PY-CEI-NRR-0706, Startup Rept,Supplemental - 2
| ML20237H344 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/27/1987 |
| From: | Cantlin J, Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| PY-CEI-NRR-0706, PY-CEI-NRR-706, NUDOCS 8709030217 | |
| Download: ML20237H344 (133) | |
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STARTUP REPORT Supplemental - 2 1
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f PERRY NUCLEAR POWER PLANT UNIT 1
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The Cleveland Electric Illuminating Compang Perry Nuclear Power Plant Unit 1
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'Date liteurwK t/v/r7 Senior VicE President Nuclear Group Date
PORWARD This Supplemental Startup Report (Supplemental-2) for the Perry Nuclear Power Plant, Unit 1, covers the period from May 16, 1987 to June 27, 1987, and is submitted as required by Regulatory Guide 1.16 and Perry Technical Specifications Section 6.9.
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TABLE OF CONTENTS Title Page SECTION 1 - DESCRIPTION 1.1 Introduction 2
SECTION 2 -
SUMMARY
2.1 Summary of Testing Since May 16, 1987 4
2.2 Startup Test Program Chronology 5
SECTION 3 - STARTUP TEST INSTRUCTIONS 3.1 Startup Test Instruction Abstracts 8
SECTION 4 - STARTUP TEST RESULTS 4.1 P35-001 Chemical and Radiochemical 10 4.2 D21-002 Radiation Measurements 12 4.3 C51-011 LPRM Calibration 13 4.4 C51-012 APRM Calibration 14 4.5 C91-013 Process Computer 17 4.6 E51-014 Reactor Core Isolation Cooling 29 4.7 B21-016A Selected Process Temperatures 38 4.8 C91-019 Core Performance 40 4.9 C85-022 Pressure Regulator System 44 4.10 N27-023A Feedvater Control System 49 4.11 N27-023D Maximum Feedvater Runout 56 Capability 4.12 B?l-025A MSIV Function Test 56 4.13 B21-027 Turbine Trip and Generator Load 58 Rejection 4.14 B33-029A Recirculation Flow Control-Valve 62 Position Loop 4.15 B33-029B Recirculation Flow Control 67 4.16 B33-030A One Recirculation Pump Trip and 78 Restart 4.17 B33-030B RPT Trip of Two Pumps 83 4.18 B33-030C Recirculation System Performance 86 4.19 B33-030E Recirculation System Cavitation 88 4.20 B21-033/P99-122 Dryvell Piping Vibration /B0P 90 Piping Expansion and Vibration 4.21 F41-034 Reactor Internals Vibration 93 4.22 B33-035 Recirculation System Flov 95 Calibration 4.23 G33-070 Reactor Vater Cleanup System 98 11
4 TABLE OP CONTENTS Tit 1e Page SECTION 4 - STARTUP TEST RESULTS (CONT.)
4.24 C95-099 ERIS (Emergency Response and 100 Information System) 4.25 P42-114 Emergency Closed Cooling System 104 4.26 T23-123 concrete Temperature Survey 105 4.27 N22-126 Main, Reheat, Extraction and 106 Miscellaneous Drains 4.28 N33-129 Steam Seal 108 4.29 R63-133 Loose Parts Monitoring System 109 SECTION 5 - ATTACHMENTS Startup Test Performance Index 112 111
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SECTION 1
,r DESCRIPTION l
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1.1 INTRODUCTION
This report consists of a summary of the Startup Test Program performed at Unit 1 of the Perry Nuclear Power Plant. This Supplemental-2 report covers the period May 16, 1987 to June 27, 1987. During this period, all testing for Test Conditions 3, 4, and 5 was completed.
Since the Startup Test Program is still in progress, Supplemental Startup Reports will be submitted at least every three months until the program is completed.
Previous Startup Report submittals are listed below:
Report Period Covered Initial Startup Report June 6, 1986 to March 1, 1987 Supplemental-1 March 1, 1987 to May 15, 1987 l
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SUMMARY
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2.1
SUMMARY
OF TESTING SINCE MAY 16, 1987 Since the submittal of the Supplemental-1 Startup Report which covered up to May 15, 1987, the following significant activities have been successfully completed within the scope of the Startup Test Program:
1)
Test Condition 3 was completed.
2)
Test Condition 5 was completed.
3)
Test Condition 4 was completed.
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l 2.2 STARTUP TESTING PROGRAM CHRONOLOGY j
5-15-87 Achieved criticality and entered Test Condition 3 Plateau.
Testing began the next day with the RCIC Cold Quick Start test and proceeded with a power increase to the 60% load line. Recirculation System performance and Reactor Internals Vibration data was collected at various points during the ramp up in power via flow.
5-20-87 A core flow calibration was performed which confirmed preliminary indications that a core flow shortfall was present. This caused a multiplier of 0.8 to be entered into the APRH flow biased trip circuitry to ensure conservative response of the APRMs rod blocks and scram setpoints while core flow data was being evaluated.
5-24-87 A manual SCRAM (87-07) was initiated due to the failure of a Feedvater drain line.
5-27-87 After returning to power on 5-25-87, testing continued until an automatic SCRAM (87-08) occurred due to a failed flow controller for the Motor Feed Pump which resulted in a low reactor vater level. After repairs, the plant returned to power later that same day.
Startup testing and tuneups were f
performed that included Feedvater, Reactor Recirculation, Loose Parts Monitoring, Process Computer, ERIS, and others.
i 6-01-87 Began TC 3 Feedvater Level Controller System tuneups.
i 6-05-87 Power was reduced to below 40% to alleviate a high reactor vater conductivity condition.
Once conductivity was restored to allovable values, a slow ramp was initiated to collect Recirculation System data. The high conductivity was appar-ently caused by the release of organic preservative from the moisture separator / reheaters, steam piping, and main turbine.
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STARTUP TESTING PROGRAM CHRONOLOGY (CONT.)
6-08-87 Completed tuneup of the Feedvater Level Controller System and began tuneup of the Recirculation Flow Control System.
6-13-87 &
IN21-F230, Hot Surge Tank Level Control valve, failed closed 6-15-87 twice and rapid power reductions were required to prevent scrams. This problem was caused by excessive flow induced vibration. Corrective action included the relocation of the valve positioner and installation of a parallel backup valve.
6-17-87 An automatic SCRAM (87-09) occurred due to closure of the outboard MSIVs caused by a loss of the
'A' RPS bus. Testing i
I in TC 3 was completed and the plant placed in Cold Shutdown for maintenance.
6-22-87 The plant' returned to operation in TC 5.
