ML17309A995
| ML17309A995 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/27/1999 |
| From: | West R FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17309A992 | List: |
| References | |
| COP-06.11, NUDOCS 9907300157 | |
| Download: ML17309A995 (60) | |
Text
EPL ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE SAFETY RELATED Procedure No.
COP-06.1)1 Current Revis dn No.
Effey ive Date 67/06/99
Title:
EST BLISHING REMOTE LABORA ORY FOR A ALYSES OF ACCIDENT S PLES Responsible Dep rtment: CHEMISTRY REVISION SUMMA Y:
~~ d4 REVISION 0 Previo lyissued as C-f17. This proce re provides instruction for the W Operational Support Ce ter (OSC) Chemistry Supervi or to establish remote laboratories at the location(s) specified b the Technical Support C nter (TSC) Chemistry Supervisor.
(Russ Cox, 05/27/99)"
PROCEDURE PA~ODuCRM Re sion 0
FRG Review Date 05/27/99 Revision FRG Review Date Approved By R.G. West Plant General Manager Approved By Plant General Manager Approv I Date 05/27 9
Approval Da S
OPS DATE DOCT PRQGEDURE DOC N COP-06.11 sYs COM coMPLETED ITM 0
9907300%57 990726 PDR ADOCK 05000335 F
PDR,I
N r
REVISION NO.:
PROCEDURE No.:
COP-06.11 EDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT TABLEOF CONTENTS PAGE:
2 of 12 SECTION 1.0 PURPOSE PAGE
.3
2.0 REFERENCES
3.0 PREREQUISITES...........~...
~....
4.0 PRECAUTIONS / LIMITATIONS 5.0 RECORDS REQUIRED...~....~...........
6.0 INSTRUCTIONS......~....
4 4
6.1 The OSC Chemistry Supervisor shall establish the operation of
, Remote Laboratories
.5 6.2 Set Up Boron Analysis Stand(s) Date/Time Initials..:...... 7 6.3 Set Up Gamma Pulse Height Analyzer(pha) System.............................8 6.4 Set Up Tritium Analysis System Date/Time Initials..
9 6.5 Set Up Alpha Analysis System Date/Time Initials 10 6.6 Set Up Sample Prescreening Process in Remote Lab...~...
~............
~. ~..11 FIGURES FIGURE 1 12
~
1
REVISION No.:
PROCEDURE NO.:
COP-06.11 EDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
3 of 12 1.0 PURPOSE 1.1 This procedure provides instruction for the Operational Support Center (OSC)
Chemistry Supervisor to establish remote laboratories at the location(s) specified by the Technical Support Center (TSC) Chemistry Supervisor.
1.2 To identify the minimum analyses equipment required for initialAccident Conditions.
2.0 REFERENCES
NOTE One or more of the following symbols may be used in this procedure:
Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, etc.
and shall NOT be revised without Facility Review Group review and Plant General Manager approval.
Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.
'P Indicates a step that requires a sign off on an attachment.
2.1 Plant Procedures EPIP-05, Activation and Operation of the Operational Support Center ADM-17.09, Invoking 10 CFR 50.54 (X)
COP-06.06, Guidelines for Collecting Post Accident Samples COP-07.10, Determination of Boron Manual Titration COP-07-15, Determination of Boron Using the Mettler Titrator COP-65.01, Ortec Multichannel Analyzers COP-01.04, Determination of Gross Beta Gamma and Tritium with LS6500 Liquid Scintillation Counter
~
C-46, Determination of Gross Alpha Radioactivity
REVISION No.:
PROCEDURE NO.:
COP-06.11 EDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
4 of 12 3.0 PREREQUISITES 3.1 Power from 110 volt AC outlets available.
4.0 PRECAUTIONS / LIMITATIONS 4.1 Standard Health Physics precautions shall be observed while handling all Accident samples.
4.2 ADM-17.09, Invoking 10 CFR 50.54(X), addresses the suspension of some Technical Specifications Surveillances when the Reactor Coolant System (RCS) is declared Out of Service.
