ML20214P200
ML20214P200 | |
Person / Time | |
---|---|
Site: | River Bend ![]() |
Issue date: | 11/18/1986 |
From: | GULF STATES UTILITIES CO. |
To: | |
Shared Package | |
ML20214P198 | List: |
References | |
NUDOCS 8612040109 | |
Download: ML20214P200 (12) | |
Text
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GULF STATES UTILITIES COMPANY RIVER BEND STATION UNIT 1 STARTUP TEST REPORT (SUPPLEMENT 1) 30 OCTOBER 1986 8612040109Og000SB PDR ADOCK PDR P
.. . s STARTUP TEST REPORT (SUPPLEMENT 1)
- 1. The River Bend Unit 1 Startup Test Program officially was concluded on June 16, 1986. This Report contains an update on the status of the test exceptions which were open as of 15 July 1986 when the Gulf States Utilities Company River Bend Unit 1 Startup Test Report was written. Since 15 July 1986 forty-two (42) test exceptions have been closed, two (2) have been created as a result of retests and eighteen (18) remain open.
- 2. All open test exceptions are categorized as affecting level 2 criteria or lower. Any Level 1 criteria failures referenced in the report were promptly downgraded to Level 2 criteria as a result of appropriate engineering analysis and are considered Level 2 criteria in this report. This is consistent with the treatement of all test criteria referenced in the initial Startup Test Report. All open test exceptions were evaluated and cleared for continued full power operation.
l PAGE 2 OF 12 )
' s ST-1 CHEMISTRY AND RADIOCHEMISTRY
))! DESCRIPTION STATUS 13 HEPA pre-filter efficiency did not meet OPEN level 2 acceptance criteria. Existing radionuclides levels are insufficient to adequately measure filter efficiency.
A retest will be performed when radio-nuclides levels are higher.
16 Insufficient Radionuclides levels to de- OPEN termine off gas Pre and Post treatment monitor response versus release rate.
Repeat when off-gas activities are sufficient to establish trending. This test exception affects level 2 criteria.
These two (2) Level 2 test exceptions (TE-13 and TE-16) were evaluated as not impacting safe, full power operation.
ST-11 LPRM CALIBRATION TE DESCRIPTION STATUS 8 LPRM's 6B-38-15 and 2D-38-47 are in- CLOSED' operable and therefore were not calibrated. Repair and retest is part of Maintenance Work Request (MWR) 38043 and 38049. There is no test criteria associated with this test exception.
ST-13 PROCESS COMPUTER TE DESCRIPTION STATUS 4 Spacer /LPRM dips are not distinguishable CLOSED at low power level. Retest is now completed.
12 BOP calculations were not verified due to OPEN late software delivery. Calculations are 90% verified. Temperature calibration pro-blems were discovered as a result of BOP testing and are in the process of being corrected. Verification will be completed upon corrective maintenance on RTD calibra-tion problem. This Level 2 exception was evaluated as not impacting safe full power operation.
PAGE 3.OF_12_____ _ ._ _ _ . _ ._ _
,' o ST-14 RCIC SYSTEM TE DESCRIPTION STATUS 27 Track Technical Specification change for CLOSED high steamline flow isolation setpoint.
This change has been approved by the Facility Review Committee (FRC).
ST-22 PRESSURE REGULATOR TE DESCRIPTION STATUS 8 Exceeded level 2 criteria of Steam flow CLOSED variation for 0-60% steam flow. General Electric Engineering concluded that the steam flow variation was acceptable.
9 Pressure regulator testing for Test CLOSED Condition 3 was not performed with the recirculation system in Flux Control Mode.
All Flux Mode testing was deleted since the Flux Mode is not desired and will not be used at River Bend.
13 Pressure regulator testing for test CLOSED Condition 6 was not performed with the recirculation system in the Flux Control Mode. Flux Control Mode testing was deleted since Flux Control Mode will not be used.
14 Could not perform pressure regulator CLOSED failover during TC-4. General Electric Engineering concluded based on failover testing at other Test Conditions that existing failover testing was adequate.
15 Missing ERIS data for pressure regulator CLOSED "A" CV stepup. General Electric Engineer-ing concluded that the missing data was not required.
PAGE 4 OF 12 _ ___
.' o ST-22 PRESSURE REGULATOR (Cont'd) jgg DESCRIPTION STATUS 17 Could not determine incremental regula- CLOSED tion for regions of 85-97% and 85-99%
steamflow to satisfy level 2 criteria.
Retest completed.
18 Exceeded level 2 criteria of steamflow CLOSED variation for 60-100% steamflow.
General Electric Engineering concluded that the steamflow variation was acceptable.
21 An alternate steam header pressure measur- CLOSED ing point was used which was not called out in the procedure. The alternate point was acceptable.