TC 5 had an upper bound of the 100% load line and between the minimum flov vith the recirculation pumps in high speed to.5% above the analytical lover limit of the autbmatic flov' control range.
6-26-87 Test Condition 5 was completed and TC 4 (Natural Circulation) entered. During natural circulation conditions, no evidence of instabilities was observed.
6-27-87 Test Condition 4 was completed and TC 6 started.
6-30 Plant Manual SCRAM (87-10) due to a Main Generator Hydrogen cooling leak. Commenced outage for implementing design changes and maintenance.
This ends the events covered by this supplement.
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SECTION 3 STARTUP TEST INSTRUCTIONS 4
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3.l' STARTUP TEST INSTRUCTION CHANGES General Electric has performed an evaluation of the scheduled tests for the Perry Nuclear Power Plant (PNPP). Based on a review of testing q
performed at other BVR's, a modest program of test reduction or 1
simplification was generated.
i Through the Field Deviation Disposition Request (FDDR) program, several planned tests were altered or deleted. The impact to the Startup. Test l
Program was evaluated by PNPP Startup Test personnel and Startup Test Instructions (STI) were revised or amended as deemed appropriate. The required 10CFR50.59 Applicability Checks were completed and, where iden-tified'as'necessary, Safety Evaluations were performed. There vas no instance of an unreviewed safety question.
In general, the test changes were relatively minor and consisted of reducing the variety.of plant conditions in which' selected tests were performed.
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a SECTION 4 STARTUP TEST RESULTS l
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STARTUP TEST RESULTS 4.1 STI-P35-001 Chemical and Radiochemical (TSN-251, 297)
This test verifies that Chemical and Radiochemical parameters of the Reactor Coolant and selected support systems meet acceptable limits. The test also determines, using approved plant procedures, the adequacy of sampling equipment and analytical procedures / techniques for sampling.
Additional objectives for this test are to evaluate fuel performance, evaluate demineralized integrity, and measurement and calibratica of the Off-Gas System and certain process instrumentation.
During Test Conditions 3 and 5, samples were obtained from Reactor Vater Cleanup, Feedvater, CRD Vater, and Off-Gas. Analyzed results are tabulated below.
Acceptance Criteria Level 1 1.
Chemical factors defined in the Technical Specifications and fuel varranty must be maintained within the limits specified.
2.
The activity of gaseous and liquid effluents must conform to license limitations.
3.
Vater quality must be know at all times and must remain within the guidelines of the Vater Quality Specifications.
Results l
Results
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RVCU Influent TC 3/TC 5 Criteria Conductivity (pmho/cm @ 25'C) 0.225/0.280 f 1.0 a.
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Chloride (ppm)
<0.010/0.0045 f 0.2 10
STARTUP TEST RESULTS (CONT.)
i STI-P35-001 (Cont.)
Results
- 1, RVCU Influent (Cont.)
TC 3/TC 5 Criteria I
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pH (@ 25'C) 7.9/7.9 5.6 to 8.6 d.
Boron (ppm)
<1.0/<1.0 f 5.0 e.
Silica (ppm) 0.25/0.12 f 5.0 l
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Feedwater a.
Conductivity (umho/cm @ 25'C) 0.061/0.056 50.1 b.
pH (@ 25'C) 6.9/6.9 5.7 to 7.5 c.
Metallic Impurities (ppm) 0.0014/0.0018 f 0.015 d.
Cu Impurity (ppm) 0.0001/0.0001 f.002 e.
Oxygen (ppm) 0.046/0.024 0.02 to 0.2 3.
CRD Vater a.
Conductivity (umho/cm 0 25'C) 0.067/0.068 f 0.1 b.
Oxygen (ppm) 0.03/0.039 5 0.05 4.
Condensate a.
Conductivity (pmho/cm @ 25'C) 0.07/0.064 N/A b.
Chloride (ppm)
<0.010/<0.0010 N/A c.
Suspended Iron Oxide (ppm) 0.01/0.050 N/A 11
l STARTUP TEST RESULTS (CONT.)
STI-P35-001 (Cont.)
Results
- TC 3/TC 5 Criteria 5.
Off-Gas s.
Pre-Treatment (uci/sec) 20.5/30.5
$3.58E5 b.
Off-Gas Vent (pci/sec)
< limits /< limits
- None
- 0ff-Gas Vent activity is converted to dose to the body in accordance with Technical Specifications.
All data collected satisfied the criteria of this test.
l 4.2 STI-D21-002 Radiation Measurements (TSN-233)
The purpose of this test is to perform a general survey of the plant to determine radiation levels.
In Test Condition 3, the test uas performed at approximately 63% power.
Acceptance Criteria Level 1 The radiation doses of plant origin and the occupancy times of personnel in radiation zones shall be controlled consistent with the guidelines of the standards for protection against radiation as outlined in 10CFR20,
" Standards for Protection Against Radiation."
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i' STARTUP TEST RESULTS (CONT.)
STI-D21-002 (Cont.)
Results After achieving 63% Reactor Power during Test Condition 3, a set of radiation measurements were conducted throughout the plant. The performance of this test was the fifth of six scheduled performances during.the Power Ascension Program.
Health Physics obtained gamma readings at all locations and neutron readings at various survey points. The 203 posted radiction survey points were monitored during this test.
'The radiation surveys required a total of approximately 40 Health Physics manhours to complete. All test results were satisfactory. All areas measured vere less than or equal to 0.5 mrem /hr gamma and less than or equal to 1.0 mrem /hr neutrun with the exception of the Reactor Vater Cleanup Rooms A and B (26.0 and 1.0 mrem /hr, B pump tagged out for repair), the Reactor Sample Station area (0.6 mrem /hr), the RCIC pump room (6.0 mrem /hr) and the Turbine Building exhaust plenum (11.0 mrem /hr).
Results of the radiation survey were compared with the maximum radiation exposures described in FSAR Figures 12.3-1 through 12.3-8.
In all cases
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the measured values vere vel) below the FSAR maximum values.
4.3 STI-C51-011 LPRM Calibration (TSN-221)
This test calibrated the LPRM's using the Process Computer.
Acceptance Criteria Level 2 Each LPRM reading vill be within 10% of its calculated value.
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i STARTUP TEST RESULTS (CONT.)
STI-C51-011 (Cont.)
Results A LPRM calibration was performed using Surveillance Instruction SVI-C51-T5351, via Process Computer program OD-1.
