JAFP-97-0090, Forwards Cycle 13 Start-Up Test Rept for Jafnpp,Which Was Submitted IAW Reporting Requirements of Section 6.3.a.1 of Plant TS
| ML20136H360 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/11/1997 |
| From: | Michael Colomb POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20136H365 | List: |
| References | |
| JAFP-97-0090, JAFP-97-90, NUDOCS 9703190123 | |
| Download: ML20136H360 (6) | |
Text
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l Jim 23 A. FitzPItrick Nucl2 r Pow 1r PIInt i
P.O. Box 41 Lycoming. New York 13093 315-342-3840 i
ewWrkPbwer Michael J. Colomb 4#
thon.ty sneexecuse a ce, l
March 11,1997 l
JAFP-97-0090 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555
Subject:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 CYCLE 13 START-UP TEST REPORT Gentlemen:
Please find attached the Cycle 13 Start-up Test Report for the James A. FitzPatrick Nuclear Power Plant, which is submitted to you in accordance with the reporting requirements of section 6.9.a.1 of the Plant Technical Specifications.
The Cycle 13 Start-Up Test Report is contained as Attachment 1. Attachment 11 is the Power Uprate Startup Test Report for Cycle 13.
We trust you will find this information satisfactory. However, should you desire more information, please contact Mr. Dave Burch at (315) 349-6311.
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Very truly yours, l
l i
I MICHAEL J. COLOMB t
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MJC/NJB/ DEB /las
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Attachments as stated.
4k CC:
U.S. Nuclear Regulatory Commission Region 1
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I NRC Resident inspector WPO for RMS Headquarters Distribution G. Rorke F. Rodriguez JAFP File - Laura Donovan JAFP File - TS RMS-JAF i
l 190009 151,E555R551115 9703190123 970311 PDR ADOCK 05000333 P
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Atta:hment i J m:s A. FitzPatrick Nucl:ar Power Mant Startup Test Report for Cycle 13 1.
Cycle 13 operations commenced on 12/07/96. The startup test program was completed on 01/08/97 after rated power with equilibrium conditions had been.
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l achieved. The program was conducted in accordance with Reactor Analyst Procedure RAP-7.3.30 " Cycle Startup Reactor Physics Test Program". Listed below is a summary of the tests referenced by RAP-7.3.30.
1.
Core Loadina and Verification:
A full core offload /onload was performed during the refuel outage in which three hundred and sixty-eight bundles were relocated, one hundred ninety-two bundles were discharged, and one hundred ninety-two new bundles j
were loaded. The Cycle 13 fuel bundle inventory breakdown is as follows:
i Fuel Type Enrichment Number Installed 1.
GE-11 3.59 %
80 Reload 10 2.
GE-11 3.56 %
72 Reload 10 3.
GE-11 3.80 %
152 Reload 11 4.
GE-11 3.59 %
16 Reload 11 5.
GE-11 3.56 %
32 Reload 11 6.
GE-11 3.56 %
4 Reload 11 7.
GE-12 4.17 %
40 Reload 12 8.
GE-12 4.12%
152 Raioad 12 1
9.
GE-10 3.22 %
5 Reload 9 10.
GE-10 3.24 %
7 Reload 9 l
The final core loading pattern was verified to be correct in accordance with Reactor Analyst Procedure RAP-7.2.4 " Reactor Core Fuel Verification" using an underwater television camera. The core loading pattern was independently verified by OA personnel.
2.
Control Rod Reolacements and Drive Mechanism Test:
Fifteen control blades were replaced during the outage with General Electric Marathon blades. A total of 86 of the one hundred and thirty seven original equipment control blades have now been replaced.
l Prior to start-up, Surveillance Test ST-20N, " Control Rod Exercise / Timing / Stall Flow Test" was performed on all 137 control rods to demonstrate that each rod is coupled to its drive mechanism, and to check that each control rod drive satisfies a travel timing test.
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Att:chment 1 James A. FitzP: trick Nucl:ar P;wcr Pl:nt Startup Test Report for Cycle 13 Control rod scram time testing was performed on all 137 control rod drives prior to reaching 40% rated core thermal power.
The results were as follows:
Notch Tech Spec Limit Average for 137 rods L
46
.338 sec .281 sec 38
.923 sec .690 sec 24 1.992 sec 1.432 sec 04 3.554 sec 2.548 sec
- The average of the scram insertion times of the three fastest operable control rods for all groupt of four controi rods in a two by two array were less than the maximum tin:es allowed by ti;s Technical Specifications.
l 3.
Shutdown Marain Test:
Initial Criticality for Cycle 13 was achieved on 12/08/96 at 0036.
Shutdown margin was demonstrated using the in-sequence critical method which showed the core to have a shutdown margin of 1.66% delta k/k. This value satisfies the Technical Specification requirement for the shutdown margin to be greater than 0.39% (delta k/k), which is 0.38% plus R, where l
R = 0.01% (delta k)/k.
