BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing

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Cycle 25 Startup Test Report Following Power Ascension and Testing
ML062160129
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 08/01/2006
From: Ted Sullivan
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 06-068
Download: ML062160129 (10)
v • d • e


Text

Entergy Nuclear Operations, Inc.

Vermont Yankee

-Entergy P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Tel 802 257 5271 August 1, 2006 BVY 06-068 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)

Vermont Yankee Cycle 25 Startup Test Report Following Power Ascension and Testing The purpose of this letter is to submit the Vermont Yankee (VY) Cycle 25 Startup Test Report in accordance with the VY Technical Requirements Manual (TRM). TRM Section 6.7.A.1 requires a summary report of plant startup and power escalation testing be submitted following an amendment to the license involving a planned increase in power level. On May 5, 2006, VY obtained the new authorized power level of 1912 MWT.

There are no new regulatory commitments contained in this submittal.

We trust that the information provided is adequate; however, should you have questions, please contact James M. DeVincentis at (802) 258-4236.

Sincerely, Site Vice President Vermont Yankee Nuclear Power Station Attachment (8 pages) 0?,'-?

BVY 06-068 Page 2 of 2 cc: Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James J. Shea, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601

STARTUP TEST REPORT - VERMONT YANKEE CYCLE 25 In accordance with Vermont Yankee Technical Requirements Manual Section 6.7.A.1, this Startup Test Report is being submitted to the NRC since a 20 % Extended Power Uprate (EPU) was implemented. This Startup Test Report contains Cycle 25 startup data (November 2005) and an EPU summary (March 2006 to May 2006).

In accordance with USFAR Section 13.5.5, the following information is being provided in this Startup Test Report.

Overview:

Vermont Yankee Cycle 25 initial startup commenced on November 10, 2005, following a 19-day outage for refueling and maintenance activities. Steady state, full power conditions were reached on November 14,2005.

The core loading for Cycle 25 consists of the following:

Quantity Fuel Description Cycle Type loaded 92 GE- 14 GEl 4-PIODNAB394-7G5.0/6G4.0-100T-150-T6-2566 23 16 GE-14 GE14-P1ODNAB394-8G5.0/6G4.0-1OOT- 150-T6-2595 23 20 GE-14 GE14-PIODNAB394-12G5.0-100T-150-T6-2596 23 32 GE-14 GE14-P1ODNAB426-16G6.0-100T-150-T6-2682 24 44 GE-14 GE14-PIODNAB390-14GZ-100T- 150-T6-2683 24 40 GE-14 GE14-P1ODNAB388-17GZ-100T-150-T6-2684 24 48 GE-14 GE14-P1ODNAB422-16GZ- 100T- 150-T6-2862 25 32 GE-14 GE14-PIODNAB383-14G6.0-100T- 150-T6-2864 25 28 GE-14 GE14-P1ODNAB383-13G6.0-100T-150-T6-2863 25 16 GE-14 GE14-P1ODNAB383-17G6.0-100T-150-T6-2865 25 For Cycle 25, VY replaced 104 GE13 and 20 GE9B fuel bundles with 124 new GE14 fuel bundles.

Core Verification:

An as-loaded Cycle 25 core map is included as Figure 1. Details of the Cycle 25 core loading are contained in the Global Nuclear Fuels (GNF) document 0000-0045-9096-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 25 (at Current Licensed Power Level of 1593 MWt)," October 2005 (PROPRIETARY).

  • Page 1 of 8

Vermont Yankee personnel verified the final as-loaded core loading in accordance with Vermont Yankee procedure OP-141 1, "Core Verification." Three separate criteria were checked:

1. Proper bundle seating was checked.
2. Proper bundle orientation, channel fastener integrity and upper tie plate cleanliness were checked and verified.
3. Proper core loading was verified by checking the serial number of each bundle against the final approved core-loading map.

This verification was performed independently by two separate teams.

Process Computer Data Checks:

Process computer data evaluation checks were completed in accordance with ENN-DC-503 "3D Monicore New Cycle Update and Databank Maintenance." These checks included various manual and computer checks of the new databank, including updating and checking the new databank for EPU conditions.

Control Rod Drive System Testing:

No control blades and six control rod drive mechanisms were replaced during RF025. Control rod coupling and withdrawal speed verification were completed satisfactorily for all 89 control rods per OP-41 11, "Control Rod Drive System Surveillance."

Single rod scram timing was performed in accordance with OP4424, "Control Rod Scram Testing and Data Reduction." Testing of all 89 control rods was completed in conjunction with OP-4101 "RPV Operational System Leakage Test" and in accordance with Vermont Yankee Technical Specification Section 4.3.C.1. All insertion times were within the limits defined in the Vermont Yankee Technical Specification Section 3.3.C.1. In accordance with Vermont Yankee Technical Specification Section 4.3.C.2, the results of the testing are included in Table 1.