The LPRM Gain Adjustment Factors (GAP's) calculated by OD-1 vere then used to adjust th'e LPRM amplifier gains to yield calibrated LPRM readings. Five LPRMs were not.
calibrated due to their inoperability. Four of these LPRMs are inoperable due to failed sensors (LPRMs32-57A, 32-49A,32-25A and 08-41A). The failure of these 4 LPRMs was previously addressed by Test Exception Report 107-1. The fifth_LPRM (24-33C) was inoperable due to spiking during the performance of this test. Work Order 87-3237 corrected the spiking and l
the LPRM has been returned to service. All other LPRMs satisfied the Acceptance Criteria.
4.4 STI-C51-012 APRM Calibration (TSN-222, 301).
This test was performed to adjust the APRM gains using the Process Computer program, OD-3, to obtain'a heat balance.
Acceptance Criteria-Level 1
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The APRM channels must be calibrated to read equal to or greater than the actual core thermal power.
2.
Technical Specification and fuel varranty limits on APRM scram and Rod Block Setpoint shall not be exceeded.
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I STI-C51-012 (Cont.)
i Level 2 If the Level I criteria are satisfied, then the APRM channels vill be con-sidered to be reading accurately if they agree with the heat balance or the value required by Technical Specifications to within 1 % of rated 2
power.
Results 1.
TC3 Performance (TSN-222)
Core thermal power was determined to be 71.64% of rated, using the Process Computer OD-3 program, and the APRM gains were adjusted to be consistent with the heat balance. The STI was successfully completed with the "as-left" APRM readings verified to be within the Acceptance I
Criteria of +2, -0% of rated thermal power.
APRM Readings (First Performance)
APRM As-Found Desired
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72.0 71.64 72.0 i
B 69.5 71.64 72.0 C
72.5 71.64 72.5 D
72.0 71.64 72.0 E
69.5 71.64 72.0 F
69.0 71.64 72.0 G
73.0 71.64 73.0 H
69.0 71.64 72.0 l
- Desired APRM readings to be greater than or equal to actual Core l
Thermal Power l
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STARTUP TEST RESULTS (CONT.)
STI-C51-012 (Cont.)
A review of the most recent performances of SVI-C51-T0027 (A-H) l demonstrated that APRM scram and Rod Block Setpoint were consistent vith Technical Specifications.
2.
TC 5 Performance (TSN-301)
The APRMs vere adjusted twice using SVI-C51-T0024. As the first adjustment did not meet all criteria, a second adjustment was required and successfully completed.
For the second adjustment, core thermal power was determined, using the Process Computer OD-3 program, to be 76.7% of rated. The APRM readings were compared to j
actual core power. The APRM amplifier gains were adjusted to read consistent with the Acceptance Criteria.
APRM Readings (Second Performance)
APRM As-Found Desired
- As-Left A
75.5 76.7 77.0 B
75.0 76.7 77.5 C
76.5 76.7 78.0 D
76.0 76.7 78.0 E
75.0 76.7 77.5 F
76.5 76.7 77.5 G
76.0 76.7 77.0 H
76.5 76.7 78.0 APRM readings to be greater than or equal to actual Core
- Desired
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Thermal Power A review of the most recent performances of SVI-C51-T0027 (A-H) demonstrated that APRM scram and Rod Block Setpoint vere consistent with Technical Specifications.
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STARTUP TEST RESULTS (CONT.)
_4.5 STI-C91-013 Process Computer (TSN-223, 224, 225 226, 227, 228, 229, 230, 231, 305)
DSTC - Plant Sensor Checks /8.7 (TSN-223, 305)
The purpose of this test was to verify correct operation of process com-puter programs OD-3 (Core Thermal Power and APRM Calibration), OD-7 (Present Control Rod Positions), and OD-8 (Present LPRM Readings). The OD-3 Core Thermal Power Determination was verified to be within 2% of a manual heat balance caleulated at the same plant power level. Other plant variables edited by UD-3 vere verified to be reflecting plant operating conditions based on a review of control room indicators. OD-7 Control Rod Positions were determined to be in agreement with those shown on the RC&IS display. Pinally, the OD-8 LPRM Readings were verified against those of the meters on the Control Room back panels. This test was performed.in both TC 3 and TC 5.
Acceptance Criteria There are no Acceptance Criteria applicable to this section of this test.
Results The results of the heat balance computations, manual vs.
computer-generated, were as follows:
TC 3 TC 5 Core power, manual heat balance 2561.1 MVt 2680.6 MVt Core power, OD-3 2555.3 HVt 2690.9 MVt Percent difference
-0.23%
0.38%
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STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
4 In addition, comparison of the OD-7 control' rod positions with RC&IS indicationsrevealednodiscrepancies,andtheOD-8ed$tedLPRMreadings with those of the Control Room showed only expected minor differences attributable to noise and momentary fluctuations.
l At the beginning of these tests, the computer was reinitialized, and using the DSPLNK program, it was verified that LPRMs and other NSSS data points were being scanned every 5 seconds. The one-minute averaging routine was also verified to be functioning correctly for the feedvater flow: signals.
Next, it was verified there were no failed sensors appearing on the OD-3 edit and in the CT array (scanned plant data at time of last P1).
o Then, OD-3 core thermal power was verified to.be within 0.23% and'0.38%
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~(for TC 3 and TC 5 respectively) of the reactor power level determined'by a manual heat balance. During TC 3, the VDC vs. VTC correlation was not verified initially because Perry specific core flov vs. drive flow curve was not available. When a correlation was later developed and inputted, this part of the test was reperformed satisfactorily under TSN-280. This L
correlation also verified satisfactorily during TC 5.
The manually _
calculated APRM gain adjustment factors (AGAF) and the APRM calibration constants (CAP) vere also shown to be approximately equal to the computer-generated values, any differences being attribu'ted to normal APRM signal fluctuations.
InadditiontotheverificationoftheOD-7andOD-8editswithindepen) dent plant instrumentation, tne respective edits requested from the I
Honeywell 4400 (process computer) and the VAX (minicomputer) were shovns to be identical in the case of OD-7 and substant: ally' equivalent (due to the i
aforementioned statistical variations in LPRM signals) in the case of OD-8.
No problems with either the computer hardware or softvare vere noted in the course of these tests.
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STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
DSTC - Power Distribution and Thermal Lf ':.,J.10 (TSN-224)
The purpose'of this test was the validation of process computer program P1 (Periodic Core Evaluation). Thermal limits (and their core locations) and LPRM calibration constants determined by P1 vere in agreement with the values calculated by the off-line computer program BUCLE. The F1 software-performed according to its specifications, and.all Acceptance Criteria vere' satisfied.
Acceptance Criteria Level 1 None Level.2 Programs OD-1, P1 and OD-6 vil) be considered operational when:
1.
The MCPR calculated by BUCLE and the process computer either a.
