L-78-264, 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-41

08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-41

ML18227D801
Person / Time
Site:	Turkey Point
Issue date:	08/09/1978
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-78-264
Download: ML18227D801 (36)

Text

Q oS'P +S R-GULATORY INFORMATION DISTRIBUTION SYST M (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-250'251 SEC: STELLQ V QRG. Ul-lRIG R E DQCDATE 08/Q9/78 NRC FL PWR 5 LIGHT DATE RCVD: 08/14/7c DOCTYP-: LETTER NOTARIZED: YE COPIES RECEIVED SUBJECT LTR - ENCL 40 FORWARDING LIC NOS DPR-3i 8: 41 APPL FOR AMEND: TECH SPEC PROPOSED CHANGE CONCERNING REVISION TO Tf<E ECCS COOLING PERFORMANCE AS LISTED AND REQUESTING

, ROVISIONS OF NRC"S 06/07/78 ORDER BE DELETED... NOTARIZED 08/09/78.

,"LANT NAME: TURKEY PT N3 REVIEWER INITIAL: X JM TURKEY PT 04 DISTRIBUTER INITIAL: ~

DISTRIBUTION O- THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FQR AFTFR ISSUANCEOF OPERATING LICFNSE.

(DISTRIBUTION CODE AOOi)

FOR ACTION: BR Cl.II EF ORB01 BC+4 W/7 ENCL INTERNAL: REG FI'LE4f+W/ENCL NRC PDP++W/ENCL I-8. E++W/2 ENCL OELD++LTR ONLY HANAUER<;ccW/ENCL CORE PERI=QRMANCE BR++W/ENCL AD FQR SYS 8. PROJ++W/ENCL ENG I NEER ING BR++W/ENCL REACTOR SAFETY BR++W/ENCL PLANT SYSTEMS BR++W/ENCL EEB++W/ENCL EFFLUENT TREAT SYS+~W/ENCL J. MCGOUGH~f+W/ENCL EXTERNAL: LPDR'S MIAMI i FL++W/ENCL TERA~f4W/ENCL NSIC~~W/ENCL ACRS CAT B++W/ib ENCL

.ISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 782190052 SIZE: 3P+29P t 8f M %%%8f%%%%%%4+wf+%%%%%4%%%4%%%4%4. Tf)E END %% M 4%c% 3f%%%%44 %%%%%%4 %%%4%4%%%%%%

FLORIOA POWER 8t LIGHT COMPANY August 9, 1978 L-78-264 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Mashington, 0. C. 20555

Dear Mr. Stello:

Re ~

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 An Order for Modification of License, dated June 7, 1978, was issued by the Commission for Turkey Point Units 3 and 4. The Order amended Facility Operating Licenses DPR-31 and DPR-41 by adding the following provisions:

(1) As soon as possible, the licensee shall submit a re-evaluation of ECCS cooling performance calculated in accordance with the Mestinghouse Evaluation Model, approved by the NRC staff and corrected for the errors described herein.

(2) Until further authorization by the Commission, the Technical Specification limit for total nuclear peaking factor (Fq) for the facility shall be limited to 2.03 and 1.91 for Unit Nos.

3 and 4, respectively.

(3) Until further authorization by the Commission, the licensee shall conduct the operating surveillance program described in.

tionss, its letter of April 10, 1978.

Mestinghouse has reevaluated ECCS cooling performance in accordance with a corrected evaluation model that we understand has been approved by the NRC staff. The reevaluation supports a Technical Specification limit for total nuclear peaking factor (F<) of 2.03 for both Units 3 and 4, assuming 255 steam generator tube plugging. Based on Mestinghouse core physics calcula-the maximum values of Fq that could occur for the remainder of Unit 3, Cycle 5 and for the upcoming Unit 4, Cycle 5 are 2.02 and 2.00, respectl'vely Because the maximum predicted Fq values are less than the maximum allowable value derived from the corrected ECCS evaluation, the augmented surveillance procedures discussed in Florida Power 8 Light Company (FPL) letter L-78-127 of April 10, 1978 will not be necessary during Cycle 5 of both Units 3 and 4.

PEOPLE... SERVING PEOPLE

Director of Nuclear Reactor Regulation Page Two As a result of the ECCS reevaluation performed in compliance with the Commission's Order of June 7, FPL submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses OPR-31 and DPR-41. l<e also request that the provisions of the June 7 Order be deleted. The proposed amendments to Appendix A are described below and shown on the a'ccompanying Technical Specifications bearing the date of this letter in the lower right hand corner.

