ML17338A909
| ML17338A909 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/15/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17338A912 | List: |
| References | |
| NUDOCS 7907250543 | |
| Download: ML17338A909 (35) | |
Text
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Docket Nos.
50-250 and '50-251 UNlTEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 15, 1979 Dr. Robert E. Uhrig, Vice President Advanced Systems and Technology Fl orida Power and Light Company Post Office Box 529100 Miami, Florida 33152 DeIrr Dr. Uhrig:
In response to your applications dated May 18, 1979 (L-79-122 and L-79-124) as supplemented on May 29 and June 8, 1979, the Commission has issued the enclosed Amendment Nos.
49 and 41 to Facility Operating License Nos.
DPR-31 and DPR-41 for the Turkey Point NucIear Generating Plant,
)nit Nos.
3 and 4.
The amendments consist of changes in the Technical Specifications that approve the operation of Turkey Point Unit Nos.
3 and 4 with a peaking factor of 2. 10, assuming that no more than 22K of the steam generator tubes are plugged.
In addition, Amendment No.
41 to License No.
DPR-41 permits continued operation of Turkey Poipt Unit 4 for six equivalent months of operation from June 1,
1979.
The application (L-'79-122) requested ten equivalent months of operation,
- however, we preferred not to predict the steam generator performance for longer.than six months at a time.
We have dijcussed this with your staff and they have accepted this judgment.
Also, for our administrative convenience, we are reissuing pew pages 3 through 6 for Facility License No.
Paragraph 3.D.1 is amended to include the new operating period and is expanded to be consistent with the requirements for Unit 3.
During our rgview of your proposed amendments we found that certain modifications were necessary to meet our requirements.
Your staff has agreed to these modifications and they hqve been incorporated in these amendments.
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Dr. Robert g, Uhrig Florida Power and Light Company June 15, 1979 Copies of the relapsed Safety Evaluation and the Notice of Issuance are alamo enclosed.
Sincerely,
Enclosures:
l.
Amendment No. 49 to DPR-,)1 2.
Amendment No.
41 to DPR-41 3.
Safety Evaluation 4,
Notice of Issuance cc:
w/enc)osurqs See newt pygmy
/
A. Schwencer, Chief Operating Reactors Branch gl Division of Operating Reactors
(
)F IU I
l
Dr. Robert E, Uhrig Florida Power and Light Company June 15, 1979 cc:
Honorable Dewey Knight County Manager of Metropolitan Dade County Miami, Florida 33130 Bureau of Intergovernmental Relations 660 Apalachee Parkway Tallahassee, Florida 32304 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Dr. David B. Hall 400 Circle Drive Santa Fe, New Mexico 87501 Mic)ael A. Bauser, Esquire Lowenstein, Newman, Reis, Axelrad and Toll 1025 Connecticut
- Avenue, N.W.
Washington, D.
C.
20036 Mr. Mark P.
Oncavage 12200 S.W.
110th Avenue 5iami, Florida 33176 Normal A. Coll, Esquire
- Steel, Hector and Davis 1400 S.E. First National Bank Building Miami, Florida 33131 Dr. Oscar H. Paris Atomic Safety hand Licensing Board S. Nuclear Regulatory Commission Washington, D.
C.
20555 Counsel for NRC Staff Office o the Executive Legal Director U.
S, Nuclear Regulatory Commission Washington, D.
C.
20555
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UNITEO STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No.
DPR-31 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The applications for amendment by Florida Power and Light Company (the licensee) dated May 18, 1979 (L-79-122 and L-79-124) as supplemented May 29 and June 8,
- 1979, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by tIlis amendment can be conducted without endangering the health pnd safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Par t 51 of the Commission's regulations and all applicable requirements have been satisfied.
1
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of the Facility Operating License No.
DPR-31 is hereby amended to read as follows:
{B)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, are hereby incorporated in the license.