Are in the same fuel assembly and do not differ in value by more than 2%, or b.
For the case in which the MCPR calculated by the process-computer is in a different assembly than that calculeted by BUCLE, for each assembly, the MCPR and CPR calculated by the two methods shall agree within 2%.
'2.
The maximum LHGR calculated by BUCLE and the process computer either:
a.
Are in the same fuel assembly and do not differ in value by more than 2%, or l-19 ww=_1_______...__._____
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STARTUP TEST RESULTS (CONT.)
1 STI-C91-013 (Cont.)
b.
For the case in which the maximum LHGR calculated by the process computer is in a different assembly than that calculated by BUCLE, for each assembly, the maximum LHGR and LHGR calculated by the two methods shall agree within 2%.
3.
The MAPLHGR calculated by BUCLE and the process computer either, a.
Are in the same fuel assembly and do not differ in value by more than 2%, or b.
For the case in which the MAPLHGR calculated by the process computer is in a different assembly than that calculated by BUCLE, for each assembly, the MAPLHGR and APLHGR calculated by the two methods shall agree within 2%.
4.
The LPRM calibration factors calculated by BUCLE and the process computer agree to within 2%.
Results The following tables present the principal results of this test. In each case, the four most limiting bundles / core locations are shown because l
although the thermal limits are the same (due to core symmetry), the computer codes P1 and BUCLE order these bundles / locations differently.
1 NOTE:
The results of three different comparisons performed during this test are presented.
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PC BUCLE Comparison Location MCPR Location MCPR
% Difference 8.10.9 vs. 8.10.15 37-52 1.910 37-52 1.911
.1%
37-10 1.910 37-10 1.911
.1%
23-10 1.911 23-10 1.911 0%
23-52 1.911 23-52 1.911 0%
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STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
PC BUCLE Comparison Location HCPR Location MCPR
% Difference 8.10.18 vs. manually 37-52 1.939 37-52 1.941
.1%
inputted 8.10.18 37-10 1.939 37-10 1.941
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BUCLE 23-10 1.939 23-10 1.941
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23-52 1.939 23-52 1.941
.1%
8.10.23 vs.
37-52 1.889 37-52 1.889 0%
8.10.23 BUCLE 37-10 1.889 37-10 1.889 0%
23-10 1.889 23-10 1.889 0%
23-52 1.889 23-52 1.889 0%
LHGR LHGR 8.10.9 vs. 8.10.15 45-14-15 8.94 45-14-15 8.94 0%
15-14-15 8.94 15-14-15 8.94 0%
15-48-15 8.94 15-48-15 8.94 0%
45-48-15 8.94 45-48-15 8.94 0%
8.10.18 vs. manually 45-14-15 8.86 45-14-15 8.83 0.3%
inputted 8.10.18 15-14-15 8.86 15-14-15 8.83 0.3%
DUCLE 15-48-15 8.86 15-48-15 8.83 0.3%
45-48-15 8.86 45-48-15 8.83 0.3%
MAPLHGR MAPLHG1; 8.10.23 vs.
45-14-15 8.94 45-14-15 8.92 0.2%
8.10.23 BUCLE 15-14-15 8.94 15-14-15 8.92 0.2%
15-48-15 8.94 15-48-15 8.92 0.2%
45-48-15 8.94 45-48-15 8.92 0.2%
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STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
PC BUCLE Comparison Location MAPLHGR Location MAPLHGR
% Difference 8.10.9 vs. 8.10.15 45-14-15 7.98 45-14-15 7.98 0%
15-14-15 7.98 15-14-15 7.98 0%
15-48-15 7.98 15-48-15 7.98 0%
45-48-15 7.98 45-48-15 7.98 0%
8.10.18 vs. manually 45-14-15 7.91 45-14-15 7.88 0.4%
inputted 8.10.18 15-14-15 7.91 15-14-15 7.88 0.4%
BUCLE 15-48-15 7.91 15-48-15 7.88 0.4%
45-48-15 7.91 45-48-15 7.88 0.4%
8.10.23 vs.
45-14-15 7.98 45-14-15 7.97 0.1%
8.10.23 BUCLE 15-14-15 7.98 15-14-15 7.97 0.1%
15-48-15 7.98 15-48-15 7.97 0.1%
45-43-15 7.98 45-48-15 7.97 0.1%
In addition, the LPRM calibration factors, C, as calculated by P1 and BUCLE vere equal at each respective LPRM location.
The first phase of this test was to demand P1 (Periodic Core Evaluation).
Since P1 zeros out the hourly accumulations of core thermal and plant electrical energies, a techeck of program P4 was performed comparing numbers of approximately the same magnitude, i.e., the 10-minute increments are only about 25-33% of the accumulated energy at the time of the test. No prablems were noted with the P4 program.
Next, verifications of power and flow distributions, thermal limits, LPRM gain adjustment factors, and LPRM alarm trip settings were performed.
Programs OD-6 (Thermal Data in a Specified /uel Bundle), OD-9 (Axial Interpolation Data), and OD-16 (Target Exposure and Power Data) were performed for the purposes of comparison with the quantities edited by P1 and the performance of selected manual calculations, i.e.,
RC (LPRM substitute values), and ER (LPRM effective readings).
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STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
The program OD-10 (List / Alter NSS Data Files) vas used to edit a number of arrays to check against the OD-6 and OD-9 edits and for comparison with manually calculated data, e.g., DRLP (differences at LPRM elevations) and-ATSP (presently applied alarm trip setpoints).
The off-line version of P1 (BUCLE) resident on the General Electric Mark III computer was used to generate an independent P1 edit. The high-speed (4800-baud) link from the on-site VAX (process computer) to the Mark III was employed to transfer the required data files to permit BUCLE to run.
A check of P1 exposure accumulation and void fraction determination was made (via manual calculations) on the variables: CICEX (total LPRM exposure), DICEX (daily LPRM exposure), CREX (control rod exposures), EXF (fuel exposure), EXVF (exposure-veighted void fraction), and VF (fuel void fraction). No problems were noted in P1 exposure updating.
Finally, P1 was demanded again and steps involving the OD-6, OD-9, and OD-16 comparison, BUCLE run, and exposure updating were repeated to note the effects of incrementing exposure.
No software problems were noted in the perfctmance of this test and all applicable test criteria were met.
This completed the second P1 verification..
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DSTC - 21' Symmetry Check /8.14 (TSN-225)
The purpose of this test is to verify the validity of P1 computations using symmetry provisions (i.e., reactor flux is actually symmetric).
This test was performed by first running a P1 vith the symmetry flag set to ' mirror' then editing bundle power data via OD-10.