ADM-17.09 should be reviewed ifthe RCS is declared out of service as a result of accident conditions.
4.3 P-10 Gas is FLAMMABLEand under high pressure in the bottle.
5.0 RECORDS REQUIRED 5.1 As per routine requirements of the applicable procedures regulating the systems and sampling, etc., as per Chemistry LIMsdata base computer, records for Accident Sample Inventory and Tracking as per Results Templates
~
P1 PAS INVforUnit1, and P2 PAS INVforUnit2, orshallbe maintainedin the plant files in accordance with QI-17-PSL-1, Quality Assurance Records.
REVISION No.:
0 PROCEDURE No.:
COP-06.11 EDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
5of12 6.0 INSTRUCTIONS 6.1 The OSC Chemistry Supervisor shall establish the operation of Remote Laboratories as follows:
The OSC Chemistry Supervisor shall contact the TSC Chemistry Supervisor to assess the location of the Remote Lab(s) based on the affected Reactor Unit and safe location to locate the lab(s).
Check the appropriate choices:
Accident affected Reactor is unit 1 OR Unit 2 Boron analysis Remote Lab is:
Unit 1 Hot Lab Unit 2 Hot Lab Unit 1 Cold Lab Other Location:
pha analysis Remote Lab is:
Unit 1 Hot Lab Unit 2 Hot Lab Unit 1 Cold Lab Other Location:
Date/Time Initials 2.
As soon as possible, the OSC Chemistry Supervisor shall assess and/or direct that the following minimum analyses equipment is set up in the designated Remote Lab(s), and ENTER the location of the test stand(s).
One Boron Analysis Stand per Step 6.2 is OPERABLE at location:
One pha multi-channel analyzer per Step 6.3 is OPERABLE at location:
REVISION No.:
PROCEDURE NO.:
COP-06.11 CEDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
6 of 12 6.1 The OSC Chemistry Supervisor shall establish the Date/Time Initials operation of the Remote Laboratories as follows:
(continued) 3.
As accident time and manpower conditions permit, the OSC Chemistry Supervisor shall assess ancVor direct that the following equipment / processes are set up in the designated Remote Lab(s)
~
One Tritium Analysis System per Step 6.4 is OPERABLE at location:
One Alpha Analysis System per Step 6.5 is OPERABLE at location:
A second pha Detector and 92X spectrum master in the Remote Lab per Step 6.3 ifthe Chemistry Counting Room cannot be used as a Remote Lab.
One Sample Prescreening Process per Step 6.6 Implement Accident Sample Inventory and Results Documentation Process for records required per Step 5.1 END OF SECTION 6.1
REVISION NO.:
PROCEDURE No.:
COP-06.11 CEDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
7 of 12 6.2 Set Up Boron Analysis Stand(s)
ENSURE that a copy of COP-07.15, Determination of Boron Using the Mettler Titrator, or as a second choice, a copy of COP-07.10, Determination of Boron Manual Titration, is available for the Remote Lab location.
Date/Time Initials 2.
3.
ENSURE test stand equipment, standard and reagents are available in the Remote Lab per the applicable procedure above.
ENSURE a QC Boron Calibration Check is performed on the instrument test stand prior to use.
END OF SECTION 6.2
REVISION NO.:
PROCEDURE No.:
COP-06.11 CEDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
Sof12 6.3 Set Up Gamma Pulse Height Analyzer(pha) System ENSURE that a pha system is available in the Remote Lab(s) consisting of:
PC Computer "HOBBES", one 92X Spectrum Master, and Detector ¹1 and/or Detector ¹2.
OR PC Computer "CALVIN",one 92X Spectrum Master,
'nd Detector ¹3.
Date/Time Initials 2.
3.
4.
ENSURE that a copy of COP-65.01, Ortec Multichannel Analyzers, is available in the Remote Lab for the pha system(s).
Ifthe pha system(s) were moved from the Unit 1 Chemistry Counting Room or the Power to them was interrupted, Then VERIFYthat the High Voltage Power Supply to the Detector(s) has been restored to the values displayed on the front panel of each Detector's 92X interface box.