The licensee shall oper ate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 15, 1979 A. 5chwencer, Chief Operating Reactors Branch 81 Division of Operating Reactors
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING STATION UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4l License No.
DPR-41 1.
The Nuc1ear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Florida Power and Light Company (the licensee) dated May 18, 1979 (L-79-122 and L-79-124) as supp1emented May 29 and June 8,
- 1979, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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.D.l of the Facility Operating License No.
DPR-41 are hereby amended to read as follows:
3.B Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 41, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.D Steam Generator 0 eration l.
After equivalent operation in Cycle 6 of six months from June 1, 1979, Turkey Point Unit 4 shall be brought to the cold shutdown condition and the steam generators shall be inspected unless:
(1) an inspection of the steam generators is performed within this six month period as a result of the requirements in 2, 3 and 4 below, or (2) an acceptable analysis of the susceptibility for stress corrosion cracking of tubing is submitted to explicitly justify continued operation of Unit No.
4 beyond the authorized six equivalent months of operation.
Any analysis justifying continued operation must be submitted at least 45 days prior to the expiration date of the authorized six equivalent months of operation.
For the purpose of this requirement, equivalent operation is defined as operation with-the reactor coolant at a temperature greater than 350'F.
Nucleay Regulatory Commission (NRC
) approval shall be obtained before resuming power operation following this inspection.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 15, 1979 A. Schwencer, Chief Operating Reactors Branch 81 Division of Operating Reactors
'TTACHMENT TO LICENSE AMENDMENT NOS.
49 AND 41 FACILITY OPERATING LICENSE NOS.
50-250 AND 50-251 Replace the following pages of the Technical Specifications contained in Appendix A of the above indicated license with the attached pages bearing the same
- numbers, except as otherwise indicated.
The changed areas on the revised pages are reflected by a marginal line.
Remove 3'"3 3.2-4 Fig. 3.2-3 Fig. 3.2-3a 8 3.2.4 8 3.2-6 Insert 3.2-3
- 3. 2-4 Fig. 3.2-3 Fig. 3.2-3a*
Fig. 3.2-3b*
B 3.2-4 8 3.2-6 Replace the following pages of Facility License No. DPR-41 with the attached pages as indicated.
The changed area in the license is indicated by a
marginal line.
Remove I
3
~
5 Insert
- C anges
>n figure number only.
4 t
reactivity insertion upon ejection greater than 0.3%
k/k at rated power.
Inoperable rod worth shall be determined within 4 weeks.
b.
A control rod shall be considered inoperable if (a) the rod cannot be moved by the CRDM, or (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 withdrawn worth of the inoperable rod.
5.
CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or 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 alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93% of rated power.
6.
POWER DISTRIBUTION LIMITS a.
Hot channel factors:
(1) With steam generator tube plugging
>22% and
<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 Fq (Z)
< {4.06) x K(Z), for P
<.5 Fg~
< 1.55 [l.+0.2 (1-P)]
Wh P i the fraction of rated power at which the core is operating; K(Z) ere s
e r
f F is th. function given in Figure 3.2-3b; Z is the core height location o
If F redicted by approved physics calculations, exceeds 2.03, the l
as p
power will be limited to the rated power multiplied by the ration of 3
2 0 divid d by the predicted F, or augmented surveillance of hot channel facto s shall be implement8d.
(2) With steam generator tube plugging
< 22%, the hot channel factors (defined in th basis) must meet the following limits at all times except during low power physics tests:
Fq (Z)
< (2 lent'P)x K(Z) > for P 5
Fq (Z)
< (4.20)x K(Z), for P
<.5 FiN(
< 1'55 Ll'+0 2 (1-P)
Wh P is the fraction of rated power at which the core is operating; K(Z) is the function given in either Figure 3.2-3 or 3.2-3a; Z is the co e g
ere is e
r hei ht locat Eon of Fq e
I f" "'f"'3tf (-,.i
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Amendment No 49 Unit 3 Amendment No. 41, Unit 4
If F as predicted by approved physics calculations, exceeds 2.03, the power will be limited to the rated power multiplied by 'he ration of 2.10 i ivided by the predicted F
, or augmented surveill.ince of hot channe L factors shall be implemlnted.