Shutdown Margin Testing:

The cold shutdown margin calculation was performed using data collected during the in-sequence critical and information provided in Global Nuclear Fuels (GNF) document 0000-0045-9096-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 25 (at Current Licensed Power Level of 1593 MWt)," October 2005 (PROPRIETARY).

In accordance with Vermont Yankee Technical Specification Section 3.3.A.1, the minimum shutdown margin required is 0.38% Ak/k. The actual demonstrated shutdown margin was 1.129%

Ak/k as determined in accordance with OP-4430 "Reactivity Anomalies/Shutdown Margin Check."

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In-Sequence Critical Eigenvalue:

The in-sequence critical test was performed as part of the reactor startup. Control rod sequence 25-A2-(1) was used to perform the in-sequence critical test. Criticality was achieved on the 9h rod in group 2 (18-3 1) at notch position 26. The moderator temperature was 195 'F as recorded by Emergency Response Facility Information System Emergency (ERFIS) point ID B023.

The actual critical rod pattern and the prediction agreed within +/- 1% Ak per OP-4430 "Reactivity Anomalies/Shutdown Margin Check."

LPRM Operability Check:

No local power range monitors (LPRM) were replaced during RF025.

LPRM connection verification and hi and low trip alarm set points were performed satisfactorily in accordance with OP 4406, "LPRM Calibration and Functional Check".

The local power range monitors were calibrated at approximately 100% Core Thermal Power (CTP) in accordance with OP 2425, "Core Power Distribution Calculation Utilizing the Traversing In-Core (TIP) System" and OP 4406, "LPRM Calibration and Functional Check."

APRM Calibration:

In accordance with Vermont Yankee Technical Specification Section 2.1.A, APRM gain adjustments were performed as required in accordance with OP 4400 "Calibration of the Average Power Range Monitoring System to Core Thermal Power." In addition, APRM gain adjustments were performed throughout the reactor startup.

Core Performance Evaluations:

In accordance with Vermont Yankee Technical Specification Section 3.11, the Average Planer Linear Heat Generation Rate (APLHGR), Linear Heat Generation Rate (LHGR) and Minimum Critical Power Ratio (MCPR) were all checked within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of reaching 25% CTP in accordance with OP 4401, "Core Thermal Hydraulic Limits Evaluation." The limits were all less than 1.0 as specified in the Vermont Yankee Technical Specifications.

At approximately 50, 75 and 100 percent power level, a heat balance calculation was performed using three separate computer calculations in accordance with OP 2409 "Operating Data Collection and Evaluation" and OP 2410 "Reactor Core Thermal Power Evaluation." The calculated core thermal power from each method was found to be in agreement (within 5 Megawatts thermal).

Core flow calibration was completed in accordance with OP 2429 "Recirculation Flow System Baseline Data Collection and Instrument Calibration" and OP 2440 "Reactor Core Flow 0 Page 3 of 8

Determination" to ensure that the core flow calculation by the process computer is accurate over the entire operating range.

Process Computer Power Distribution:

The plant process computer power distribution was updated at approximately 73% CTP using the TIP system during the ascent to full power. A few days later, the plant process computer power distribution was updated at approximately 100% CTP (1593 MWT) using the TIP system.

The process computer power distribution update performed after reaching steady state conditions was used as a basis for comparison with an off-line calculation performed using SIMULATE-3.

The axial and radial power distribution comparison between 3D Monicore (on-line code) and Simulate-3 (off-line code) is documented in Table 2 and Table 3. The result of the comparison is acceptable.

In addition, the plant process computer power distribution was updated for EPU conditions at approximately 100% CTP (1912 MWT) using the TIP system.

TIP Uncertainty:

Total TIP uncertainty was calculated in accordance with OP 4455, "TIP Uncertainty." The resulting total TIP uncertainty for this case of 1.22% is less than the 6% licensing acceptance criteria.

EPU:

On March 4, 2006, following receipt of License Amendment No. 229 to increase maximum authorized reactor power level, Vermont Yankee started a controlled and deliberate power ascension program including the following activities:

" APRM setpoint change and calibration to new 100% licensed power level.

" Individual power increase limits of 1% per hour.

" At each 5% power level increment, testing of the feedwater level control response and turbine pressure control systems was performed.

" In accordance with the steam dryer monitoring plan and license condition requirements, steam dryer monitoring system data was obtained and analyzed hourly during power ascension. In addition, at each 5% increment, data was supplied to the NRC and a minimum 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> hold period was implemented.

" At each 5% increment, plant piping walkdown and monitoring data were obtained and provided to the NRC for review. System walkdown information was also obtained and evaluated at each hold point.

