ML17355A358
| ML17355A358 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/28/1999 |
| From: | Hovey R FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-99-138, NUDOCS 9907070232 | |
| Download: ML17355A358 (16) | |
Text
0 CATEGORY 1 e REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)1 ACCESSION NBR:9907070232 DOC.DATE: 99/06/28 NOTARIZED:
NO DOCKET FACZL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION HOVEY,R.J.
Florida Power 8 Light Co.RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
"Turkey Point Unit 4 Cycle 1'8 Startup Rept." With 990628 ltr..DISTRIBUTION CODE: IE26D COPIES RECEIVED:LTR ENCL.SIZE: TITLE: Startup Report/Refueling Report (per Tech Specsi NOTES: RECIPIENT ID CODE/NAME LPD2-2.PD INTERNA: FILE CENTER I 01 EXTERNAL: NOAC COPIES'TTR ENCL 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME JABBOUR,K NRR/DSSA/SRXB'RC PDR COPIES LTTR ENCL 1 1 1 1 1 1 0 D 0 U N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP'US TO REDUCE WASTE.;O HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF'OP=-S RE EIVE B.YOU OR YOUR ORGANIZATION, CONTAC;THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 4I5-"-083 TOTAL NUMBER OF'OPIES'EQUIRED:
LTTR 7 ENCL 7 II,.0 JUN 28 t999 L-99-138 10 CFR 50.36 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: Turkey Point Unit 4 Docket No.50-251 Turke Point Unit 4 C cle 18 Startu Re ort Technical Specification (TS)6.9.1.1, Startup Report, states that a summary report of plant startup and power escalation testing shall be submitted following installation of fuel that has a different design.Turkey Point Unit 4 Cycle 18 started up with ZIRLO clad material in the new fuel assemblies.
This is the first cycle for Unit 4 with a fuel assembly design with ZIRLO material and in accordance with TS 6.9.1.1 the attached startup report is provided.Should there be any questions, please contact us.Ve yours,/'Arrt~R.J.Hovey Vice'President Turkey Point Plant Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9907070232 990628 PDR ADOCK 05000251 P PDR an FPL Group company C
Attachment to L-99-138 Page 1 of 6 TURKEY POINT UiNIT 4 CYCLE IS STARTUP REPORT
1.0 DESCRIPTION
AND PURPOSE On April 19, 1999, Turkey Point Unit 4 completed the Cycle 18 refueling outage and the unit was placed on-line.Cycle 18 was the first cycle that Unit 4 operated with Zirlo clad material in the.new fuel assemblies.
Turkey Point Unit 3 has operated with Zirlo clad fuel, assemblies since the beginning of Cycle 17 (October 28, 1998).Zirlo material replaced the standardlZircaloy-4,material.
Fifty-six fresh, assemblies used Zirlo material in.the fuel rod cladding, guide tubes, instrument tubes and mid-span spacer grids.Technical Specification (TS)6.9.1.1, Startup Report, states that a summary report of plant startup and power escalation testing shall be submitted following:
...(3)'installation of fuel that has a different design or has been manufactured by a different fuel supplier.TS 6.9.1.1 states that the report shall'ddress each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions of characteristics obtained'during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall be described.
Any additional specific details required in license conditions based on other commitments shall be'included in this report.Subsequent Startup Reports shall address startup tests that are necessary to demonstrate the:acceptability of changes'and/or modifications.
This startup report is generated on the basis that the use of Zirlo represents a different, fuel assembly design.2.0 ANALYSIS/EVALUATION Core Desi n and C cle Burnu The core design of Cycle 18 is made up of 157 Debris Resistant Fuel Assemblies that contain a nominal 6 inch axial blanket of natural uranium dioxide pellets at both, the top and the bottom of the fuel stack.The fuel assemblies are arranged'in a low leakage pattern.The core design is accomplished by replacing 37'of Region 17 thrice burned and 20 of the Region 18 twice burned fuel assemblies with 56 fresh Region 20 fuel assemblies and one reinserted:Region 16 twice burned assembly.Region 20 consists of 12 assemblies at 4.0 w/o U-235 and 44.assemblies at 4.4 w/o U-235.The remainder of the 157 assemblies is made up of 44 twice burned Region 18 fuel assemblies and 56 once burned Region 19 fuel assemblies carried over from Cycle 17.Startu Test Pro ram Turkey Point's Startup Test Program includes initial dilution to criticality, Low Power Physics Testing (LPPT),.Power Ascension Testing and Reactor Coolant System (RCS)Flow Verification.
LPPT is 4l Ck Attachment to L-99-138 Page2of6 performed in accordance with ANSVANS-19.6.1 1985, Reload Startup Physics Tests.for Pressurized Water Reactors.Power Ascension Testing addresses the various flux maps and RCS temperature measurements performed at intermediate power levels as the unit ascends to 100%power.The RCS Flow Verification is performed per Technical'Specification 3/4.2.5, after each fuel loading and at least once per 18 months.Each phase of the Startup Test Program is discussed in more detail in the following paragraphs.
Initial Dilution to Criticality Following the refueling outage, Turkey Point performs a dilution to criticality by withdrawing the shutdown banks followed by the control banks in overlap, and performing 1/M calculations at selected intervals.
