
values become (2.20/P) and. (4.40) respectively.
: b. Following     initial loading    before the reactor is operated above 75% of rated power and at regular effective full rated power monthly intervals.,
thereafter, power distribution maps, using the
        'ovable detector system shall be made, to conform that the hot channel factor limits of the specifica-tion are satis ied. For the purpose of this comparison, t
3~2 3                             6/8/77

A An  upper bound envelope of 2.22 "times the nor. I'==-'eeking factor axial dependence of Figure 3.2-3 has been determined "o '=-.= consistent -~ith the
 . technical specifications on power distribution c-n =ol as given in Section 3.2.
  ,Vhen an F    measurement is taken, both ezpe ~ental error and manufacturing tolerance must be allowed for. Five percent is the appropriate experimental uncertainty allowance for a full core map taken with the movable incore detector flux mapping system and three percent is the appropriate allowance for manufacturing tolerance.
In the specified li=~t o" P>H, there is an 8 percent allowance for uncertz~-
ties which means that no-. mal operation of the core is expected to result in P~(1.55/1.08. ~~e logic behind the larger uncertainty in this case is that (a) normal perturbations in the radial power shape (e.g., rod misalign-ment) affect F><, in most cases without necessarily affecting F , (b) the operator has a direct influence on F through movement of rods, and can .limit q
it to the desired value, he has no direct    control over P~ and (c) an error in the predictions for radial power shape, which may be detected during startup physics tests can be compensated for in F by tighter 'axial, control, g
but compensation for r~ is less readily available. %hen a measurement of P> ks taken, experimental error must be allowed for and 4X is the appro-priate allowance for a full core map taken with tne movable incore detector, flux mapping   system.
Measurements   of the hot channel factors are required as part o start-up physics tests, at least. once each full rated powermnth of operation, and whenever abnormal power dist'ribution conditions require a reduction of core power to a level based on measured hot channel factors. The '"core map taken following initial loading provides confirmation of'he basic nuclear
*For steam generator tube plugging in excess of 10%, this value becomes 2.20.
B3.2-4              .6/8/77

Flux Difference (hg) and a reference value which c-=esponds to the fu13.
design power equilibrium value of Axial Offset (.-'a:=.= 0 set = 'r/fractional
, power). The reference value of flux difference var'es w th pow r level and burnup but expressed as axial offset     it varies only ." th burnup.
The   technical specifications on power distr.bution ccntzol assure that the F upper bound envelope of 2.22 times Figure 3.2-3 is not exceeded and xenon distributions are not develooed which at a later tine, would cause greater local power peaking even though the flux differen'ce is tnen within the l&.ts specified by the procedure.
The  target (or reference) value of flux difference is determined as fo13.ows At any time that equilibrium xenon conditions have been established                    tne i=
dicated flux dizference is noted .wit.x part length rods withdrawn from tne co~~
and with tne full lengtn rod control rod bank, more than 190 steps withdrawn'i.e.,
normal rated power operating posi.tion appropriate for the time in 1" fa 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 tne design power value of the tar et flux difference       Va3.ues for all other cora power levels are obtained by multiplying tne design power value by the fractional power. Since the indicated equilibrium valu was noted, no allowances for excore detector error ar necessary and indicated deviation of
  +5K DI are permitted from the indicated reference value.       During periods where extensive load fo3.lowing is required, it may be impractical to'stab~
the required core conditions for measuring the t~~ t flux difference every rated power month. For this reason, methods aze pe~tted by Item 6c of Section 3.2 for updating the target flux differences. Fibre B3.2-1 shows a typi.cal construction of the target flux difference band at. BOL and Figure B3 2-2           ~
shows the typical variation of the full. power value wi.th buznup.
Strict control of the flux difference (and rod position) is -ot as necessary during part pow r operation. This is because xenon. distribution control at part power is not as significant as the control at full power'nd allowance has been made in predicting t'se heat flux peaking factors for less strict co"..
trol at part pc=':. Strict control of the flux difference is not possible during certai= / .'sics tests'or during the required, periodic excore calibra'-
* Fpz stear. generator tube plugging           in excess of    10%,  this value becomes    2."0.
az.2-6                   6/8/77

