ML17291B175
| ML17291B175 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/31/1995 |
| From: | PARRISH J V WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GO2-95-277, NUDOCS 9512280207 | |
| Download: ML17291B175 (17) | |
Text
CATEGORY j REGULATOR INFORMATION DISTRIBUTION S STEM (RIDS)ACCESSION NBR:9512280207 DOC.DATE: 95/12/31 NOTARIZED:
NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION PARRISH,J.V.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
"Reactor Power Uprate Startup Test Rept," for WNP-2.W/951215 ltr.DZSTRZBOTZON CODE: ZE26D COPZES RECEZVED:LTR l ENCL i SZZE: TITLE: Startup Report/Refueling Report (per Tech Specs)NOTES: RECIPIENT ID CODE/NAME PD4-2 PD INTERNAL: ACRS NRR/DSSA/SRXB/B EXTERNAL: NOAC COPIES LTTR ENCL 1 1 5 5 1 1 1 1 RECIPIENT ID CODE/NAME CLIFFORDPJ ILE C MPR~RGN4 FILE 01 NRC PDR COPIES LTTR ENCL 1 1 1 1 1.1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE)CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12 ti WASHINGTON PUBLIC POWER SUPPLY SYSTEM PO.Box 968~3000 George Washington Way~Richland, Washington 993S2-0968
~(509)372-SOOO December 15, 1995 G02-95-277 Docket No.50-397 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555 Gentlemen:
Subject:
NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 REACTOR POWER UPRATE STARTUP TEST REPORT Transmitted herewith is the reactor power uprate Startup Test Report for the WNP-2 Plant.This report is submitted in accordance with the requirements of WNP-2 Technical Specification 6.9.1.1.The report summarizes the startup testing performed on WNP-2 following implementation of reactor power uprate during the spring 1995 refueling outage (R-10).Should you have any questions or desire additional information, please call me or D.A.Swank at (509)377-4563.Sincerely, J..Parrish (Mail Drop 1023)Vice President, Nuclear Operations JVP/DLM Enclosure CC: LJ Callan, NRC-RIV KE Perkins, Jr., NRC-RIV, Walnut Creek Field Office NS Reynolds, Winston&Strawn JW Clifford, NRC NRC Sr.Resident Inspector (Mail Drop 927N, 2 Copies)DL Williams, BPA (Mail Drop 399)95i2280207 95i23i PDR ADOCK 05000397 P PDR WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP-2 REACTOR POWER UPRATE STARTUP TEST REPORT December 1995 TABLE OF CONTENTS 1.0 2.0 3.0 4'EXECUTIVE
SUMMARY
INTRODUCTION POWER UPRATE TEST PROGRAM DESCRIPTION
SUMMARY
OF TEST RESULTS REFERENCES PAGE TABLES TABLE 1-Initial Power Ascension Startup Tests
EXECUTIVE
SUMMARY
This report summarizes the startup testing performed on WNP-2 following implementation of reactor power uprate during the spring 1995 refueling outage (R-10).Implementation of the reactor power uprate program resulted in an approximately five percent increase in reactor power.The WNP-2 reactor power uprate test program began on July 6, 1995, with the plant at approximately 50 percent power.All control system testing at the uprated power level was completed on July 12, 1995.The Reactor Power Uprate Test Sequence procedure was completed on September 26, 1995, after test results from the feedwater flow element calibration accuracy testing were obtained.The test program included reactor feedwater water level system and pressure regulator control system testing to show acceptable adjustments and operational capability.
Test results were compared to acceptance criteria and in all cases, the acceptance criteria were satisfied.
No adjustments to control system controller settings were required.The plant operated very well at the uprated conditions.