On May 5, 2006 Vermont Yankee achieved the new 100% authorized reactor power level of 1912 MWT.

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On May 8,2006, a Condensate Pump Trip Test at Full EPU Power, ERSTI-04-VTYI-1409-000 8 was implemented successfully per VY's EPU license condition: "Prior to exceeding 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of plant operation at the nominal full power EPU reactor power level, with feedwater and condensate flow rates stabilized at approximately the EPU full power level, confirm through performance of transient testing that the loss of one condensate pump will not result in a complete loss of reactor feedwater."

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TABLE I CONTROL ROD SCRAM TESTING RESULTS VERMONT YANKEE BEGINNING OF CYCLE 25 Scram Number: 218 Single Rod Scram testing performed on November 8, 2005 Reactor Pressure: 1020 Psia Reactor Power: 0%

Full Core Average - Number of Rods Averaged: 89 Dropout Position Avg. Scram Time Admin. Limit Pass/Fail 46 0.290 0.347 PASS Dropout from Average Scram Tech. Spec. Pass/Fail Tech. Spec. Pass/Fail Notch Position Insertion Time Criteria Criteria 3.3.C. 1.1 3.3.C. 1.2 PASS 46 0.290 0.358 PASS 0.358 PASS 36 0.800 0.912 PASS 1.096 PASS 26 1.327 1.468 PASS 1.860 PASS 06 2.436 2.686 3.419 PASS Slowest 2X2 Average Summary for Each % Insertion

  • Dropout 2 X 2 Average
  • Admin. Limit Pass/Fail Position 46 0.290 0.368 PASS Dropout from 2 X 2 Average
  • Tech. Spec. Pass/Fail Tech. Spec. IPass/Fail Notch Position Insertion Time Criteria Criteria 3.3.C.1.1 3.3.C. 1.2 PASS 46 0.290 0.379 PASS 0.379 PASS 36 0.813 0.967 PASS 1.164 PASS 26 1.343 1.556 PASS 1.971 PASS 06 2.474 2.848 PASS 3.624
  • The 2X2 Averages consist of the slowest arithmetic average of the three fastest rods in a 2X2 array.

Slowest Single Rod Dropout Position Rod Id. Scram Time Tech. Spec. Criteria 3.3.C.2. Pass/Fail 06 22-03 2.710 7.000 PASS 0 Page 6 of 8

TABLE 2 CORE AVERAGE AXIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE-3 VERMONT YANKEE BEGINNING OF CYCLE 25 Node 3DM Simulate-3 25 0.115 0.105 24 0.295 0.317 23 0.452 0.432 22 0.578 0.552 21 0.670 0.638 20 0.751 0.718 19 0.808 0.774 18 0.837 0.805 17 0.849 0.797 16 0.850 0.793 15 0.908 0.856 14 1.101 1.016 13 1.171 1.105 12 1.269 1.217 11 1.347 1.293 10 1.375 1.343 9 1.402 1.406 8 1.45 1.464 7 1.475 1.508 6 1.506 1.592 5 1.542 1.643 4 1.506 1.626 3 1.352 1.493 2 1.030 1.169 1 0.361 0.337 TABLE 3 RELATIVE RADIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE-3 VERMONT YANKEE BEGINNING OF CYCLE 25 Ring 3DM Simulate-3 1 0.823 0.802 2 1.193 1.205 3 1.112 1.107 4 1.175 1.179 5 1.135 1.139 6 0.702 0.696 S Page 7 of 8

FIGURE 1 Vermont Yankee Core Map

, North Cvcle 25 44 42 40 38 I 1 I I 7 9 11 13 15 177I I 19 I 21 23 25 27 I 29

--- C-23: GZ14-P1ODNAB3 4--7GS.0/ 6 92 Core Loading Reference Document:DRl0000-OO3S-6409 C-23: GE14-P10DtaAB394-SG5.0/06 16 Reference Loading Pattern (RLP) Databank

--- C-23: GE14-P10DUAB394-12G5.U 20 Edit

--- C-24: GE14-PIODNA.B426-16G6.0 32

--- C-24: GE14-PIODNAB390-14GZ 44, Form Completed by: (Originalsignedby Je..*'r L. Dean) (*A04/2005

--- C-24: GE14-PIODNAB388-17GZ 40

--- C-25: G~E14-PIODUAB422-16GZ 48,

--- C-25: GE14-PIODNAfl383-14G6.0 32 Verified by: (0,igmaI i~g-dby. Robel A Vita) OMi4=5~f

--- C-25: GE14-PIODNAB383-13G6.0 28:

--- C-25: GE14-PI0DNAB3!33-17G6.0 16 36a Core Weight: 72.867 ST VYOPF 1410 03 0P1410 PageRev. 26 1 of 1 0 Page 8 of 8

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