BVY 10-043, Cycle 28 Startup Report

Cycle 28 Startup Report

ML102250208
Person / Time
Site:	Vermont Yankee
Issue date:	08/10/2010
From:	Michael Colomb Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 10-043
Download: ML102250208 (8)

Text

Entergy Nuclear Operations, Inc.

Vermont Yankee 320 Governor Hunt Road 4Entergy Vernon, VT 05354 Tel 802 257 7711 Michael J. Colomb Site Vice President BVY 10-043 August 10, 2010 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Cycle 28 Startup Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28

Dear Sir or Madam:

The purpose of this letter is to submit the Vermont Yankee (VY) Cycle 28 Startup 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 installation of fuel that has a different design. On May 22, 2010 following a refueling and maintenance outage, VY commenced operation with a partial core load of GNF2 nuclear fuel assemblies.

There are no new regulatory commitments being made in this submittal.

Should you have any questions regarding this submittal, please contact Mr. Robert J.

Wanczyk at (802) 451-3166.

Sincerely,

[MJC/JTM]

Enclosure:

Startup Report - Vermont Yankee Cycle 28 (6 pages) cc list: next page

BVY 10-043 / Page 2 of 2 cc: Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee 320 Governor Hunt Road Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620

STARTUP REPORT - VERMONT YANKEE CYCLE 28 In accordance with Vermont Yankee (VY) Technical Requirements Manual Section 6.7.A. 1, this Startup Report is being submitted as a result of installation of fuel that has a different design compared to previous reloads. VY Cycle 28 included installation of 116 new GNF2 fuel assemblies. The report will summarize the tests performed and include a general description of the results as compared to design predictions and specifications.

In accordance with VY Updated Final Safety Analysis Report (UFSAR) Section 13.5.5, the following test information is being provided in this report.

Overview:

Vermont Yankee Cycle 28 initial startup commenced on May 22, 2010 following a 29 day outage for refueling and maintenance activities. Steady state, full power conditions were reached on June 5, 2010.

The core loading for Cycle 28 consists of:

Quantity Fuel Description Cycle Type loaded 4 GE14 GEl 4-P1 ODNAB383-17G6.0- 100T-I 50-T6-2865 25 4 GNF2 GNF2-P10DG2B387-15GZ- 100T2-150-T6-2977-LUA (GNF2) 26 40 GE14 GE 14-PI ODNAB422-14GZ- 1 OT-I 50-T6-2965 (GEl 4C) 26 44 GE14 GE14-P1ODNAB388-15GZ-100T-150-T6-2968 (GE14C) 26 40 GE14 GE14-P1ODNAB388-15GZ-100T-150-T6-2969 (GE14C) 26 32 GE14 GE 14-P IODNAB421-16GZ- 1GOT- 150-T6-3084 (GE I4C) 27 24 GE14 GEl 4-P IODNAB388-15GZ- 1OOT- 150-T6-3086 (GE14C) 27 16 GE14 GE14-PIODNAB420-16GZ- lOOT-1 50-T6-3085 (GE14C) 27 48 GE14 GEl4-PIODNAB388-16GZ- 1GOT-150-T6-3087 (GE14C) 27 48 GNF2 GNF2-P 10DG2B404-18GZ- 10OT2-150-T6-3262 (GNF2) 28 16 GNF2 GNF2-P10DG2B403-11G6.0-100T2-150-T6-3261 (GNF2) 28 32 GNF2 GNF2-P10DG2B404-14GZ- 100T2-150-T6-3260 (GNF2) 28 20 GNF2 GNF2-P I0DG2B403-14G6.0-100T2-150-T6-3259 (GNF2) 28 For Cycle 28, VY replaced 116 GE14 fuel bundles with 116 new GNF2 bundles.

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Core Verification:

An as-loaded Cycle 28 core map is included as Figure 1. Details of the Cycle 28 core loading are contained in the Global Nuclear Fuels (GNF) document 0000-0100-8162-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 28," May 2010.

VY personnel verified the final as-loaded core loading in accordance with Entergy procedure EN-RE-210, "BWR Reactor Core and MPC Cask Fuel Verification." Three separate criteria were checked:

1. Proper bundle seating was checked, corrected as necessary and verified.

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 and completed on 5/12/10.

Process Computer Data Checks:

Process computer data evaluation checks for Cycle 28 were completed in accordance with EN-DC-503, "3D Monicore New Cycle Update and Databank Maintenance." These checks included various manual and computer checks of the new databank prior to, and during reactor startup.

Control Rod Drive System Testing:

Six control rod drives were replaced during RF028. On 5/22/10, control rod coupling and withdrawal speed verification was completed satisfactorily for all 89 control rods per OP4 111, "Control Rod Drive System Surveillance."

Single rod scram timing was performed in accordance with OP4424, "Control Rod Scram Testing and Data Reduction." On 5/19/10, testing of all 89 control rods was completed in conjunction with OP4101 "RPV Operational System Leakage Test" and in accordance with VY Technical Specification (TS) Section 4.3.C. 1.a prior to operation above 40% RTP (rated thermal power). All insertion times were within the limits defined in the VY TS Section 4.3.C and Table 4.3.C-1. All control rods were found to be operable, and none were considered to be slow.