INTRODUCTION WNP-2 is a GE BWR-5 which achieved commercial operation in December 1984.On July 9, 1993 the Supply System requested a change to the Facility Operating License to increase rated thermal power from 3323 MWt to 3486 Mwt.This 4.94 increase in power is achieved by increasing steam flow and feedwater flow five percent and increasing reactor pressure by 15 psig.This report, summarizes the startup testing performed on WNP-2 following implementation of reactor power uprate during the spring 1995 refueling outage (R-10).The initial power ascension startup tests for WNP-2 are described in Chapter 14 of.the FSAR (reference 1)and are listed in Table 1.These tests were reviewed for applicability to reactor power uprate.The tests which were determined to be applicable to power uprate are also noted in Table 1.Additional surveillance tests which are normally performed during a startup following a refueling outage were also performed.,
Table 1 Initial Power Ascension Startup Tests FSAR Initial Power Ascension Startup Test Test Procedures No.Chemical and Radiochemical Radiation Measurements Fuel Loading Full Core Shutdown Margin Control Rod Drive System SRM Performance and Control Rod Sequence 9 Water Level Reference Leg Temperature Measurement 10 IRM Peiformance 11 LPRM Performance 12 APRM Calibration Tests Performed Specifically for Power Uprate No No No No No No No No No No 14 16A Process Computer RCIC System Process Temperatures System Expansion No Yes (Note 1)No No 18 Core Power Distribution 19 Core Performance 20 Steam Production 21 Core Power Void Mode Yes (Note 1)Yes (Note 1)No No 22 23A 23B 23C 23D Pressure Regulator Water Level Setpoint and Manual Flow Changes Loss of Feedwater Heating Feedwater Pump Trip Maximum Feedwater Runout Capability Yes Yes No No No il FSAR Initial Power Ascension Startup Test Test Procedures No.24 Turbine Valve Surveillance 25A MSIV Function Tests 25B Full Reactor Isolation 26 Relief Valves Tests Performed Specifically for Power Uprate No No No No 27 28 29A 29B 30A 30B'30C 30D 30E 31 33 34 35 70 71 72 74 Turbine Trip and Generator Load Rejection Shutdown from Outside the Main Control Room Recirculation Flow Control Valve Position Control Recirculation Flow Loop Control Recirculation System One Pump Trip Recirculation System RPT Trip of Two Pumps Recirculation System Performance Recirculation Pump Runback Recirculation System Cavitation Loss of Turbine Generator and Offsite Power Piping Vibration RPV Internals Vibration Recirculation System Flow Calibration Reactor Water Cleanup System A Residual Heat Removal System Drywell Atmosphere Cooling System Cooling Water Systems Offgas System No No No No No No No No No No No No Yes (Note 1)No No No No No NOTE 1: Existing plant surveillance procedure was used instead of developing a special power uprate test procedure.
POWER UPRATE TEST PROGRAM DESCRIPTION The reactor power uprate startup testing requirements were developed from a review of Chapter 14.2 of the WNP-2 FSAR and the WNP-2 Power Uprate Project Startup Test Specification (reference 2)provided by the General Electric Company.The test program includes all testing required by the WNP-2 Licensing Submittal For Power Uprate From 3323 MWt to 3486 MWt (reference 3).Section 14.3 of the WNP-2 FSAR (Reference 4)describes the required testing for reactor power uprate.PPM 8.8.1, Reactor Power Uprate Test Sequence, documented the required power uprate testing which was performed in addition to the normal surveillance and routine testing required after a refueling outage.The procedure documented implementation and subsequent surveillance testing of required instrument setpoint changes for power uprate, RCIC system testing, steady-state core thermal limits data collection, and control system checks at the previous rated power level (954), 974 and near 100 percent rated power.
SUMMARY
OF TEST RESULTS All reactor power uprate tests were performed satisfactorily during the startup following refueling outage R-10.The tests are summarized below.RCIC SYSTEM A quick start of RCIC was performed at the new rated reactor pressure to verify the RCIC turbine did not trip on overspeed.
This test was performed using PPM 7.4.7.3.3B, RCIC Quarterly Operability Test.The acceptance criteria were met demonstrating adequate overspeed trip avoidance margin exists at uprated pressure.Since there were no changes made to the RCIC system controller settings as a result of reactor power uprate, control system testing was not required to be performed.