SAFETY EVALUATION I. Introduction This safety evaluation and the attached Westinghouse ECCS re-evaluation support the following proposed change to the Technical Specifications:
(1)    The maximum allowable nuclear peaking factor (Pq) is decreased from 2.22 to 2.20, for steam generator tube plugging in excess of  10%.
II. Discussion A   re-evaluation of ECCS cooling performance calculated in accordance      with an approved Westinghouse Evaluation Model has been performed.        The re-evaluation shows that for breaks up to and including the double ended severence of a reactor coolant pipe, the ECCS will meet the Acceptance Criteria presented in 10 CFR 50.46. The detailed re-evaluation is attached, and shows that, at a core power level of 102%
of 2200 Mwt and a minimum accumulator water volume of 875 ft3 per accumulator, the maximum allowable nuclear peaking factor is 2. 20 for steam generator tube plugging in excess of 10%.
The attached Westinghouse ECCS re-evaluation assumed:
: 1. 15%   steam generator tube plugging
: 2. Fq = 2.20
: 3.          f 875 t3 accumulator minimum      water volume 4 ~   2200 Mwt core power level III. Conclusions Based on these      considerations, (1) the proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as defined in the basis for any technical specification; therefore, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in com-pliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

LARGE BREAK TIME SE UENCE OF E'/ENTS DECL (CD=0.4)
(Sec)
START                                              0.0 Rx Trip Signal                                     0.595 S. I. Signal                                     0.
67'6.
Acc. Injection                                      0 End of Bypass                                     27.16 End of Blowdown                                   27.31 Bottom of Core Recovery.                          46. 24 Acc. Empty                                        60. 8 Pump   Injection                                  25.67

TABLE LARGE BREAK DECL (CD=0.4)
Results Peak Clad Temp.     'F                      2173 Peak Clad  Location Ft.                      6.5" Local Zr/H20 Reaction (max)%                11.655 Local Zr/H20 Location Ft.                    6.0 Total Zr/H20 Reaction %                     <0. 3 Hot Rod Burst Time sec"                     22.6 Hot Rod Burst Location Ft,                   6.0 Cal cul ati on Core Power Mwt 102%     of                         2200 Peak Linear Power      kw/ft 102%'of               12.499
'eaking Factor                                        2.20 Accumulator Water Volume       (ft )                875 (per accumulator)
Fuel region + cycle analyzed           Cycle  Region UNITS 3 5 4                            3      3

TABLE       3 LARGE BREAK CONTAINMENT OATA    ORY CONTAINMENT NET FREE VOLUME                                            1.55x10   Ft INITIAL CONOITIONS Pressure                                                   14.7 psia Temperature                                                 .90  F RNST Temperature                                             39 OF Service Mater Temperature                                    63 oF Outside Temperature                                          39 'F SPRAY SYSTEM Number   of Pumps Operating                                   2 Runout Flow Rate                                           1450 gpm Actuation Time                                               26 secs SAFEGUARDS FAN COOLERS Number   of Fan Coolers  Operating                            3 Fastests   Post Accident  Initiation of   Fan Coolers        26 secs

TABLE 3   (Continued)
LARGE BREAK CONTAINMENT DATA DRY CONTAINMENT STRUCTURAL HEAT SINKS Thickness  In                     Area    Ft Steel       0.03                     31,400 Steel       0; 063                  107,158 Steel       0.1                      56,371 Steel       0.2                      57,185 Steel       0. 24-                     9.931 Steel       0.2898 Concrete   24.0                     136,000 Steel       0.4896                   23,677 Steel       0.6396                     6,537 Steel       0.8904                   , 4,915 Steel       1.256                    27,802 Steel       1.56                       5,307 Steel       2.0                          668 Steel       2. 75                    1268. 7 Steel       5.5                      1277.4 Steel       9.0                        260. 4 Stainless   0.14 Concrete   24.0                      14,392 Stainless   0. 44                         768 Stainless   2. 126.                    3,704.
Stainless   0.007                   102,400 Concrete   24.0                      59,132

I TABLE       4 REFLOOD tNSS AND ENERGY RELEASES FOR   LIMITING BREAK DECLG CD =   0.4 Total  Mass  Flowrate           Total Energy Flowrate Time, Sec                      LBm/Sec                    10  BTU/Sec 46.235                         0.0                            0.0 48.36                          0.0                            0.0 53.982                         35.09                          0.4562 64.197                         93.67                          1.16 76.997                         96.36                          1. 20 92.197                         117.2                          1. 30 108.097                        238.3                          1.61 124.697                        267.3                          1.65 160. 397                       276.7                          1.57 199. 397                       283.3                          1.48