Pa e 3.2-3 Specification 3.2.6.a (Power Distribution Limits) is revised to reflect the results of the correct d Westinghouse ECCS evaluation.

Fi ures 3.2-3 and 3.2-3a The current figures are deleted and replaced with a single Figure 3.2-3 (Hot Channel Factor Normalized Operating Envelope) that is valid for an Fq of 2.03 and steam generator tube plugging <251..

Pa es 83.2-4 and 83.2-6 Bases Section B3.2 (Control and Power Distribution Limits) is revised to delete superseded Fq values.

The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Conmittee and the Florida Power 8 Light Company Nuclear Review Board.

They have concluded that it does not involve an unreviewed safety question.

Yery ly yours, obert E. Uhrig Yice President REU/HAS/cpc

'ttachment cc: Yu . James P. O'Reilly, Region II Robert Lowenstein, Esquire

reactivity insertion upon ejection greater than 0.3/= Q k/k at rated po~er.

Inoperable rod worth shall be determined within 4 weeks.

b. A control rod shall be considered inoperable (a) the rod cannot be moved by the CRDH, or if (b) the rod is misaligned from its bank by more than 15 inches, or (c) the rod drop time is not met.

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

'5. CONTROJ ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation mon-itor 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 alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93/ of rated power.

6. POWER DISTRIBUTION LZMITS

a. Hot channel factors:

With steam generator tube plugging < 25%, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests:

F (Z) < (2.03/P) x K(Z), for P > .5 q

F (Z) < (4.06) x K(Z), for P < .5 F~N < 1.55 (1.+ 0.2 (1-P) }

Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3; Z is the core height location of F If predicted Fq exceeds 2.03, the power will be limited to the rated power multiplied by the ratio of 2.03 divided by the predicted Fc, or augmented surveillance of hot channel factors 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 thereafter, power distribution maps, using the movable detector system shall be made, to confirm that the hot channel factor limits of the speci-fication are satisfied. For the purpose of this comparison, 302 3

HOT CHANNEL FACTOR-NORMALIZED OPERATING ENVELOPE (FOR STEAM GENERATOR TUBE PLUGG ING + 25% GQd Fq 2 0 3)

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

When an F q

measurement is taken, both experimental. 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 limit of F~, there is an 8 percent allowance for uncertain-ties which means that normal operation of the core is expected to result in F~<1.55/1.08. The logic behind'he larger uncertainty in this case is that (a) normal perturbations in the radial power shape (e.g., rod misalign-

'ent) affect P> , in most cases without necessarily. affecting F , (b) although the operator has a direct influence on F through movement of rods, and can limit it q to the desired value, he has no direct control over F~ N 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, q

but compensation for FN is less readily available. When a measurement of P is taken, e~erimental error must be allowed for and 4X is the appro-priate allowance for a full core map taken with the movable incore detec'tor flux mapping system.

Measurements of the hot channel 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 power to a level based on measured hot channel factors. The incore map taken following initial loading provides confirmation of the basic nuclear B3.2-4

Flux Difference (Ag) and a reference value which. corresponds to the full design power equilibrium value of Axial Offset (Axial Offset ~ A4/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 upper bound envelope as defined by Figure 3.2-3 is not exceeded and xenon q

distributions are not developed which at a later time, would causa greater local power peaking even though the"flux difference is then within the limits specified by the procedure.

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

At any time that equilibrium xenon conditions have been established, 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 than 190 steps withdrawn (i.e., normal rated power operating position appropriate for the time 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 target flux difference. Values for all other core power 1'evels are obtained by multiplying tne design power value by the fractional power. Since the indicated equilibrium value was noted, no allowances for excore detector error are necessary and indicated deviation of

+5% dI are permitted from the indicated reference value. During periods where extensive load following is required, it may be impractical to establish the required core conditions for measuring the target flux difference every rated power month. For this reason, methods are permitted by Xtem 6c of Section 3.2 for updating the target flux differences. Figure B3.2-1 shows a typica1 construction of the target flux difference band at BOL and Figure B3.2-2 shows the typical variation of the full power value with burnup.