ENSURE that a Quality Control Check Source is available and that an ActivityCheck is performed on the Detector(s) that are present, prior to use.
END OF SECTION 6.3
P
REVISION NO.:
PROCEDURE No.:
COP-06.11 CEDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
9of 12 6A Set Up Tritium Analysis System ENSURE that a Beckman LS 6500 Scintillator is available in a Remote Lab.
Date/Time Initials 2.
3.
ENSURE that a copy of COP-01.04, Determination of Gross Beta Gamma and Tritium with LS6500 Liquid Scintillation Counter is available in the Remote Lab.
ENSURE that Quality Control Check Source(s) are available and that an ActivityCheck is performed on the User Program(s) for Tritium and/or 1 ml. Gross prior to use.
END OF SECTION 6.4
17~
REVISION NO.:
PROCEDURE NO.:
COP-06.11 P
OCEDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
10 of 12 6.5 Set Up Alpha Analysis System ENSURE that one Alpha Counter and counting assembly is available in a Remote Lab.
Date/Time Initials 2.
ENSURE that a copy of C-46, Determination of Gross Alpha Radioactivity is available in the Remote Lab.
CAUTION P-10 as is FLAMMABLE.
3.
4.
5.
ENSURE that a P-10 gas bottle is available to supply the instrument at the Remote Lab location.
Ifa P-10 bottle and temporary tubing have to be set up in a Remote Lab (other than the Chemistry Unit 1
,Counting Room), Then the bottle connections and instrument tubing connections should be checked for gas leaks.
ENSURE that a Quality Control Check Source is available and that an ActivityCheck is performed prior to use.
END OF SECTION 6.5
REVISION NO.:
PROCEDURE No.:
COP-06.11 CEDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
11 of 12 6.6 Set Up Sample Prescreening Process in Remote Lab OBTAIN a Health Physics General Area Survey Meter for the Remote Lab.
If available, Then the survey meter should have OPEN and CLOSED window capability.
Date/Time Initials 2.
VERIFYthat the Survey Meter is calibrated per the affixed calibration sticker.
3.
a.
5.
CHECK the Survey Meter's Battery Check is satisfactory.
The Survey Meter should be used to measure contact readings on accident samples prior to counting.
For long-term accident recovery, Figure 1 should be filled out to provide guidance for the maximum sample radiation reading(s) that can be tolerated for counting without sample pretreatment (dilution).
END OF SECTION 6.6
REVISION NO.:
PROCEDURE NO.:
COP-06.11 CEDURE TITLE:
ESTABLISHING REMOTE LABORATORY FOR ANALYSES OF ACCIDENTSAMPLES ST. LUCIE PLANT PAGE:
12 of 12 FIGURE 1 MAXIMUMALLOWABLERADIATIONREADING ON SAMPLE FOR AVOIDING EXCESSIVE ANALYSISDEAD TIME (Page 1 of 1)
For GAMMAAnalysis Without Pre-Dilution Sample TYPE and Container Gasin-30cc lasss here Gas in 1250,cc mari beaker Liquid in 16 ml vial comet Liquid in 4000 ml mari beaker Iodine in TEDA II cartridge Particulate Filter in Whirlpak on Shelf ¹ 0 zero on Detector 1 or 2 Particulate Filter in Whirlpak on Shelf N on Detector 3 Evaporated Liquid in Ianchet Analysis S stem ha on Shelf ¹1 pha on Face pha on Shelf ¹1 pha on Face pha on Shelf N fli counted pha on Shelf ¹0 (zero) pha on Shelf N pha on appropriate shelf HP Survey Meter Maximum Allowable Contact Readin Specify Engineering Units For Alpha and Tritium Analysis Without Pre-Dilution Sample TYPE and Container Analysis S stem HP Survey Meter Maximum Allowable Contact Reading:
Specify Open Window (OW) or Closed Window C Specify Engineering Units Tritium in Li uid Sam le Beckman LS6500 Tritium in Gas Sparger Sam le Beckman LS6500 Alpha in Evaporated Liquid Alpha Counting Sam le In Planchet S stem Alpha Filter Sample in Planchet Alpha Counting S stem
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ML ADAMS"HQNTAD01 ID: 003677141
Subject:
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Body:
ADAMS DISTRIBUTION NOTIFICATION.
Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS.
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IE26 Startup Report/Refueling Report (per Tech Specs)
Docket:
05000335 Page 1
\\
Florida Power &light Company, 6351 S. Ocean Drive, Jensen Beach, FL 34957 APL January 12, 2000 r
L-2000-008 10 CFR 50.36 U. S. Nuclear Regulatory Commission
'ttn:
Document Control Desk Washington, DC 20555 Re:
St. Lucie Unit 1 Docket 50-335 C cle16Startu Ph sics Testin Re rt Pursuant to St. Lucie Unit 1 Technical Specification 6.9.1.1, the enclosed summary report of plant startup and power escalation testing for Cycle 16 is hereby submitted.
Should you have any questions, please contact us.
Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/spt
Enclosure:
St. Lucie Unit 1, Cycle 16 Reactor Startup Physics Testing Report cc:
Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, St. Lucie Plant QQ) i)-
an FPL Group company
0
)-
RTUP PanICS TESTING REPORT
~I
0 St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Author Reviewed
.Ac.
C Walter D. Mead, Jr.
Reactor Enginccring, St. Lucie lant n.
Lourdes M. Porro Reactor Engineering, St. Lucie Plant Date
/~ >0 i'i'ate Reviewed J otfold'h/4 P~t.
K. Nordmcycr for C. O'Farrill Nuclear Fuel, ENG Date Approved C. Ashton Pell Reactor Enginccring Supervisor, St. Lucie Plant Date
4'1 4
I II Ot. Lncie Unit 1, Cycle 16 Startup Physics Testing Report Author Walter D. Mead, Jr.
Reactor Engineering, St. Lucio Plant Date Reviewed Lourdes M. Forro Reactor Engineering, St, Lucio Plant Date Roviewed K. Nor eyer for C. OtFarrill Nuclear Fuel, ENG Dato ~Z-:Ea-99 Approved C. Ashton Pell Reactor Enginee'ring Supervisor, St. Lucie Plant Date E
800/800'd OitOOP.
sowvttnssv avaaontt OtCv t'69 799 f Bt:60 666ttOC'os'
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St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Table of Contents Section Title Pa e
~ I II III IV V
UI VII UIII IX Introduction Cycle 16 Fuel Inspection and Repair Cycle 16 Fuel Design CEA Drop Time Testing Approach to Criticality Zero Power Physics Testing Power Ascension Program Summary References 3
4 5
6 7
8 9
10 11 List ofFi ures Fi ure Title Pa e
1 2
3 4
5 6
7 As-built Reconstitution of Assembly Tl Cycle 16 Core Loading Pattern Inverse Count Ratio Plot-Channel B Inverse Count Ratio Plot-Channel D Power Distribution - 30% Power Power Distribution - 45% Power Power Distribution - 98% Power 12 13 14 15 16 17 18 List of Tables Table Title Pa e Cycle 16 Reload Sub-Batch ID.
Approach to Criticality CEA Group Worth Summary 19 20 21
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report I.
Introduction The purpose of this report is to provide a description of the fuel design and core load, and to.
summarize the startup testing performed at St. Lucie Unit 1 followingthe cycle 16 refueling outage.
The Startup testing verifies key core and plant parameters are as predicted.
The major parts of this testing program include:
1)
Initial criticalityfollowingrefueling, 2)
Zero power physics testing, and 3)
Power ascension testing During cycle 15 operation, an increase in iodine chemistry trending indicated the failure of one or more fuel pins. Fuel sipping and ultrasonic inspections were performed during the cycle 16 refueling outage. This testing confirmed the presence of failed rods in fuel assemblies residing in, very low power locations in the cycle 15 core. Of these failures, 7 of 8 assemblies with failed fuel rods were scheduled for discharge to the spent fuel pool. The remaining assembly with a failed fuel rod was repaired for re-use in the cycle 16 loading pattern. The root cause of the failures was determined by the fuel vendor to be grid-to-rod fretting.