Then with core power unchanged, a second P1 was run with the symmetry flag set for an asymmetric calculation and again bundle power data was edited via OD-10.
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STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
Finally, the two bundle power edits were compared to verify that the actual power distribution was equivalent to a mirror symmetric calculated power distribution.
Acceptance Criteria ~
There are no Acceptance Criteria applicable to this section of this test.
Results The comparison of'the symmetric calculation results with the non-symmetric assumption calculation results shoved that core power was symmetrically distributed and consistent between methods. No problems with either the process. computer hardware or software were noted in this test.
DSTC - OD-12 Verification /8.15 (TSN-226)
The purpose of this test is to validate on demand program OD-12, Isotopic Composition of Incore Fuel. This' test was performed by demanding OD-12,
.the last P2 log (via OD-17 option 2), and an edit of EBUN (via OD-10).
The OD-12 data was checked for correct core fuel locations,-approximate expected fuel bundle burnups-(individually and core vide) and overall reasonableness.
Acceptance Criteria i
Level 1 None Level 2 l
Having undergone successful completion of static and dynamic testing, program OD-12 is considered operational.
24
.. O
STARTUP TEST RESULTS- (CONT. )
STI-C91-013 (Cont.)
Results Results of the OD-12 data which were checked showed that the fuel was located in the correct core locations, fuel bundle burnups both indivi-dually and core vide were reasonable, and the isotopic composition'of the fuel bundles showed an expected distribution for fuel with a small exposure. No problems with either the process computer hardware or software vere noted in this test.
DSTC - Computer Initialization Check on P1/0D Phase I/8.16 (TSN-227)
The purpose of this test is to verify that OD-15, Computer Shutdown and Outage Recovery Monitor, properly updates exposure data during computer outages (short term).
This test was performed by collecting current exposure data for control rod exposure, LPRM exposure and fuel exposure-voids. Then the computer was disabled for 5 minutes, restarted, OD-15 was run, P1 was demanded, and exposure data was collected again.
Acceptance Criteria There are no Acceptance Criteria applicable to this section of this test.
Results l
Comparison of both sets of exposure data generated during performance of this test found that they were approximately equal and that OD-15 properly maintained exposure data during a short computer outage.
No problems with either the process computer hardware or software were noted in this test.
25
STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
DSTC - Computer Initialization Check on P1/0D Phase II/8.17 (TSN-228)
The purpose of this test is to verify that OD-15, Computer Shutdown and Outage Recovery Monitor, properly updates exposure data during computer outages (long term).
This test was performed by collecting current exposure data for control j
rod exposure, LPRM exposure and fuel exposure-voids. Then'the computer was disabled, restarted with approximately day old P1 data (from temp.
save' file), OD-15'vas run, P1 was demanded and then exposure data for this update was collected.
Acceptance Criteria There are no Acceptance Criteria applicable to this section of this test.
Results Comparison of current exposure data with day old exposure data updated by OD-15 found both sets were approximately equal, which indicated OD-15 operated properly.
No problems with either the process computer hardware or software vere noted in this test.
I DSTC - Verification of Validity of BLIP Correlation /8.19 (TSN-229)
The purpose of this test is to verify the validity of the BLIPP correlations, i.e., to verify the base distribution from the last OD-1 (OD-2) is properly corrected for rod motion. This test was performed by moving a control rod which had not been moved since the last OD-1 (0D-2).
Then a sequence of P1, OD-9 for an LPRM string nearest the control rod moved, OD-10 for BLPP and BLIPP for the same LPRH string, OD-2 for the 26 1
1
STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
same string, a second P1 and OD-9 for the same LPRM string vere demanded.
l Then the first OD-9 was compared with the second OD-9 to verify the BLIPP correction was reseroed after OD-2 and P1 vere run. This sequence was completed for three different control rod movements (2, 4, and 6 notch l
movements).
Acceptance Criteria There are no Acceptance Criteria applicable to this section of this test.
Results Control Rod 06-23 was pulled from position 42 to 46, control rod 14-15 was pulled from position 24 to 32, and control rod 30-07 vas pulled from position 24 to 36.
In all cases, the base distributions were properly compensated and the BLIPP correlation functioned properly.
No problems with either the process computer hardware or software were noted in this test.
DSTC - Simultaneous P1/0D-2 Check /8.20 (TSN-230)
The purpose of this test is to verify no interactions during simultaneous OD-2's and P1's(i.e., no count errors or malfunctions). This test was performed by running 2 consecutive OD-2's in parallel with 4 P1's.
Acceptance Criteria There are no Acceptance Criteria applicable to this section of this test.
Results During performance of this test no interactions, count errors or 1
malfunctions occurred.
27
STARTUP TEST RESULTS (CONT.)
STI-C91-013 (Cont.)
No problems with either the process computer hardware or software were noted in this test.
DSTC - P5 Testing (TSN-231)
The purpose of this test is to verify operability of Periodic Program PS, Drifting LPRM Diagnostic. This test was performed in three parts:1) verify that LPRM digital filtering properly initialized, 2) verify that LPRM digital filtering properly averages and resets baseline values, 4
and 3) verify LPRM Drift Diagnostics properly identifies drifting LPRM's.
Acceptance Criteria Having undergone successful completion of static and dynamic testing, programs PS and OD-14 are considered operational.
Results This test demonstrated that digital filtering was properly initiated for control rod movement (control rod 30-55 was moved) and when generator megavatts varied by 0.2% (normally set at 1% when not being tested). This test also showed that digital filtering operated properly by changing a RPAVG value to 1.0 then watching it return to its original value as filtering is initiated. Finally, the drift diagnostics were verified by setting the drift threshold value to -0.1 and verifying all the LPRMs drifted.
In summary, all features of P5 operated properly.
This test was also the culmination of many tests, each verifying various options of OD-14 by producing the required performance or expected results.
i No problems with either the process computer hardware or software vere noted in this test.
i 28
)
1 STARTUP TEST RESULTS (CONT.)
I 4.6 STI-E51-014 Reactor Core Isolation Cooling (RCIC) 1 (TSN-212, 234, i
294, 290)
The purpose of this test is to verify the proper operation of the RCIC system over its expected operating range and demonstrate reliability in starting from cold standby when the reactor is at power.
Acceptance Criteria Level 1 1.
The average pump discharge flow must be equal to or greater than the 100% rated value after 30 seconds have elapsed from automatic initiation (or manual push button start) at any reactor pressure between 150 psig and rated.
2.
The RCIC turbine shall not trip or isolate during auto or manual start tests.
Level 2 1.