Strict co'ntrol 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 tne heat flux peaking factors for less strict con-trol at part power. Strict control of the flux difference is not possible during certain physics tests or during the required, periodic excore calibra-B3.2-6

TABLE 1 LARGE BREAK TIME SEQUENCE OF EVENTS DECL (Sec)

START 0.0 Rx Trip Signal 0.535 S. I. Signal 0. 77.

Acc. Injection 16.1 End of Bypass 27.60 End of Blowdown 27.79 Bottom of Core Recovery 46.03 Acc. Empty 60.14 Pump Injection 25. 77

TABLE 2 LARGE BREAK DECL Results Peak Clad Temp. 'F 2173 Peak Clad Location Ft. 6.25 Local Zr/H20 Rxn(max)% 7.678 Local Zr/H20 Location Ft. 6.25 Total Zr/H20 Rxn <0.3 Hot Rod Burst Time sec 32.0 Hot Rod Burst Location Ft ~ 6. 25 Calculation Core Power Met 102% of 2200 Peak Linear Power kw/ft 102% of 11.53 Peaking Factor 2. 03 Accumulator Water Volume (ft3 ) 875 (per accumulator)

Cycle Analyzed Cycle Unit 3 and Unit 4 5

Page 1 of 3 TABLE 3 LARGE BREAK CONTAINMENT DATA (DRY CONTAINMENT) 6 NET FREE VOLUME 1.55 x 10 Ft INITIAL CONDITIONS Pressure 14.7 psia Temperature 90 'F RWST Temperature 39 'F Service Water Temperature 63 'F 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

Page 2 of 3 TABLE 3 (CONTINUED)

CONTAINMENT DATA (DRY CONTAINNENT)

STRUCTURAL HEAT SINKS THICKNESS AREA (INCH)

(FT )

Paint 0.006996 Carbon Steel 0.20 51824. 69 Carbon Steel 0.006996 996054.9 Paint 0.006996 Carbon Steel 0.4896 35660.11 Carbon Steel 0.4896 11886.7 Paint 0.006996 Carbon Steel 0.2898 Concrete 24.0 102000.0 Carbon Steel 0.2898 Concrete 24.0 34000.0 Paint 0.006996 Carbon Steel 1.56 4622.69 Carbon Steel 1.56 1540.89 Paint 0.006996 Carbon Steel 5.496 1277.87 Carbon Steel 5.496 425.93 Paint 0.006996 Carbon Steel 2.748 951.525 Carbon Steel 2.748 317.175 Paint 0.006996 Carbon Steel 0.03 23550.0 Paint 0.006996 Carbon Steel 0.063 80368.5 Paint 0.006996 Carbon Steel 0.10 42278.25 Paint 0.006996 Carbon Steel 0.006996 76800.0 Stainless Steel 0.4404 768.0

Page 3 of 3 TABLE 3 (CONTINUED)

CONTAINMENT DATA (DRY CONTAINMENT)

STRUCTURAL HEAT SINKS THI CKNESS AREA

( INCH) (FT )

Stainless Steel 2.1264 3704.0 Stainless Steel 0.1398 Concrete 24.0 14392. 0 Concrete 24 ' 59132.0

TABLE 4 REFLOOD MASS AND ENERGY RELEASES - DECLG (CD=0.4)

TINE MASS FLOWRATE ENERGY FLOWRATE (LBm/SEC)

(10 BTU/SEC) 46.028 0.0 0.0 47.653 0.2476 0.0032 53.696 34.83 0.4511 63.653 89.23 1.108 76.653 92.04 1.142 91.953 187.08 1.416 108.153 261.56 1.579 125.253 273.11 1.562 162.253 280.75 1.482 202.853 287.45 1.392

TABLE 5 BROKEN LOOP ACCUMULATOR FLOW TO CONTAINMENT FOR LIMITING CASE DECLG (CD=0.5) 25/

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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 Applicant herein:

That he has executed the foregoing document; that the statements 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 Applicant.

Robert E. Uhrig Subscribed and sworn to before me this day of l9 7&-

NOTARY PUBLI , z.n and for the County of Dade, State of Florida NOTA'USUC STATE OF FLOAIOA at LARGE hlY CQhlf CGGION 'r'G~IRES h~ARCII 27, ISQ My commission expires: BGNGEQ il".v hIAYeeo eoNGI'IG AGENcY