This Cycle 16 Startup Report is being submitted in accordance with Technical Specification 6.9.1.1 as the result of the use of:
1) a repaired and reconstituted, twice-burned fuel assembly that experienced a fuel pin breach near, the end of cycle 15 operation and, 2) an assembly substituted for a fuel bundle that suffered grid strap damage in the spent fuel pool during fuel handling operations.
The test data collected during startup and summarized in this report indicates there were no observable changes in neutronic or thermal-hydraulic parameters and thus there was no significant impact to the performance of the unit. The test data satisfied all acceptance criteria and demonstrated general confoimance to predicted performance.
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report II.
C cle16FuelIns ection and Re air During the refueling outage, core-wide sipping of fuel used in cycle 15 was performed via a wet sipping system installed in the refueling machine mast. In this inspection campaign, eight fuel assemblies were identified with possible fuel failures; one twice-burned assembly (T-01) scheduled for reinsertion and seven thrice-burned assemblies scheduled to be discharged (S-30, S-32, S-34, S36, S-44, S-45, and S-48). The seven S-batch assemblies were all on the core periphery in low power locations during cycle 15 operation.
Ultrasonic inspections of these assemblies pinpointed fuel pins having the greatest probability of failure. These assemblies were reconstituted and the fuel pins subjected to further testing.
Inspection of suspect rods using eddy-current and visual techniques resulted in identifying one failed rod out of four inspected in assembly T-01, four failed rods and two rods indicating wear out of nine rods inspected in assembly S-45, and one failed rod out of four inspected in assembly S-36.
Assembly T-01 was found to have one (1) leaking fuel pin in location E-2. The failed UO~ pin has been reconstituted with a stainless steel filler rod, as shown in Figure
- 1. Thb final as-built configuration of assembly T-01 is bounded by the calculations performed in Reference 1 and satisfies all of the requirements in the guidelines provided by the Nuclear Fuels department.
The fuel vendor, Seimen's Power Corporation (SPC), has stated in Reference 2 that it is acceptable to return assembly T-01 to the reactor for continued service in Cycle 16. The S-batch assemblies were discharged to the spent fuel pool for storage.
The results of SPC's evaluation support the conclusion that the failures observed do not represent a reactor safety or a fuel operability concern. This conclusion is further strengthened by the knowledge that the rods at greatest risk for grid-to-rod fretting are high exposure, low power rods operating at the reactor core's edge and that the RCS activity of cycle 15'and prior cycles has remained at levels well below Technical Specification limits.
In addition to the repairs made to T-01, a second assembly, S-76, was replaced with fuel bundle S-50 subsequent to the original core design loading pattern. S-76 resided in the spent fuel pool during cycle 15 operation and was inspected prior to use in cycle 16. The inspection revealed damage to a spacer grid strap necessitating replacement of the assembly. The assembly S-50 is equivalent to the assembly S-76 in terms of physical dimension and neutronic characteristics. The impact on the core design parameters and the operational data was determined to be insignificant.
Allthe reload analyses continued to remain applicable for the revised core loading pattern (Reference 12)
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report III. C cle16FuelDesi n
The cycle 16 reload consists entirely of fuel manufactured by Siemens Power Corporation (SPC).
The 217 assemblies of the cycle 16 core are comprised of fuel from four batches.
Of these, 76 are fresh assemblies (Batch X), 76 are once-burned batch T and Batch U assemblies, and 65 are twice-burned assemblies from batches T and S. Table 1 provides enrichment information for the cycle 16 reload sub-batches. The design supports a cycle length between 12,480 EFPH and 12,858 EFPH based on a cycle 15 exposure of 13,600 to 14,370 EFPH.