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Shutdown Margin Testing:

The cold shutdown margin calculation was performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of criticality using data collected during the in-sequence critical and information provided in Global Nuclear Fuels (GNF) document 0000-0100-8162-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 28," May 2010.

In accordance with VY TS (3.3.A.1), the minimum shutdown margin required is 0.38% Ak/k.

The actual demonstrated shutdown margin was 1.579% Ak/k as determined in accordance with OP4430 "Reactivity Anomalies/Shutdown Margin Check."

In-Sequence Critical Eigenvalue:

The in-sequence critical test was performed as part of the reactor startup. Control rod sequence 28-A2-(1) was used to perform the in-sequence critical test. Criticality was achieved on the 10Ith rod in group 2 (26-15) at notch position 20. The moderator temperature was 182 'F and reactor period was 205 seconds.

The actual critical rod pattern and the prediction agreed within +/- 1% Ak per OP4430 "Reactivity Anomalies/Shutdown Margin Check."

LPRM Operability Check:

Three local power range monitors (LPRMs) were replaced during RF028 per OP1408, "LPRM Removal and Replacement." Initial calibration currents were set and all power supplies were checked per OP1408.

LPRMS were calibrated at 100% CTP in accordance with OP4406, "LPRM Calibration and Functional Check" on 6/9/10.

APRM Calibration:

In accordance with VT TS Section 2.1 .A and Table 4.1.1, APRM gain adjustments were performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of achieving 23% CTP and throughout the startup as required in accordance with OP4400, "Calibration of the Average Power Range Monitoring System to Core Thermal Power."

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Core Performance Evaluations:

In accordance with VY TS 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 23% CTP and daily thereafter in accordance with OP4401, "Core Thermal Hydraulic Limits Evaluation." The limits were all less than 1.0 as specified in the VY TS.

At approximately 30, 50, 75 and 100 percent power level, a manual heat balance calculation was performed using three separate computer calculations in accordance with OP2410 "Reactor Core Thermal Power Evaluation." The calculated core thermal power from each method was found to be in agreement.

Process Computer Power Distribution:

The plant process computer power distribution was updated at 64% and 100% CTP using the TIP system during the ascent to full power in accordance with OP2425, "Core Power Distribution Calculation Utilizing the Traversing In-Core (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 1 and Table 2. Theresult of the comparison is acceptable.

TIP Uncertainty:

Total TIP uncertainty was calculated in accordance with EN-RE-209, "TIP Symmetry Check."

The resulting total TIP uncertainty for this case of 2.48% is below the 6.0% licensing acceptance criteria assumed in determining the safety limit MCPR.

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TABLE 1 CORE AVERAGE AXIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE-3 VERMONT YANKEE BEGINNING OF CYCLE 28 Node 3DM Simulate-3 25 0.156 0.134 24 0.370 0.385 23 0.563 0.509 22 0.693 0.645 21 0.785 0.735 20 0.871 0.832 19 0.926 0.892 18 0.976 0.947 17 1.056 1.041 16 1.071 1.050 15 1.099 1.097 14 1.187 1.178 13 1.193 1.176 12 1.233 1.227 11 1.257 1.259 10 1.256 1.261 9 1.294 1.307 8 1.324 1.340 7 1.331 1.358 6 1.355 1.388 5 1.365 1.399 4 1.313 1.357 3 1.172 1.230 2 0.841 0.970 1 0.314 0.282 TABLE 2 RELATIVE RADIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE-3 VERMONT YANKEE BEGINNING OF CYCLE 28 Ring 3DM Simulate-3 1 0.933 0.910 2 1.319 1.345 3 1.280 1.300 4 1.172 1.176 5 1.080 1.075 6 0.646 0.633 Page 5

FIGURE 1 Vermont Yankee Core Map North Cycle 28 1 3 5 7 9 11 13 27 29 31 33 35 37 39 41 43 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 A GEl 4-P 10DNAB383-17G6.0-1 0OT- 150-T6-2865 4 Core Loading Reference Document: RLP C28DatabankEdit B GNF2-P 10DG2B387-15GZ-100T2-150-T6-2977-LUA 4 C GE14-P10DNAB422-14GZ-1 OT- I50-T6-2965 40 D GE14-P10DNAB388-15GZ-1 OCT-150-T6-2968 44 E GE14-P10DNAB388-15GZ-1 OT-1 50-T6-2969 40 Form Completed by: John Card! original igned F GE14-P10DNAB421-16GZ-100T-150-T6-3084 32 G GE14-P10DNAB420-16GZ-100T-1 50-T6-3085 16 H GE14-P10DNAB388-15G6.0-1O0T-1 50-T6-3086 24 GE14-P10DNAB388-16GZ-100T-1 50-T6-3087 48 Verified by: Dennis Pearsonoinginal sigRned J GNF2-Pl0DG2B403-14G6.0-1 00T2-150-T6-3259 20 K GNF2-P10DG2B404-14GZ-100T2-150-T6-3260 32 Core Weight: 73.7204 ST L GNF2-P10DG2B403-1 1GO-100T2-1 50-T6-3261 16 M GNF2-PlODG2B404-18GZ-100T2-150-T6-3262 48 Page 6