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 specification.are satisfied.
For the purpose of this comparison, (1)
The measurement of total peaking factor, P~q
, shall be increased by three percent to account for manufacfuring tolerances and further increased by five percent to account for measurement error.
(2)
The measurement of the enthalpy rise "hot channel factor, FgH, shall be increased by four percent to account for measurement error.
If either measured hot channel factor exceeds its limit specified under It 6 'he reactor power shall be reduced so as not to exceed a fraction tern a,'
o P
d of the rated value equa1 to the ration of the Fo or P>H limit to measure value, whichever is less, and the high neutron flux trip setpoint shall be reduced by the same ratio. If subsequent in-core mapping cannot, ~ithin a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, demonstrate that the hot channel factors are met, the reactor shall be brought to a hot shutdown condition with return to power authorize only for the purpose of physics testing.
"The reactor may be returned to higher power levels when measurements indicate that hot channel factors are within limits.
c.
The reference equilibrium indicated axial flux difference as a function of power level (called the target flux difference)"shall be measured at least once per e
ec r effective full power quarter.
If the axial flux difference has tar et flux not been measured in the last effective full power month, the target ux difference must be updated monthly by linear interpolation using the most recent measured value and tQe value predicted for the end of the cycle life.
d.
Except during physics tests or during excore calibration procedures and as modified by items 6e through 6g below, the indicated axial flux difference shall be maintained within a + 5% band about, the target flux difference (this defines the target band on axial flux difference).
- e. If the indicated axial flux difference at a power level greater than 90% of rated power deviates
- 3. 2-4 Amendment No 49 Unit 3 Amendment No. 41, Unit 4
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'IGURE 3,2-5 HOT HAI'I,'IEL /ACTOR EHALOk( OR TUBf PLUGGING
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HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (for steam generator tube plugging 22% and Fq ~ 2.10)
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BOTTOM 10 12
'OP CORE HZXGRT (ZT)
ZXCURE 3.2-3b Amendment No. 49, Unit 3 Amendment No. 41, Unit 4
An upper bound envelope as defined by the normalized peaking factor anal dependence of dvigu-es3.2-3, a,g b has been. determined to be consistent with the j technical specifications on power distribution contxol as given in Section 3 2 Shen an P measurement is taken, both experimental, erxox'nd manufacturing tolerance musk be allowed for.
Hve percent is the appropriate experimental nnce-taint@ allo~a fox a fu11 core map taken Mth the movable encore
- detector Xtmc mapping system and three percent is the appropriate allowance for manufacturing kolera'nce
. Xn the-specified 1imit of P>, there is an 8 percent allowance for uncextai-t=Ke L Which means tnat: no~ opexation of the core Zs expected to result in c~1.55/1.08.
Tne 1ogic behind'he larger uncertainty in this case is that Claw (a) normal-perturbations in the xadial power shape (e.g.
rod mis~~gn-ment3 affect P~, in most cases without necessarily. affecting 2' (b) although the operator has a direct influence on 7 through movement of rods~ and can Iimi Xt to the desired value, h has no direct control over P~ and (c) an error M the pxedic&ons for radial power shape, which may be detected during startup physic" tests can be compensated for in 7 by tighter axial control but compensation for P~ is less xeadi~y available.
linen a measurement of is taken, e~e-f~ental error must be aIIowed for and 47 is the appxo-priate allowanc'e for a full core map taken with the movable incore detector flux mapping system.