This is the tenth cycle of operation utilizing gadolinium in the form of Gdq03, as a burnable neutron absorber. Batch X assemblies consist ofenriched UOq fuel rods and UOq-Gdq03 bearing rods (gadolinia burnable absorber fuel rods). UOq fuel rods have a central zone enrichment of4.15 and 4.45 w/o U235, whereas the UO2-Gd203 rods have a central zone of4 to 8 w/o Gdq03 dispersed in a 2.6 to 3.5 w/o U23s carrier. The total batch burnable absorber requirement for fresh fuel is 992 Gd203 rods. The mechanical design ofBatch X fuel is essentially the same as that of Batches U &
T (Cycle 15), Batch T (Cycle 14) and Batch S (Cycle 13) reload fuel. However the length of the axial blankets (UO2) rods and cutback regions (Gadolinia rods) have changed for Batch X. Also the fuel assembly design for Batch X fuel utilizes radial enrichment zoning.
The entire cycle 16 fuel load, batches S, T, U and X, consist of the debris resistant fuel assembly design first implemented in cycle 11. This design has long fuel rod lower end caps which provides protection against debris-induced-fretting in the lower end-fittin region.
The cycle 16 core map is represented in Figure 2. The assembly serial numbers and control element assembly (CEA) serial numbers are given for each core location. A low-leakage fuel management scheme similar to that of Cycle 15 is utilized in the Cycle 16 core design.
There are no vessel fluence reduction assemblies (VFRA) in the Cycle 16 core, similar to Cycle 15 core design.
The Cycle 16 core loading pattern is 90 degrees rotationally symmetric.
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report IV. CEA Dro Time Testin Following the core reload and prior to the approach to criticality, CEA drop time testing was performed. The purpose of this test is to demonstrate that the reactivity insertion as a function of time is bounded by the CEA scram worth curve assumed in the FSAR analysis.
The objective of this test is to measure the time of insertion from the fullywithdrawn position (upper electrical limit)to the 90% inserted position under hot, fullflow conditions. The average CEA drop time was found to be 2.28 seconds with maximum and minimum times of 2.52 seconds and 2.18 seconds, respectively. Alldrop times were within the 3.1 second requirement of Technical Specification 3.1.3.4 and the reload PC/M 99-016 requirements (References 10 &
13).
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report V. A roach to Criticalit The approach to criticality involved diluting from a non-critical boron concentration of 1592 PPM to a predicted critical boron concentration of 1383 PPM. Inverse count rate ratio (ICRR) plots were maintained during the period of dilution using wide range Nuclear Instrument Channels B and D. Refer to Figures 3 and 4 for ICRR information. Table 2 summarizes the dilution rates and times, as well as beginning and ending boron concentrations.
Initialcriticalityfor St. Lucie Unit 1, Cycle 16, was achieved on October 16, 1999 at 1000 with CEA group 7 at 60 inches withdrawn and all other CEAs at the all-rods-out (ARO) position. The actual critical concentration was measured to be 1393 PPM.
<j,
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report
'I.
Zero Power Ph sics Testin To ensure that the operating characteristics of the cycle 16 core were consistent with the design predictions, the followingtests were performed:
- 1) Reactivity Computer Checkout;
- 2) Dual CEDM Symmetry Test;
- 3) AllRods Out Critical Boron Concentration;
- 4) Isothermal Temperature Coefficient Measurement; and
- 5) CEA Group Rod Worth Measurements.
Proper operation of the reactivity computer was verified through the performance of two tests.
In the first, reactor power was elevated sufficiently high to ensure maximum sensitivity of the reactivity measuring system and at the same time preserve adequate margin to the point of adding heat. The second test ascertains the response to a known value of positive or negative reactivity by measuring the values of positive or negative reactor periods that result. The results of the reactivity computer checkout were compared to the appropriate predictions supplied in the reload PC/M 99-016. Satisfactory agreement was obtained.
Verification of proper CEA latching is confirmed through the use of a CEA symmetry test for those groups which contain dual CEAs (shutdown banks A&B). The prescribed acceptance criteria is that the reactivity measured for each dual CEA shall be within a15.0 pcm of the average reactivity measured all dual CEAs within the entire group. The acceptance criterion was satisfied and it was concluded there were no unlatched CEAs in either shutdown group.