Control Bank D is withdrawn to a pre-determined core height position and then the reactor is slowly diluted to criticality.
For the Unit 4'Cycle 18 startup the desired critical rod height was D-Bank at 190 steps withdrawn.
The design critical boron concentration at the desired rod position on D-Bank.was 1802 ppm.The reactor was declared critical and data was taken at an equilibrium value of approximately SE-08 Amps as indicated by the power range excore detectors, indicated at D-Bank position of 192 steps and a critical boron concentration of 1804 ppm.Low Power Phvslcs Testln Following dilution to criticality, LPPT.was commenced.
The purpose of this, test is to ensure that the physics characteristics of the new core are consistent with the core operating limits and the operating characteristics of the core are consistent.
with the design predictions.
LLPT is performed in accordance with ANSVANS-19.6.1 1985, Reload Startup Physics Tests for Pressurized Water Reactors.The.following tests were performed during the LLPT:~All Rods Out (ARO)Boron Endpoint,~Positive Period Check,~Differential Boron Worth,~ARO Hot Zero Power Isothermal Temperature Coefficient and Moderator Temperature Coefficient,~Reference Bank-In Rod Worth (by dilution)and~Non-Reference Bank Rod Worth (by Rod Swap).The results of each of these tests are provided in Table 1, with a comparison of the predicted value and the measured value.As indicated in Table 1, all of the LPPT performed met their acceptance criteria.
0 Attachment to L-99-138 Page 3 of 6 Power Ascension.
Testln Turkey Points Power Ascension Testing included performing incore flux maps at approximately 30%, 75%and 100%power.During this startup, Turkey Point implemented the Westinghouse Single Point Excore Calibration method which predicted excore detector behavior following the refueling.
In addition, at 75%power and 100%power, an incore-excore calibration was.performed to generate full power total'currents and Axial Flux Difference Calibration data.Once the unit reached 100%power, an RCS flow verification was performed, as well as a Hot Full Power Boron Concentration Test.Figures 1 and 2 display the Beginning of Cycle peaking factors.RCS Flow Verification The RCS flow verification was performed to satisfy the requirements of TS 4.2.5.4.This Technical Specification requires that after each fuel loading and at least once per, 18 months, the RCS flow rate shall be determined by precision heat balance afler exceeding 90%power.TS 3.2,5 requires that the measured RCS flow shall be greater..than or equal to 264,000 gpm.The measured RCS flow was approximately 284,986 gpm.
3.0 CONCLUSION
As demonstrated in this report,,the transition from Zircaloy-4 to Zirlo cladding has resulted in no deviation in predicted core design behavior.Unit 4 fuel reliability continues to indicate a defect-free core, and.the core continues to operate consistently with design predictions.
ll I Attachment to L-99-138 Page4of6 Table 1 Turkey Point Unit 4 Cycle 18 Low Power Physics Test Results Ph sics Test Acce tance Criteria Measured Value M Predicted Value P Difference*
All Rods Out (ARO)Boron Concentration HZP Isothermal Temperature Coefficient
+/-50 ppm+I-2 pcmi'F 1813 ppm-.0.643 pcm/'F 1812 ppm-1.198 pcml'F-1 ppm-0.555 pcml'F HZP Moderator Temperature Coefficient
<5 pcml'F 1.027 pcm/'F 0.472 pcmi'F-0.555 pcm/'F Positive Period Check Reference Bank In Boron End oint+I-4%+I-50 ppm 83.17 cm 1619 ppm 83.28 cm 1622 ppm 0 13%3 ppm Individual Bank Worth CBD CBA CBB SBB SBA Reference Bank Worth+/-15%or+I-100 pcm, whichever is greater 714.7 1195.2 233.8 1174.6 999.3 743 1211 261 1202 1055 4.0%I 28.3 pcm 1.3%/15.8 pcm 11.6%I 27.2 pcm 2.3%/27.4 pcm 5.6%I 55.7 pcm CBC Total Bank Worth+/-10%+I-10%1355.4 5673 1400 5872 33%3.5%HZP Differential Boron Worth+I-15%6.85 cml m 7.37 cml m 7.6%*Difference
=(Predicted
-Measured)Percent Difference
=((Predicted/Measured)
-1)x 100 41 i(j E 2.40 Attachment to L-99-138 Page 5 of 6 FIGURE I UMT 4-CYCLE 18 Peak Fq ys Exposure 2.30--..-.Design Fq+5%~Measured Fq (Including Uncertainties)
Design Fq (Including Uncertainties)
Design Fq-5%2.20 2.10 4 2.00 Q.1.90 1.80 1.70 1.60 2000 4000 6000 8000 10000 12000 14000 Cycle Exposure (EFPH) 0 l(j Attachment to L-99-138 Page6of6 Fi ure2 UNIT 4-CYCLE 18 Normalized Peak FdH vs Exposure 1.80.1.75 1.70-Technical Specifications Limit------Design FdH+4%Measured FdH (Including Uncertainties)
-.Design FdH (Including Uncertainties)
Design FdH-4%1.65 1.60.1.55.1.50~1.45.1.40.~1.35 1.30 0 2000 4000 6000 8000 Cycle Exposure (EFPH)10000 12000 14000 il