I 4.
Control Rod Seouence:
The control rod withdrawal sequence was prepared and loaded into the RWM program in accordance with the requirements of Reactor Analyst Procedure RAP-7.3.32 " Reduced Notch Worth Procedure". Prior to reactor startup, surveillance test ST-20A was performed to demonstrate system operability.
I 5.
SRM Performance Check:
Source Range Monitor (SRM) Functional Testing was performed prior to startup to demonstrate operability of the SRM monitoring instrumentation.
During reactor startup, an SRM/lRM (Intermediate Range Monitor) overlap check was performed to demonstrate that each IRM was on scale before any SRM exceeded the rod block setpoint.
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Att:chmInt i Jam:s A. Fit 2P trick Nuclear P wer Pl nt Startup Test Report for Cycle 13 6.
IRM Performance Check:
IRM functional testing was performed prior to startup to demonstrate operability of the instruments. During reactor startup, an IRM/APRM (Average Power Range Monitor) overlap check was performed to demonstrate that each APRM channel was on scale before any IRM exceeded the high IRM rod block setpoint.
7.
Reactivity Anomalv Check:
A comparison between the predicted and actual control rod density was performed at 100% rated core thermal power and 97.6% rated core flow.
The actual rod inventory adjusted for thermal-hydraulic conditions was 293 notches. This value is within the Technical Specification allowable bounds of l
36 to 611 predicted notches around a value of 352 predicted notches, l
which represent a reactivity anomaly of 1% delta k/k.
8.
Core Power Distribution Measurements and LPRM Calibrations: The core power distribution was monitored throughout the power ascension using 3D-Monicore software in conjunction with the Traversing incore Probe System (TIP) and the Local Power Range Monitors (LPRMS). LPRM calibrations were performed at 50% and 100% of rated power. Acceptance criteria for LPRM gain adjustment factors (GAF) stated in RAP-7.4.3 was satisfied. All fuel power production parameters were maintained within Technical Specification limits.
9.
Core Power Svmmetry Calculations:
Bundle power symmetry was checked at 50%,75%, and 100% rated core j
thermal power. The values calculated for difference among symmetric fuel bundles are within the acceptance criteria and they are shown below.
Test Plateau Maximum % Difference Average % Difference 50% Power 7.93%
0.63 %
75% Power 7.31 %
0.59 %
100% Power 7.72 %
0.59 %
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l Att chm:nti Jimis A. FitzPatrick Nucirr P w:r Pl nt j
Startup Test Report for Cycle 13 10.
Manual Heat Balance:
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A manual heat balance was performed per RAP-7.3.3 at 25%,50%,75%,
l and 100% rated power. In each case, reactor power was calculated to be l
within 5% of the plant computer calculatica. The results satisfy the acceptance enteria and they are tabulated below.
Test Plateau Hand Calculation Computer Calc 25% Power 26.3 %
24.8 %
50% Power 50.06 %
48.80 %
75% Power 74.48 %
75.40 %
100% Power 101.97 %
100.2 %
11.
During scram time testing, when control rod insertions and withdrawals were performed, LPRM response testing was conducted on all operable detectors. This test verified that each operable detector is connected to the appropriate flux amplifier. Three LPRM assemblies were replaced during the outage. In addition, a TIP response test was conducted to verify that each i
TIP tube is connected to the appropriate LPRM assembly. Results of these tests were satisfactory.
i 12.
Core Flow Evaluation:
A Core Flow Evaluation was performed at 100% rated power per Reactor Analyst Procedure 7.3.7. The indicated flow of 74.915 Mlb/hr differed from i
the calculated flow of 74.912 Mib/hr by 0.008%, well within the procedure acceptance criteria of 1.0%.
13.
Determination of Rated Drive Flow:
A rated drive flow calculation was performed at 100% power, and the results show that a drive flow of 33.720 Mlb/hr produces the rated core flow of 77.0 Mlb/hr. The original design value for rated drive flow was 34.2 Mib/hr.
14.
TIP System Checkout:
The Traversing incore Probe System was operated in accordance with Reactor Analyst Procedure-7.3.14. Axial alignment of TIP channels assigned to machines A, B and C were checked at full power. The ability of the 3-D I
Monicore software system to adapt to the changing power shape until TIP data could be taken at steady state conditions was used to allow plant operation up to 100% power.
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Attachment i James A. FitzPatrick Nuclear P:wer Plant Startup Test Report for Cycle 13 15.
TIP Readino UncertalD1Yi The standard deviation between BASE distributions of symmetrically located TIP strings was determined at 50 percent power. The resulting TIP reading uncertainties were calculated to be 1.699%. This value are well below the 8.71% TIP reading uncertainty assumed in the Licensing Topical Report.
16.
APRM Calibrations APRM calibrations were performed as required at 25%,50%,75% and l
100% power. Additional APRM calibrations were performed as necessary throughout the startup.
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