In order to provide an overspeed and isolation trip avoidance margin, the transient start first and subsequent speed peaks shall not exceed 5% above the rated RCIC turbine speed.
2.
The speed and flow control loops shall be adjusted so that the decay ratio of any RCIC system related variable is not greater than 0.25.
Other Analysic 1.
The delta P switches for the RCIC steam supply line high flow isolation trip shall be calibrated to actuate at the value specified in the plant Technical Specifications (about 300%).
29
STARTUP TEST RESULTS (CONT.)
STI-E51-014 (Cont.)
Results 1.
RCIC Cold Quick Start to Vessel (Rated) (8.4) (TSN-212)
The purpose of this test is to demonstrate the proper operation of the RCIC system during a cold quick start to the reactor vessel at rated reactor pressure.
All Level 1 and Level 2 criteria vere satisfied. RCIC flow was 709.9 gpm at 30 seconds after initiation and peak RCIC turbine speed was 4247 rpm.
No oscillatory responses were observed.
(See attached plot).
TER 212-01 was written to document anomalies on one train of the RCIC leak detection instrumentation. The instrument did not pass the "Other Analysis" criteria of this test, but passed equivalent criteria in earlier tests: The data was forwarded for engineering evaluation.
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30
___________--___-a
T STARTUP TEST RESULTS (CONT.)
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STARTUP TEST RESULTS (CONT.)
STI-E51-014-(Cont.)
2s RCIC Surveillance Baseline Data - Rated (8.7) (TSN-234)'
The purpose of this test is to gather surveillance baseline data during a RCIC initiation (CST to CST) using final system controller settings.
All Level 1 and Level 2 criteria were satisfied. RCIC flow reached 700 gpm in 17 seconds. Peak RCIC turbine speed was 4443 rpm. No oscillatory responses were observed.
(See attached plot).
TER 234-01 was written to document anomalies on one train of the RCIC leak detection instrumentation. The instrument did not pass the "Other Analysis" criteria of this test, but passed equivalent criteria in earlier tests. The data was forwarded for engineering evaluation.
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I STI-E51-014 (Cont.)
i 3.
RCIC Surveillance Baseline Data - 150 psig (8.7) (TSN-294)
This test gathered surveillance baseline data during a RCIC initiation (CST to CST) using final system controller settings.
All Level 1 and Level 2 criteria vere satisfied. RCIC flow reached 700 gpm in less than 30 seconds. Peak RCIC turbine speed was 2870 rpm. No oscillatory Iesponses were observed. '(See attached plot).
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STARTUP TEST RESULTS (CONT.)
STI-E51-014 (Cont.)
I 4.
RCIC Discharge to the Vessel (150 psig) (8.4) (TSN-298) 1 This :est involves demonstration of flow controller stability and a RCIC quick start demonstration at 150 psig to 165 psig.
(See attached plots)
Demonstration of flow controller stability was demonstrated by inserting 10% step changes to the flow controller output at 700 gpm and 350 gpm.
Since the 10% step changes were applied to the flow controller output, which resulted in a 10% rated turbine speed change, system response to the step change is greater at lover pressure compared to rated pressure.
Quick start. capability was demonstrated by manual initiation. The ability of RCIC to achieve and maintain 2700 gpm flov vithin 30 seconds of initiation with no RCIC isolation or trip occurring was satisfactorily demonstrated.
All Level 1 and Level 2 Acceptance Criteria vere satisfied.
It should also be noted that no level anomalies were observed at any time during this test.
35
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STARTUP TEST RESULTS (CONT.)
STI-E51-014 (Cont.)
5.
RCIC Final Controller Settings as determined during Startup Testing are listed below:
RCIC Controls I
1E51-R600 (Main Control Room) 0.10 x 1.0 (DIAL) 0.075 x 1.0 (ACTUAL)
GAIN RESET - 4.0 x 10.0 (DIAL) 3.6 x 10.0 (ACTUAL)
IC61-R001 (Remote Shutdown) 0.05 x 1.0 (DIAL) 0.13 x 1.0 (ACTUAL)
GAIN RESET - 3.5 x 10.0 (DIAL) 3.6 x 10.0 (ACTUAL)
INNER LOOP SETTINGS EGH 8.0 GAIN 6.5 STABILITY 1/4 TURN OPEN NEEDLE VALVE 15.9 SECONDS SLOPE TIME RGSC 4.7 STI-B21-016A Selected Process Temperatures (TSN-244, 279,
]
l 287, 312)
There are three purposes to this test:
1)
To confirm that measured reactor bottom head drain temperature corresponds to the bottom head coolant temperature during normal operation,
)
l l
38
1 1
'STARTUP TEST RESULTS (CONT.)
i STI-B21-016A (Cont.)
2) to identify any reactor operating modes which cause temperature stratification in the reactor vessel, and
)
1 3) to familiarize the plant personnel with the temperature differential limitations of the reactor system.
Acceptance Criteria Level l' l.
The reactor recirculation pumps shall not be started nor flow increased unless the coolant temperatures between the steam dome and bottom head drain are within 100'F.
2.
The recirculation pump in an idle loop must not be started, active loop flow must not be raised, and power must not be increased unless I
the idle loop suction temperature is within 50'F of the active loop suction temperature.
If two pumps are idle, the loop suction temperature must be within 50'F of the steam dome temperature before pump startup.
a Level 2
.q l
During two pump operation at rated core flow, the bottom head temperature as measured by the bottom head drain line thermocouple should be within
)
~
1 30'F of the recirculation loop temperatures.
Results 1.
Drain Line Thermocouple Data (TSN-244)
During two recire, pump operation, with RVCU and CRD in their normal I
configuration, the bottom head temperature as measured by the bottom 39
}
)
L______________------_----
)
l.
STARTUP TEST RESULTS (CONT.)
STI-B21-016A (Cont.).
head drain line thermocouple was found to be within 6 to 8'F of the A & B recirc loop suction temperature.
2.
One Pump Trip Temperature Data (TSN-279)
In this test, reactor coolant temperature and bottom head drain temperature vere monitored following the trip of one recire pump.
l The data showed that coolant temperature differentials were well within the criteria limit of 100'F.
Maximum observed difference
'between the steam dome and bottom head drainline was 41.7'F.
- Also, the temperature difference between the active and the idle loops of the recirc system was 4.9'F, therefore satisfying the 50'F differential criteria.
3.
Two Pump Trip Temperature Data (TSN-287, 312)
Two sets of data vere taken for this test with the Recirculation Pumps tripped and the reactor in natural circulation. The first set of data was of short duration (only 5 minutes) when the plant scram-med from an event unrelated to this test. Data recorded during this test showed no evidence of stratification. 'The second set of data was taken on June 26, again at natural' circulation conditions. After four hours of data collection, a temperature differential of 41.5'F was observed, therefore, satisfying the 100'F criteria.
