BVY 04-068, Cycle 24 Startup Test Report

From kanterella
Revision as of 23:49, 16 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Cycle 24 Startup Test Report
ML042160021
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 07/21/2004
From: Devincentis J
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 04-068
Download: ML042160021 (8)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Vermont Yankee 185 Old Ferry Rd.

~Entergy RO. Box 500 Brattleboro, Vr 05302 Tel 802-257-5271 July 21, 2004 Vermont Yankee Docket No. 50-271 BVY 04-068 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Vermont Yankee Cycle 24 Startup Test Report The purpose of this letter is to submit the Vermont Yankee Nuclear Power Station (VY)

Cycle 24 Startup Test Report in accordance with section 6.7.A.1 of the WA Technical Requirements Manual.

There are no new commitments being made in this submittal.

If you have any questions or require additional information, please contact me at (802) 258-4236.

Sincerely, ames M. DeVincentis Manager, Licensing Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station

BVY 04-068 Docket No. 50-271 Page 2 of 2 cc: Mr. Richard B. Ennis, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Mail Stop 0 8 B1 Washington, DC 20555 Mr. Samuel J. Collins Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601

STARTUP TEST REPORT - VERMONT YANKEE CYCLE 24 In accordance with Vermont Yankee Technical Requirements Manual Section 6.7.A.1, this Startup Test Report is being submitted as a result of the following changes implemented in Cycle 24 which differ from Cycle 23:

1. Improved core physics code (PANAC 11 - TGBLA 06) - NRC approved methodology
2. Reduced SLMCPR Uncertainty - NRC approved methodology
3. Process 8 cladding - Process enhancement
4. Improved LHGR limits for GE13 fuel - GE methodology improvement
5. ARTS-MELLLA - NRC approved methodology
6. Revised thermal limit calculation - part of ARTS
7. Statistically Based Rod Withdrawal Error Analysis - GE methodology improvement -

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

Overview:

Vermont Yankee Cycle 24 initial startup commenced on May 3, 2004 following a 30-day outage for refueling and maintenance activities. Steady state, full power conditions were reached on May 8, 2004.

The core loading for Cycle 24 consists of:

Quantity Fuel Description Cycle Type loaded 8 GE-9B GE9B-P8DWB335-lOGZ-80U-150-T6 17 12 GE-9B GE9B-P8DWB335-11GZ-80U-150-T6 17 88 GE-13 GE13-P9DTB386-1 G4.0/ 1G3.0-10OT-146-T6-3958 22 16 GE-13 GE13-P9DTB225-NOG-lWT-146-T6-2571 22B 92 GE-14 GE14-PlODNAB394-7G5.0/6G4.0-0OOT-150-T6-2566 23 16 GE-14 GE14-PlODNAB394-8G5.0/6G4.0-lOOT-150-T6-2595 23 20 GE-14 GE14-PlODNAB394-12G5.0-lOOT-150-T6-2596 23 32 GE-14 GE14-PIODNAB426-16G6.0-l0T-150-T6-2682 24 44 GE-14 GE14-PlODNAB390-14GZ-10OT-150-T6-2683 24 40 GE-14 GE14-PIODNAB388-17GZ-IOOT-150-T6-2684 24 For Cycle 24, VY replaced 136 GE13 and GE9B fuel bundles with 116 new GE14 fuel bundles and 20 previously discharged GE9B fuel bundles.

Beginning of Cycle 24 start-up commenced on May 3, 2004 with steady-state full power conditions reached on May 8, 2004.

  • Page 1

Core Verification:

An as-loaded Cycle 24 core map is included as Figure 1. Details of the Cycle 24 core loading are contained in the Global Nuclear Fuels (GNF) document 0000-0026-5068-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 24," March 2004 (PROPRIETARY).

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, 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.

Process Computer Data Checks:

Process computer data evaluation checks were completed in accordance with OP- 5401 "Data Shuffling and Data Checks for Process Computer at BOC." These checks included various manual and computer checks of the new databank.

Control Rod Drive System Testing:

Eight control blades and six control rod drives were replaced during RFO24. Control rod coupling and withdrawal speed verification was completed satisfactorily for all 89 control rods per OP-4 111, "Control Rod Drive System Surveillance."

Strongest rod out sub-critical check was performed satisfactorily after the independent review of the core verification was completed. This was performed in accordance with OP-4430, "Reactivity Anomalies/Shutdown Margin Check."

Single rod scram timing was performed in accordance with OP-4424, "Control Rod Scram Testing and Data Reduction". Testing of all 89 control rods was completed during the Reactor Hydrostatic Test 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 Specifications 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.

0 Page 2

Shutdown Margin Testing:

The cold shutdown margin calculation was performed using data collected during the in-sequence critical and information provided in GNF document 0000-0026-5068-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 24," March 2004 (PROPRIETARY).

In accordance with Vermont Yankee Technical Specifications (3.3.A.1), the minimum shutdown margin required is 0.38% Ak/k. The actual demonstrated shutdown margin was 1.291% Ak/k as determined in accordance with OP-4430 "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 24-A2-(1) was used to perform the in-sequence critical test. Criticality was achieved on the 10"O (last) rod in group 2 (26-15) at notch position 36. The moderator temperature was 152.6 'F.