Heasuxemnts of the hot channel factors are required as part of start-up physics tests, at least, once each full rated power month of operation a>d vhenever 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 83.2-4 Amendment No. 49, Unit 3 Amendment No. 41, Unit 4
FLux Mfferexxce (hy) aud a reference ~alue vhich corresponds to the, full desigxx paver equilib~ value of Ax'.M Offset (AxLal Offset h4(fractional paver).
The reference value of flux difference varies vith pover level and burxxnp. but, expressed as axLal offset it varies anly Mth burnup.
The tecQxnic~ sp~4icatians an paver dkstribukLan control assu a that the p
appex boned envelope as deddaLed by Pdgnxe3a.2->,
a& b ia noc exceeded and xenon p
distxibutians are uat develaped which at a Iater elm, vould cause grcLxLter IacxQ. polar percha@
even thoush the flux differenc M then vithin the limits specked by the procedure.
e The target (or reference) va3Lxxe of flux cKffereuce is dete~ed as foIIovs At any coma that equilibrium xenon conditions have been establish~,
the ixx-chated fIxx-difference is noted vith part length rods vithdravn from the core
+
axxcL vith the fuI1 length rod control rad baal more than 190 steps vithdravn (i e
~ xxozmal rated pave operattuE position approprfate for the ~ in life Control rods are usually vtthdrac~ farther as buzxxup proceeds).
~i" value, divided by the fraction of design paver at vhich the core vas opera~
design pcwer value of tbe target flux differexxce-Vatues for ale. other core paver IeveIs are obtained by multiplyixxE the desigxx paver vatxxe by the fracticma3. paver Since the tudicated equilib~ value vas xxated aIIavaxxces for excel detectar ezmr are necessary and MLLcated devia~~n of
+5X hX are permitted fram the ixxdicated reference value Du~ periods vhere extecLsive load faIIazrtng is required, it may be impractical to cstabli=h the require care canditions for mea.wrixxg the target flux diffemace ev~
rated paver month For this reason, methods are p~tted by Item 6c of Sectian 3 2 for upda~ the target flux differences Hgure B3 2-I, shovs a,
typical construction of the target flux cLLffere ce band at BOL and. Fichu e B3.2-2 shovs the typical vaxLaMan of the fuII paver value vf.th. buxn~.
Strict ca'n~l of the fIux cLLfferexxce (axxd rad pasitLon) is nat as xxecessa~
durixxg part paver operation.
This is because xenon &LLstribution control at part pove is not as ignificant as the control at Eall pave and allova=ce has been made in predicting the heat,.flux peatctug factors for less strict con-trol at part power.
Strict cou~l of tne Klux cKffercnce is not possible a
durhE cerM physics test" ar durixxg the required, periodic encore cal bra-Any reference to part-length rods no longer applies after the part-length
.rods are removed Zrom the reactor.
83.2-6 Amendment No. 49, Unit 3 Amendment No.
41 Unit 4
- B.
'Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis
- Report, as supplemented and amended.
C.
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive,
- possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required.
D.
Pursuant to the Act and 10 CFR Part 30 to receive,
- possess, and use at any time 100 millicuries each of any byproduct material without restriction to chemical or physical form, for sample analysis or instrument calibration; E.
Pursuant to the Act and 10 CFR Parts 40 and 70 4o receive,
- possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical
- form, for sample analysis or instrument calibration; F.
Pursuant to the Act and 10 CFR Parts 30 and 70 to possess, but not
- separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Unit Nos.
3 and,4.
3.
This license shall be deemed to contain and is subject to the'c'onditions specified in the following Commission Regulations in 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50 and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Leve1 The reactor shall not be made critical until the tests described in the applicant's letter of April 3, 1973; have been satisfactorily completed.
Thereafter, the applicant is authorized to operate the facility at reactor core power levels not in excess of 2200, megawatts thermal.
- 8. 'echnica1 S ecifications The Technical Specifications contained in Appendices A and 8 as revised through Amendment No.
4'I are hereby incorporated in the license.
The licensee shall operate the facility in accordance
'with the Technical Specifications.