6.0 FT A}lD 6.5 FT g  0.95
: 0. 90 I
0.85 0.80
    ~ ~
0.75 IO-'  8 l00 6    slo'                 6  8 IO  2 'll 6 8 IO'"
T IIIE (SEC)
              ~
Figure 1. Fluid Quality - DECLG {CD = OA)

tip I
30               ~       6.5 IT 2P 6.0 IT lo                                                  6-0 FT AND 6.5 FT ED
)
UJ
   - IO
   >>20 6 8 lp    2            6   8 )Pl    2            6  8  lp    2 6 8 TIVE (SEC) lp'igure
: 2. Mass Velocity - DECLG (CD = 0,4)

i 03 8
6 U
I cv     2 I-
     )02 8
6 6.0 FT 2
CO
      )0)
I-                                  6.5 FT l-2 lo0 0   f00                    200                  300       900 500 TiVE (SEC}
Figure 3. Ideat Transfer Coefficient - DECLG (CD = 0.4)

2500 2000 l500 l000 500 0 IO                    20                 30   'IO 50 TIME (SEC)
Figure 4. Core Pressure - DECLG (CD = 0.4)

I.lxlQ5 exlo" 7xlo" 5xlQ" i5 3xlo" lxlQ"
      -lxlo" 0   IQ                   20 TIME (SEC) 30'IQ 50
                ~
Figure 5. Break Flow Rate - DECLG (CD = OA)

70 50 c5   0
   -50
   -70 0 10                    20                 30     00 50 TlME (SEC)
Figure 6. Core Pressure Drop - DECLG (CD = OA)

2500 6.0 FT 2000                                                                     6.5 FT 6.5 FT 6.0 FT l500 ED cB !000 O
C)
CD 500 0
: 0.      25 50              75           l00         l 25        l50        l75 200 TlhlE (SEC)
Figure 7, Peals Clad Temperature - DECLG (CD = 0.4)

2000 1750 1500 U
1250 oc 1000 750 6.0  FT AND 6.5  FT
    $~
250 0 l00                  200                  300        900 500 T111E  (SEC)
Figure 8. Fluid Temperature   - DECLG (CD = 0,4)

7000 5000 2500 TOP 0
                     \
MI'IOM
-2500
-5000
<<7000 0               l0               l5              20      30 TlME (SEC)
Figure 9. Core Flow - Top and Bottom - OECLG (CD = OA)

20.0 17.5 OONHCOHER LEVEL 15.0
: 12. 5 10.0 7.5 CORE LEVEL 5.0 "2.5 0.0 0     25             50            75         100        125          150         175 200 TlhIE (SEC)
Figure 10. Ref lood Transient - DECLG (CD = OA) Downcomer and Core Water Levels

2.00 l.75 I.50 o 0,75
: 0. 50
: 0. 25 0.00 50                           l00       l25           l 50 T-lltE {SEC)
Figure 10a. Ref lood Transient'- DECLG (CD = OA) Core inlet Velocity

6000 5000 CD UJ 4000 3000.
Ch 2000 CD l000
     ~ t 0
0      lo.o                20. 0              30.0         '00. 0 50.0 TlME (SEe)
Figure 11. Accumulator Flow (Blowdown) - DECLG (CD = OA)

8.0 o 6.0 Q.O 2.0 0             80        ) 20         l60        200        290'80 320 T)ME    (sec)
Figure 12. Pumped ECCS Flow (Ref lood) - DECLG (CD = OA)

30 25 CV 20 ul c     l5 I-IO cf I-
~
CD 0
0 lIO        80       I20      IGO        200 '<)0        280 320 360
                                             . TINE (SEC)
Figure 13. Containment Pressure  - DECLG (CD = 0.4)

l.p 0.8 p
K p g 0.2 0 lp.p                20.0                 30.0        50.0 TIME (SEC)
Figure 14. Core Power Transient - DECLG (CD = 0.4)

3.5 x l07 2.5 x l07 l.5 x 107 0,5 x I06
-0.5 x I06 0 I0.0                20. 0                 30.0    50.0 TIME (SEC)
Figure 15. Break Energy Released to Containment

I I 00 l000 900 800
   /
700 600 500
 '400 300 200 IOO 0
0                  IOO                  200                   300 TIME (SEC)
Figure 16. Containment Wall Condensing Heat Transfer Coefficient

STATE OF FLORIDA     )
                     )     ss COUNTY OF DADE       )
Robert E. Uhrig, being  first       duly sworn, deposes and says:
That he is a Vice President of Florida Power                       & Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document. are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert        ED  Uhrig Subscribed and sworn to before         me     this day of  p/,~'M                                19    77
       ~Spudin~and NOTARY PUBLIC, 6/,/
fbr th)        County       of     Dade, State of Florida               'C l'0"UC 5$ ATg Of FLOftr A st MFC~
8"Th Ny commission    expires'aUY   CEAAtdSlW tg1CS        HAY 5, NS1

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