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

LPRM Operability Check:

Four NA300 local power range monitors (LPRM) were replaced during RFO24. The new LPRM initial operating current was set in accordance with OP-1408, "LPRM Removal and Replacement" and electrically checked per OP-5307 "Electrical Checkout of Neutron Monitoring Detectors."

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."

APRM Calibration:

In accordance with Vermont Yankee Technical Specification Section 2.1.A, Average Power Range Monitor (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.

  • Page 3

TABLE I CONTROL ROD SCRAM TESTING RESULTS VERMONT YANKEE BEGINNING OF CYCLE 24 Scram Number: 210 Single Rod Scram testing performed on April 26,2004 Reactor Pressure: 1020 Pisa Reactor Power: 0°/0 Full Core Average - Number of Rods Averaged: 89 Dropout Position Avg. Scram Time Admin. Limit Pass/Fail 46 0.291 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.I 3.3.C.1.2 PAS 46 0.291 0.358 PASS 0.358 PASS 36 0.794 0.912 PASS 1.096 PASS 26 1.312 1.468 PASS 1.860 PASS 6 2.405 2.686 PASS 3.419 PASS Slowest 2X2 Average Summary for Each % Insertion

  • Dropout Position 2 X 2 Average
  • Admin. Limit Pass/Fail 46 0.299 0.368 PASS Notch Number 2 X 2 Average* Tech. Spec. Pass /Fail Tech. Spec. Pass/ Fail Insertion time Criteria 3.3.C. 1.I Criteria 3.3.C.1.2 46 0.299 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 PASS
  • 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 6 06-23 2.691 7.000 PASS 0 Page 5

TABLE 2 CORE AVERAGE AXIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE,3 VERMONT YANKEE BEGINNING OF CYCLE 24 Node 3D Simulate 25 0.082 0.090 24 0.214 0.220 23 0.397 0.370 22 0.511 0.470 21 0.595 0.540 20 0.657 0.600 19 0.706 0.650 18 0.757 0.700 17 0.787 0.720 16 0.820 0.760 15 0.892 0.840 14 1.064 1.000 13 1.151 1.100 12 1.253 1.220 11 1.335 1.300 10 1.385 1.370 9 1.453 1.470 8 1.518 1.540 7 1.554 1.600 6 1.603 1.680 5 1.635 1.720 4 1.611 1.710 3 1.481 1.580 2 1.146 1.240 1 0.392 0.350 TABLE 3 RELATIVE RADIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE-3 VERMONT YANKEE BEGINNING OF CYCLE 24 Ring 3D Simulate 1 0.935 0.929 2 1.347 1.368 3 1.172 1.201 4 1.138 1.142 5 1.120 1.115 6 0.673 0.655

  • Page 6

FIGURE 1 VERMONT YANKEE CYCLE 24 CORE MAP 44 l::::I6JZYJ2j2 l YJ~ssza g H 42 JS0 w

xsZ0SyZ II 2A22 2" 41 Lc2 t

lYJZ301 40 I A 4 I .1 Il -t LL7s YJZ326J YJZ320 l YJ257 WHo 38 MM762ILCS YJ2329 YJS134 36 34 32 30 YJ2341 YJzsis 28 YJ532S VI1324 26 VJZ297 VIZ344 24 YJZ53 yz"M YJZ284 1

-1" 22 AgII' YJZI13 YJZ310 yizist YJZ330 20 VJZ2 YJzaaI jLtSl 5 YJZ345 l Z3Is i8 WE.

0 9 YJS3k7 16 YJZ314 14 12 10 a II' 4U U III" PW W Fwol e4 6 lYJS139 YJ220SYJZ331le JmTz~ L75S -,' JaLL Ja750 a7s1' 4 YJ2305 j iL2 rit25 wt22s YJZ294 2 ,43z Gz342 nz3ot JUl02 Yt31i YJS3ZS 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 Core loading reference document: Cycee24 Core Management Rsprt YJZ269-356 - C-22: CE-13 381 1G4.013.0 (88 bundles) Form completed by: oil 1401.01.Wgd I Mar. la 2004 JLE 291412 - C-228: OE-13 225O Gad (16 bundles) Chip Dean dat L01505498 - C-23: OE-14 394-7G5.0iW4.0 (02 bundles)

C-23: GE-14 394-BG5.0lG4.0 (16 bundles)

JLL 763-784 - C-23: GE-14 304-1205.0 (20 bundes) Verified RvB flH.II 1401.01 X..V- I LAr. IN 200i C-24: GE-14 428-1608.0 32 bundtes) Jos" Anderson dete L 828 - C-24: 0E-14 390-14GZ (44 bundOes)

C-24: 0E-14 388-17GZ (40 bundes)

YJ6-* - C-24: GE-8 335-1011 iGZ (20 ReInsert bundles orignially loaded hI 1 iore weln l

  • Page 7
Retrieved from "https://kanterella.com/w/index.php?title=BVY_04-068,_Cycle_24_Startup_Test_Report&oldid=2614407"