C.
This license is subject to the following conditions for the protection of the environment:
(1) The applicant shall pursue evaluations of alternatives to the proposed cooling channel system during construction, interim operation, and evaluation of the channel system.
These evaluations shall include at least the following:
(a) Study of availability of groundwater or other'lternative sources of surface water to use in the cooling system.
(b) Study of applicability of mechanical cooling devices, including powered spray modules and cooling towers.
(c) Study of marine environmental impacts of once-through cooling alternatives
{described in Section X of the AEC Final Environmental Statement on Turkey Point Units 3 and 4, July 1972).
(2) The applicant shall take appropriate corrective action on any adverse effects determined as a result of monitoring and study programs.
To the fullest extent practicable, the applicant shall utilize results of study programs in improving and modifying the operation of the facility and its cooling system so as to achieve a minimal adverse environmental impact.
D.
Steam Generator 0 eration (1) After equivalent operation in Cycle 6 of six months from June 1, 1979, Turkey Point Unit 4 shall be brought to the cold shutdown condition and the steam generators shall be inspected unless:
{1) an inspection of the steam generators
is performed within this six month period as a result of the requirements in 2, 3 and 4 below, or (2) an acceptable analysis of the susceptibility for stress corrosion cracking of tubing is submitted to explicitly justify continued operation of Unit No.
4 beyond the authorized six equivalent months of operation.
Any analysis justifying continued operation must be submitted at least 45 days prior to the expiration date of the authorized six equivalent months of operation.
For the purpose of this requirement, equivalent operation is defined as operation with the reactor coolant at a temperature greater than 350'F.
Nuclear Regulatory Commission (NRC) approval shall be obtained before resuming power operation following this inspection.
(2) Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator,.
With a steam generator tube leakage greater than this limit, 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.
(3)
(4)
The concentration of radioiodine in the reactor coolant shall be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.
Reactor operation shall be terminated and NRC approval shall be obtained prior to resuming operation if primary to secondary leakage attributable to the denting phenomena is detected in 2 or more tubes during any 20 day period.
(5) The Metal Impact Monitoring System (MIMS) shall be contained in operation with the capability of detecting losse objects.
If the MIMS is out of service in other than cold shutdown or refueling mode of operation, this fact shall be reported to the NRC.
Any abnormal indications from the NIMS shall also be reported to the NRC by telephone by the next working day and by a written evaluation within two weeks.
(6) Following each startup from below 350'F, core barrel movement shall be evaluated using neutron noise techniques.
E.
The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).
The approved security plan documents, withheld from public disclosure pursuant to 10 CFR 2.790(d),
collectively titled "Turkey Point Plant Unit Nos.
3 and 4
Physical Security Plan.", dated October 18,
- 1978, as supplemented February 20, 1979".
F.
Fire Protection The licensee may proceed with and is required to provide a schedule for and to complete the modifications identified in Paragraphs
- 3. 1.1 through 3.1-19 of the NRC's Fire Protection Safety Evaluation, dated May 21, 1979 for the facility.
These modifications are to be completed prior to December 1980.
If any modifications cannot'e completed on schedule the licensee shall submit a report explaining the circumstances together with a revised schedule.
In addition, the licensee shall submit the additional information identified in Sections 3.1 and 3.2 of the related Safety Evaluation in accordance with the schedule contained therein.
In the event these dates for submittal cannot be met, the licensee shal.l submit a'report, explaining the circumstances, together with a, revised schedule.
The licensee is required to develop and implement the administrative controls which are consistent with the licensee's letters of August. 28 and November 7, 1978 within three months froth the date of this amendment.
4.
This license is effective as of the date of issuance, and shall expire at midnight April 27, 2007.
FOR TKE ATOMIC ENERGY COMMISSION Original Signed By A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
Appendix A - Technical Specifications Appendix B - Environmental Technical Specifications Date of Issuance:
April 10, 1973
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