The measurement of the all-rods-out (ARO) critical boron concentration was performed.
The measured value was 1434 PPM which compared favorably with the design value of 1426 PPM (Reference 7). This was within the acceptance limits of+ 50 PPM.
The measurement of the isothermal temperature coefficient was performed and the resulting moderator temperature coefficient (MTC) was derived. The MTC was determined to be 1.15 pcm/'F which fell well within the acceptance criteria of+ 2.0 pcm/'F of the design MTC of 0.99 pcm/'F (corrected).
This satisfies the Unit I Technical Specification which 'states that the MTC shall be less positive than 7.0 pcm/'F when reactor power is less than 70% power.
Rod worth measurements were performed using the rod swap methodology. This method involves exchanging a reference group, which is measured by the boration dilution technique, with each of the remaining test groups. A comparison of the measured and design CEA reactivity worths is provided in Table 3. The followingacceptance criteria applies to the measurements made:
1)
The measured value of each test group, or supergroup measured, is within+15% or+100 pcm of its corresponding design CEA worths, whichever is greater and,
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report 2)
The worth of the reference group and the total worth for all the CEA groups measured is within + 10% of the total design worth.
Allacceptance criteria were met.
VII. Power Ascension Pro ram During power ascension, the fixed incore detector system is utilized to verify that the core is loaded properly and there are no abnormalities occurring in various core parameters (core peaking factors, linear heat rate, and tilt)for power plateaus at 30%, 45%, and 98% rated thermal power.
A summary of the flux maps at the 30%, 45% and 98% power plateaus is provided in Figures 5, 6 8 7. These flux maps are used for comparing the measured power distribution with the predicted power distribution. For the purposes of the power ascension, the acceptance criteria requires the root mean square (RMS) value of the power deviation be less than or equal to 5%. In addition, for the 30% and 98% plateaus, the individual assembly powers should be within 10% of the predicted power (both) and the relative power density (RPD) should be within 0.1 RPD units of predicted for the 30% power case. These criteria were satisfied.
When the unit reached full power, a calorimetric was performed in accordance with reference 8 for the purpose of calculating the RCS flow rate. The RCS flow rate was determined to have increased from 407,206 gpm (measured in cycle 15) to 409,240 gpm in cycle 16 (reference 8).
This measured flow was well in excess of the Technical Specification minimum of 365,000 gpm and well within the flow measurement uncertainty.
Within seven effective full power days of attaining the equilibrium value of 100% power, a hot full power (HFP) MTC test was performed by maintaining power constant and varying temperature.
The center CEA (7-1) was operated to permit compensation of the resulting reactivity changes.
The HFP MTC was measured to be-6.21 pcm/'F. This satisfied the acceptance criteria to verify compliance with Technical Specification 3.1.1.4 to have a measured MTC less positive than+2.0 pcm/'F while thermal power is greater than 70%. The power coefficient was not measured.
St. Lucie-Unit-.1., Cycle 16 Startup Physics Testing Report VIII.~Summar Compliance with the applicable Unit 1 Technical Specifications was satisfactory and all acceptance criteria were met. The test data supports a conclusion that the repairs made to fuel assembly T-01 and the replacement of assembly S-76 with assembly S-50 had no significant effect on core behavior. The physics and thermal-hydraulic performance test data satisfied all acceptance criteria and demonstrated general conformance to predicted performance.
10
e St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report IX.
References 1)
FPL Calculation PSL-1FJF-99-141, Rev 1, "St. Lucie Unit I Cycle 16 Region T Bounding Fuel Pin Reconstitution" 2)
SPC Letter RIW:99:220, "Acceptability of Repaired Assembly TOI for Use in St, Lucie UnitI Cycle 16" September 29, 1999.
3)
"InitialCriticality,"Pre-Operational Procedure 1-3200088 4)
"Reload Si'artup P/iysics Testing," Pre-Operational Procedure 3200091 5)
"Reactor Lngineering Power Ascension Program,"
Pre-Operational Procedure 3200092 6)
St. Lucie Unit 1 Technical Specifications.