CORE POWER DISTRIBUTION AND CORE PERFORMANCE THERMAL LIMITS Core thermal limits were evaluated for reactor power uprate at approximately 88 percent, 95 percent, 98 percent and 100 percent uprated power.PPM 7.4.2.1, Power Distribution Limits, was used to evaluate the operating performance parameters before exceeding the previous power rating.The acceptance criteria were met.PPM 7.4.3.1.1.49, APRM and Core Thermal Power Channel Calibration Check, was performed to ensure each APRM channel was maintained within+2%of calculated thermal power (calculated by heat balance).PRESSURE REGULATOR Pressure regulator transient response was demonstrated at approximately 95 percent, 98 percent and 100 percent rated power using PPM 8.8.3, Pressure Regulator Step Changes.Pressure control setpoint changes of+4 psi,+8 psi and+10 psi were induced to evaluate pressure regulator transient performance.
The system response to these step changes was excellent and no system adjustments were required.There were no signs of oscillations.
The measured decay ratios were zero and no limit cycles were observed.Acceptance Criteria 1.The transient response of any pressure control system-related variable to any test input must not diverge.
J'1 1 2~Pressure control system-related variables'ay contain oscillatory modes of response.In these cases, the decay ratio for each controlled mode of response must be less than or equal to 0.25.3.The pressure response time from initiation of pressure setpoint change to the turbine inlet pressure peak shall be<10 seconds.4~Pressure control system deadband, delay, etc., shall be small enough that steady state limit cycles (if any)shall produce steam flow variations no larger than+0.5 percent of rated steam flow.5.The peak neutron flux and/or peak vessel pressure shall remain below the scram settings by 7.5 percent and 10 psi, respectively, for all pressure regulator transients.
The acceptance criteria were met.PPM 8.8.2, Pressure Regulator Linearity Demonstration, was performed during power ascension from 55 percent power to rated power.Steam flow, pressure regulator output and governor valve position data was collected at approximately two percent increments in power to verify the pressure control system linearity.
The data was used to calculate incremental regulation.
Acceptance Criteria The variation in incremental regulation (ratio of the maximum to the minimum value of the quantity,'"incremental change in pressure control signal/incremental change in steam flow" for each flow range)shall meet the following:
4 of Steam Flow Obtained With Valves Wide 0 en Maximum Variation 0 to 904 90 to 97%'0 to 994 4:1 2:1 5:1 The acceptance criteria were met.REACTOR WATER LEVEL SETPOINT CHANGES Reactor water level control system response was demonstrated at approximately 95 percent, 98 percent and 100 percent rated power using PPM 8.8.4, Reactor Water Level Setpoint Changes.Manual feedwater flow changes were made to induce+3 inch and+6 inch reactor water level changes.The transient response of the control system was evaluated.
The system response was very good and no system adjustments were required.Acceptance Criteria 1.The transient response of any Feedwater Level Control System related variable to any test input shall not diverge.2~Level control system related variables may contain oscillatory modes of response.In these cases, the decay ratio for each controlled mode of response shall be less than or equal to 0.25.The acceptance criteria were met.RECIRCULATION SYSTEM FLOW CALIBRATION Calibration of the installed recirculation system flow instrumentation was performed at near 100 percent power using PPM 9.3.11, Core Flow Determination and Instrument Calibration.
The acceptance criteria were met.FEEDWATER FLOW ELEMENT CALIBRATION ACCURACY Feedwater flow element calibration accuracy was evaluated using PPM 8.3.338, Rubidium Nitrate Tracer Test, following power uprate testing at.the uprated power level.The results of this testing indicated feedwater flow, and hence reactor power, was approximately 2.4 percent higher than indicated by plant instrumentation.
Feedwater flow instrumentation and the APRM's were adjusted to indicate 100 percent rated conditions after reactor power was reduced by 2.5 percent.Problem Evaluation Request (PER),295-1039 was written to document and resolve this issue.Subsequent sodium tracer and rubidium testing determined rated conditions may be 1.2 percent higher than determined by the first rubidium test.
e REFERENCES 1~2~3~FSAR Chapter 14, Section 14.2.12.3, Startup Test Procedures WNP-2 Power Uprate Project Startup Test Specification GE-NE-208-19-0993, Rev.1, July 1994.WNP-2 Licensing Submittal For Power Uprate From 3323 MWt to 3486 MWt With Extended Load Line Limit FSAR SCN 94-069, Section 14.3, Initial Testing For Power Uprate