Pumps were restarted successfully.
4.8 STI-C91-019 Core Performance (TSN-252, 253, 313, 314)
The purposes of this test are to evaluate several of the primary reactor core performance parameters at TC 3 and TC 4 (natural circulation) with l
40
l STARTUP TEST RESULTS (CONT.)
STI-C91-019 (Cont.)
l respect to their corresponding limits in the Technical Specifications.
This testing is divided into evaluation of the " global" parameters of core i
thermal power (CTP) and flov and the localized parameters listed belows i
a.
Maximum Linear Heat Generation Rate (MLHGR);
]
b.
Minimum Critical Power Ratio (MCPR);
)
c.
Maximum Average Planer Linear Heat Generation Rate (MAPLHGR' Acceptance Criteria Level 1 1.
Steady-state reactor power shall be limited to the rated MVT and values on or below the minimum of either rated thermal power or the bounding licensed load line.
2.
The Maximum Lj: ear Heat Generation Rate (MLGHR) during steady state conditions shall not exceed the limit specified by the Plant Technical Specifications.
3.
The steady state Minimum Critical Power Ratio (MCPR) shall exceed the minimum limit specified by the Plant Technical Specifications.
1 4.
The Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) shall not exceed the limits specified by the Plant Technical Specifications.
There were no Level 2 or 3 Acceptance Criteria.
l Results Vith the reactor at steady state conditions, an OD-3 option 2 (long edit)
I was obtained from the process computer on June 2, 1987. The OD-3 edit was used to evaluate core flow and CTP. Additionally, on June 4, 1987, with 41
i i
STARTUP TEST RESULTS (CONT.)
STI-C91-019 (Cont.)
~the reactor at nearly the same conditions, a P1, Periodic NSS Core Per-formance Log, was obtained from the process computer. The P1 edit was used to evaluate the' localized parameters listed above. The results j
showed'that all. values were well within the Technical Specification-limits. Consequently, all Acceptance Criteria vere satisfied.
Global Core Performance Evaluation (TSN-252)
Using the core flow value of 87.5% obtained from the OD-3 edit, the bounding licensing power was obtained by finding the intersection of the core flow value and the ME0D load line. This resulted in a core thermal power limit of 3579 MVt (100% of rated), which far exceeded the current' power level of 2549 MVt (71.2%). Thus, the Level 1 Acceptance Criteria was satisfied.
Localized' Core Performance Evaluation (TSN-253)
~
The folloving table shows the values of localized parameters, their location in the core and the associated limiting value for the reactor conditions at the time of this test in TC 3.
Core Thermal / Hydraulic l
Core Location l Limiting Tech. Spec.
Parameter Value l
x-y-z*
l Value l
l HLHGR 8.86 kv/ft l
45 15 l
f 13.4 kv/ft (2)
]
HCPR 1.948 l
37 - 52 l
2 1.340 (3)
MAPLHGR 7.90 kv/ft l
45 15 l
f 10.25 kv/ft (4) 4
- x-y bundle coordinates j
i z
bundle node (not applicable to dCPR) i I
i 42
STARTUP TEST RESULTS (CONT.)
STI-C91-019 (Cont.)
The column farthest to the right represents the Level 1 Acceptance Criteria. The letter to the right in parentheses indicates which Acceptance Criteria with which it is associated. The values in the column farthest to the left are the most limiting values calculated by the process computer. The results indicate that all the Level 1 Acceptance Criteria vere satisfied.
Global Core Performance Evaluation (TSN-313)
Vith the reactor operating in steady state, natural circulation (TC 4) a OD-3, option 2 (long edit) was obtained from the process computer to determine core thermal power and core ficv.
A core flow of 26%, obtained from 1B33-R613 (Control Room Total Core Flow Recorder), was used to determine the bounding licensing power by finding the intersection of the core flow value and the ME0D line. The MEOD line had to be extended since core flow at these conditions was lower than expected. This resulted in a core reactor thermal power limit of 2040 MVt.
Since the power level computed by OD-3 was 1621 MVt, which is lover than 2040 MVt, the Level 1 Acceptance Criteria was satisfied.
Localized Core Performance Evaluation (TSN-314)
This portion of the test was performed at the same reactor conditions as those above for TSN-313 by requesting the process computer Periodic Core Evaluation Program, Pl.
Results of this evaluation are presented in the table below. No Technical Specification thermal limits were exceeded, and all Acceptance Criteria vere satisfied.
i l
1
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l I:3 L_______________
STARTUP TEST RESULTS (CONT.)
STI-C91-019 (Cont.)
Core Thermal / Hydraulic j
Core Location l Limiting Tech. Spec.
Parameter Value l
x-y-z*
l Value l
l HLHGR 5.88 kv/ft l
51 4 l
f 13.4 kv/ft MCPR 1.833 l
31 - 30 l
2 1.633 MAPLHGR 5.23 kv/ft l
51 4 l
f 7.58 kv/ft
- x-y bundle coordinates z
bundle node (not epplicable to MCPR)
I i
4.9 STI-C85-022 Pressure Regulator (TSN-213, 262, 263)
Purpose The purposes of this test are to demonstrate:
1.
The adequacy of the controller settings for the pressure control loop.
2.
The backup capability of the pressure regulators via the simulated failure of the controlling regulator.
3.
The smooth pressure control transition between the turbine control valves and bypass valves when the reactor steam generation exceeds the steam flow used by the turbine.
l 4.
That the other affected parameters are within acceptable limits during pressure regulator induced transient maneuvers.
44
l STARTUP TEST RESULTS (CONT. )
STI-C85-022 (Cont.)
Acceptance Criteria Lpvel 1 The transient response of any pressure control related variable to any test input must not diverge.
Level 2 1.
Pressure control system related variables may 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.
2.
The pressure response time from initiation of pressure setpoint change to the turbine inlet pressure peak shall be less than or equal to 10 seconds.
3.
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.
4.
.For all pressure regulator transients the peak neutron flux and/or peak vessel pressure shall remain below the scram settings by 7.5 percent and 10 psi respectively (maintain a plot of power vs. the peak variable values along the bounding licensed rod line).
5.
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 flov," for each flow j
range) shall meet the following:
l J
45 1
1 l
STARTUP TEST RESULTS (CONT.)
1 STI-C85-022 (Cont.)
i
% of Steam Flow Obtained With Valves Vide Open Variation (Less than or equal to) q 0 to 85%
4:1 85% to 97%
2:1 85% to 99%
5:1 Level 3 1.