7)
St. Lucie Unit 1 Cycle 16 Reload PC/M ¹99016, CRN 99016-8628, Table 2.3.1 8)
"RCS Flow Determination By Calorimetric Procedure," St. Lucie Unit 1 Operating Procedure 1-0120051 9)
St. Lucie Unit 1 Cycle 16 Reload PC/M ¹99016, Rev. 2, Attachment 1, Page 28 of 30.
10)
ENG Calculation PSL-IFJF-93-025, Revision 0, "PSLI CEA Drop Time Criteriafor 90% Insertion" 11)
"At Power Deternn'nation of Moderator Temperature Coefficient and Power Coefficient, " Operating Procedure 3200051 12)
St. Lucie Unit 1 Cycle 16 Reload PC/M ¹99016, Rev. 2, Page 18 of 62.
'13)
"Periodic Rod Drop Time Test and CEA Position Functional Test,"
Operating Procedure 1-0110054 11
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report F<igure 1 As-built Reconstitution of Assembly Tl Assembly ID NW quadrant NE quadrant A
B C
D E
F G
H K
L M
N P
R SST 10 12 13 14 SW quadrant Top View SE quadrant Le end SST Stainless Steel Filler Rod 12
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Figure 2 Cycle 16 Core Loading Pattern N
T13 S72 T22 T90 X16 114 T82 X21 U51 207 X02 U46 X66 105 X26 796 117 U13 S50 X29 U66 U24 79 U21 94 Y
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T78 T36 731 T81 Assembly Serial¹~
XXX Insert Serial¹~ ¹¹ 13
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Figure 3 Inverse Count Ratio Plot - Channel B 1.0 1.0 0.9 0.9 0.8 0.7 0.7 0.6 0.6 0.5 0.5 Q.4 0.4 0.3 "a
0.2 0.2 0.1 0.1 0.0 1000 0
2000 3000 4000 5000 6000 7000 8000 9000 10000 11PPP G a~*m~ed O.Q 14
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Figure 4 Inverse Count Ratio Plot - Channel D 1.0 1.0 0.9 0.9 0.8 os 0.7 0.7 0.6 0.6 0.5 0.5 0.4 0.4 0.3 0.3 0.2 0.2 0.1 0.1 0.0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 Ganonswutea 0.0 15
St. Lucis Unit 1, Cycle 16 Startup Physics Testing Report Figurc 5 Measured:
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St.Lucle Unit1,Cycle16 Stsrtup Physics Testing Report Stessured:
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St. Lucis Unlt1, Cycle 16 Startup Physics Testing Report Figurc 7 Power Dlslrlbullon-Full Power R
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St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Sub-Batch Sl S2 S4 S6 TS UI, U2 U3 U4 US U6 Xl X2 X4 Table 1 Cycle 16 Reload Sub-Batch ID" Number ofAssemblies 20 12 20 32 16 24 24 20 Av. Enrichment 3.9 3.88 3.79 3.76 4.43 4.41 4.33 4.30 3.98 3.95 4.38 4.36 4.33 4.30 4.34 4.29 4.26 4.21
- Reference (9) 19
St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Table 2 Approach to Criticality Dilution Rate 132 gpm 88 gpm 44 gpm Initial Boron Concentration 1592 1533 1433 Final Boron Concentration 1533 1433 1393 Dilution Time (minutes) 18 48 46 20
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St. Lucie Unit 1, Cycle 16 Startup Physics Testing Report Table 3 CEA Group Worth Summary CEA Group Reference Group A 5&B 3&4 Total Measured Worth
( cm 826.05 354.95 576.64 662.98 773.97 761.00 878.05 4834.25 Design
- Worth
( cm) 860.00 340.00 570.00 595.00 771.00 780.00 833.00 4749.00 Percent Difference
-4.10 4.21 1.15 10.25 0.38
-2.42 5.13 1.76
- Reference 7 Percent difference = (Measured-Design)/(Measured)
- 100 21