22 Failed level 2 criteria for incremental OPEN regulation. General Electric is evaluating.
This exception has been determined not to impact full power operation.
ST-23A WATER LEVEL SETPOINT, MANUAL FEEDWATER FLOW CHANGES
))p DESCRIPTION STATUS 19 Flow transmitters were recalibrated. OPEN Function generator linearization data will be repeated. This Level 2 exception was evaluated as not impacting full power operation.
20 Response times of FWRV's exceed level 2 CLOSED criteria. General Electric Engineering has concluded that the existing response time is acceptable.
21 "B" FWRV exceeded settling time level 2 CLOSED criteria. General Electric Engineering has determined that existing settling time is acceptable.
22 Feedwater flow response exceeded level 2 CLOSED criteria. General Electric Engineering has determined that existing flow response is acceptable.
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? s ST-23A WATER LEVEL SETPOINT, MANUAL FEEDWATER FLOW CHANGES (Cont'd)
TE DESCRIPTION STATUS 25 Delay time of "A" FWRV exceeded level 2 CLOSED criteria. General Electric Engineering has determined that existing delay time is acceptable.
26 Response time of A FWRV exceeded level CLOSED 2 criteria, General Electric Engineering has determined that existing response time is acceptable.
27 Peak overshoot of A FWRV exceeded level CLOSED 2 criteria General Electric Engineering has determined that the test data is acceptable.
28 A FWRV settling time of 75.4 seconds ex- CLOSED ceeded level 2 criteria. General Electric Engineering has determined that the test data is acceptable.
29 Portions of single element testing at CLOSED test condition 6 was not performed. Based on similar test data at other test conditions General Electric Engineering has determined that the single element response is acceptable.
30 Final feedwater dynamic response verifica- CLOSED tion was not performed at test condition 6.
General Electric has determined that based on similar test data at other test conditions that the Feedwater dynamic response is acceptable.
31 Single element limit cycles make determina- CLOSED tion of decay ratio impractical. General Electric Engineering has determined that the single element control is accepta-ble.
PAGE 6 OF 12 ,
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ST-23D MAXIMUM FEEDWATER RUNOUT CAPABILITY TE DESCRIPTION STATUS 3 Level 2 criteria was exceeded in the 3 CLOSED pump /3 valve configuration when CNM-AOV119 failed to open. General Electric Engineer-ing has determined that the test results were acceptable.
ST-24 TURBINE VALVE SURVEILLANCE TE DESCRIPTION STATUS 3 Turbine valve surveillance at high power CLOSED level was not performed due to inoperable moisture separator / reheater. Since River Bend currently does not intend to per-form TCV surveillance testing above 85%
power this test exception has been closed.
ST-25C/D MAIN STEAM LINE FLOW INSTRUMENTATION TE DESCRIPTION STATUS 3 The elbow tap flow versus delta P curves OPEN are not within + 5% of the design curves.
The largest deviation is 32%. General Electric has evaluated this data and agreed that this exception does not impact full power operation. Investigation is continu-ing however, to determine the cause.
5 The flow venturi delta P as extrapo- CLOSED lated to 140% rated steam flow is 157 psid versus level 2 criteria of 178 psid.
Design documents have been changed and the Technical Specification has been approved by the FRC.
PAGE 7 OF 12 _ _ _ _ _ _ _
- s ST-29 RECIRCULATION FLOW CONTROL TE DESCRIPTION STATUS 4 Flux Loop and Flux Estimator testing was CLOSED not conducted in order to expedite testing.
Since this mode of operation will not be used, Flux Loop testing has been deleted.
10 The duty cycles for FCV "A" and "B" did CLOSED not satisfy the level 2 criteria of 0.2% Hz.
A retest is needed. This Test Exception was closed since it is a duplicate of TE-18.
17 Flux Loop and Flux Estimator testing was CLOSED not performed since this feature will not be utilized at River Bend. Flux Loop testing has been deleted (See ST-29 TE-4).
18 Duty cycle testing was not performed based OPEN on failure at similar test conditions at TC-3 (See TE-10). Based on General Electric San Jose recommendations position indicators were recalibrated and retest to be performed.
This exception was evaluated to have no im-pact on full power operation.
ST-30C RECIRCULATION SYSTEM PERFORMANCE TE DESCRIPTION STATUS 3 Flow control valve mismatch exists. Core OPEN flow and drive flow shortfall exist when considering individual flow control valve positions though total loop and core flows are satisfactory. This TE is under evaluation by General Electric Engineering.
This TE affects level 2 criteria. This ex-ception was evaluated to have no impact on full power operation.
PAGE 8 OF 12
,s
- s ST-74 OFF-GAS SYSTEM TE DESCRIPTION STATUS 1 Off-gas parameter outside level 2 liraits CLOSED for startup system.*
7 Off-gas parameters outside level 2 limits.* CLOSED 4 Two dryers, instead of one as specified, CLOSED were on-line during off-gas testing.*
5 Off-gas parameters outside level 2 limits.* CLOSED 9 Did not conduct Test Condition 3 testing CLOSED due to high flow.*
10 Off-gas system flow is greater than speci- CLOSED fied in test prerequisite.*
11 "A" dryer in Manual Control CLOSED 12 Off-gas parameters outside level 2 limits OPEN 13 "A" Hydrogen Analyzer Inoperable OPEN
- Test Exception 1,7,4,5,9,10 were due primarily to excess air flow and are duplicated by TE-12. Thus, these test exceptions have been closed and a retest will be performed by TE-12. It has been determined that these exceptions (TE-12, and TE-13) do not impact full power operation. Off-gas flow has been reduced to 40 cfm.
ST-94 LOOSE PARTS MONITORING SYSTEM TIj DESCRIPTION STATUS 2 LPM Channel 2 was inoperable. Retake data CLOSED for LPM Channel 2 at each test condition.
Retest completed.
3 LPM printer is inoperable. Test data CLOSED obtained manually and was acceptable.
PAGE 9 OF 12 _
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s ST-95 EMERGENCY RESPONSE INFORMATION SYSTEM TE DESCRIPTION STATUS 3 Module SD-10 failed. This Level 2 excep- OPEN tion does not impact full power operation.
4 RPV temperature validation at cold CLOSED shutdown not performed. Retest completed.
5 Core flow constants not recalculated. CLOSED Retest completed.
6 RPV level validation at cold shutdown CLOSED not performed. Retest completed.
7 Core flow validation at cold shutdown CLOSED not performed. Retest completed.
8 Core flow validation not performed after CLOSED core flow constant recalculation. Retest completed.
ST-100 PIPING VIBRATION TE DESCRIPTION STATUS 15 ERIS Drywell panel 107 was failed during OPEN 100% power steady state vibration test.
Open for retest.
16 Vibration data for MSS points T42 and OPEN T220 was not available due to failure of ERIS data collection Panel 107. Panel to be repaired and points retested.
19 During Feedwater pump trip test (ST-23C) OPEN points T144 X & Y failed Level 1 criteria.
T-144Z failed level 2 and data for T-35 was unavailable due to failed ERIS panel 107.
Open pending repair of panel 107 and retest.
PAGE 10 OF 12
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- s ST-100 PIPING VIBRATION (Cont'd)
TE DESCRIPTION STATUS 20 During generator load rejection (ST-27) OPEN points MSS T-42Z, T-235 X, Y, & Z, FWS T-144X, failed Level l criteria. MSS T-42X and FWS T-144Y and Z failed Level 2 criteria. No data was available for conden-sate test point T/S-525 since AOV-119 failed to open. The test data was reviewed and found acceptable for continued power operation (downgraded to Level 2) by S&W/NuPE. This TE is open pending retest.
21 Test points MSS T-220, FWS T-39, SVV T-39 OPEN and T-85 were not operable during genera-tor load rejection. Open for retest.
ST-100, TE-15, 16, 19, 20 and 21 require that ERIS Panel 107 be operable. Failure of the panel resulted in the inability to collect data. The panel will be repaired and retesting performed. Engineering analysis was performed on these test exceptions utilizing actual vibration / expansion measurements recorded at previous test conditions and existing stress analysis, where appropriate. The engineers concluded that all Level I criteria violations could be downgraded to Level 2 and these open exceptions did not impact continued operation at full power.
ST-101 BOP PIPING THERMAL EXPANSION DESCRIPTION STATUS
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29 Rated Feedwater expansion data, per TE-20, CLOSED was unsatisfactory for test points E-35, E-50 and E-941 due to a inoperable ERIS drywell panel. ERIS panel was repaired and test points were retested.
37 During retest of Reactor Water Cleanup per OPEN TE-21, WCS test point E-56X failed Level 1 and WCS snubber PSSP-3013-Al failed Level 2 criteria. Retest is required.
PAGE 11 OF 12
,. .. i ST-101 BOP PIPING THERMAL EXPANSION (Cont'd)
This test exception was evaluated by engineering utilizing existing stress calculations. It was concluded that the Level l criteria could be downgraded to Level 2 and that the TE-37 violations did not impact full power operation.
ST-104 ESF AREA COOLING TE DESCRIPTION STATUS 2 Measured ESF room temperatures in the OPEN HPCS, RCIC, RHR A, RHR B, RHR C exceed
-Level 3 criteria of 90 degrees F. I Evaluation being performed by General Electric Engineering.
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