Additional dynamics of the control system outside of the regulator compensation filters, shall be equivalent to a time constant no greater than 10.0 seconds. This also includes any dead band tim?
vhich may exist.
2.
Cor'r ol or bypass valve motion must respond to pressure inputs with deadband (insensitivity) no greater than 20.1 psi.
I Pressure Regulator (Test Condition 3) i i
The Pressure Regulator Tests which were performed during this test condition vere:
1.
Section 8.1, Pressure Regulator Test with Control Valves, which consisted of performing transients with load set at the high end of the band to allow only the control valves to respond to changes in pressure regulator deadband.
2.
Section 8.2, Pressure Regulator T(st with Bypass Valves Incipient, whichconsistedofperformingtransientswiththeloabsetreduced until the closing bias signal to the turbine bypass valves was com-pensated and the lifting of number 1 bypass valve was incipient. The 5 and 10 psi changes were input via a test signal to both A and B Pressure Regulators and responses to these signals were recorded.
I 46 l
L_____________
1
l i
i STARTUP TEST RESULTS (CONT.)
r i
STI-C85-022 (Cont.)
]
)
1 3.
Section 8.4, Pressure Regulator Linearity, consisted of recording values for flow demand (pressure regulator output) and steam flow
)
from,118 HVe to 725 MVe in intervals of 15 to 35 MVe while turbine inlet pressure remained constant.
1 Section 8.1 ine',uded a simulated failure of the operating pressure I
regulutor chr.r.el to the standby channel. This was accomplished by putting a 20 psi step change into the operating regulator and observing transfer to the other.
i All Level 1 and 2 Acceptance Criteria vere verified satisfactory during the performance of this test.
The Pressure Regulator has gone through testing in this and the past teet conditions and is working as designed and expected.
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CONTROL VALVE DEMAND T$N-2l3 60 STEAM FLoli t
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STARTUP TEST RESULTS (CONT.)
4.10 STI-N27-023A Feedvater Control System (TSN-239, 240, 248, 249, 250, 254, 255, 256, 257, 258, 259, 260, 261, 306, 307, 308)
The purpose of this test is to verify that the various components of the Feedvater Control System have been adjusted to provide acceptable control of reactor vater level in all operating conditions.
Acceptance Criteria Level 1 The transient response of any level control system-related variable to any test input must not diverge.
Level 2 1
1.
Level control system-related variables may 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.
2.
The open loop dynamic flow response cI each feedvater actuator (turbine or valve) to small (less than 10%) step disturbances shall be less than or equal to:
l l
a.
Maximum time to 10% of a step disturbance 1.1 see b.
Maximum time from 10% to 90% of a step 1.9 sec disturbance 49 l
STARTUP TEST RESULTS (CONT.)
STI-N27-023A (Cont.)
c.
Peak overshoot (% of step disturbance) 15%
d.
Maximum settling time, 100% 5%
14 sec 3.
The average rate of response of the feedvater actuator to large (greater than 20% of pump flow) step disturbances shall be between 10% and 25% of rated feedvater flow /second. This average response rate vill be assessed by determining the time required to pass linearly through the 10% and 90% response points.
Level 3 Initial settings of the function generators should give a straight line.
The function generators must be adjusted so that the change in slope (actual fluid flow change divided by demand change for small disturbances) shall,not exceed a factor of 2 to 1 (maximum slope versus minimum slope) over the entire 20% to 100% feed flow range.
Also the function generators should be used to minimize the differences between feedvater actuators (pumps and/or valves).
Results A.
FV Startup Rx Level Controller Steps (8.3)
Section 8.3 of STI-N27-023A vas performed individually on TDFPA, TDFPB, and the MFP in Test Condition 3 and individually on TDFPA and B in TC 5.
The testing involved initiating six inch increasing /
decreasing steps in reactor water level (controller in AUTO for that pump). Throughout each step change, the system's responses were monitored and recorded. The data obtained during testing was evaluated to verify system stability and correct controller response.
All Acceptance Criteria vere satisfied.
1 i
50
STARTUP TEST RESULTS (CONT.)
STI-N27-023A (Cont.)
B.
FV Pump Open Loop Steps (8.4)
Section 8.4 of STI-N27-023A vas performed individually on TDFPA, TDFPB, and the MFP in TC 3.
The testing involved initiating approximately 8% and 22% (of pump full flow demand) open loop decreasing and increasing steps, allowing the system to stabilize between each step. Throughout each step change the system's responses were monitored and recorded.
The average rate of response to the 22% steps for TDFPB and the MFP was outside the Level 2 Acceptance Criteria. Also the 0-10% and 10-90% rise time response for the MFP vere outside the Level 2 Acceptance Criteria. All other Acceptance Criteria were met satisfactorily. The performance of the system was determined to be acceptable for continued operation.
TER's were written against all Level 2 violations. These tests vill be reperformed as scheduled tests in TC 6 after further tuneups to optimize the systems are completed.
Attached are plots of the 22% decreasing / increasing steps for TDFPA.
C.
FW Master Rx Level Controller Steps (8.5)
Section 8.5 of STI-N27-023A vas performed individually on TDFPA, TDFPB, and the MFP and in combinations of TDFPA and TDFPB, TDFPA and MFP, and TDFPB and MFP in TC 3.
In TC 5, the combination of TDFPA and TDFPB vas tested. The testing involved initiating six inch increasing / decreasing closed loop steps using the Master Reactor Level Controller tapeset in AUTO. Throughout each step change, the system's responses were monitored and recorded. The data obtained 51
STARTUP TEST RESULTS (CONT.)
STI-N27-023A (Cont.)
I during testing was evaluated to verif> system stability and correct J
controller response.
All Acceptance Criteria vere satisfied.
D.
FV Control Linearity (8.6)
Section 8.6 of STI-N27-023A vas performed individually for TDFPA and TDFPB in TC 3.
The testing involved adjusting flov to vessel with the controller in MANUAL for that pump and collecting steady state data points between 20-100% of pump flow. The maximum slope was determined to be 2.52 and 3.53 times the minimum slope for TDFPA and TDFPB respectively, which were outside the Level 3 Acceptance Criteria. TER's were written against the Level 3 violations. These tests will be reperformed as scheduled tests in TC 6 after further tuncups to optimize the systems are completed. Also during TC 3, the tests were performed at constant power. In TC 6, data vill be l
collected at various power increments. During the test, the TDFPA and TDFPB HANUAL/ AUTO Station Flow Demand output ranged between 58%
and 78%, and 54% and 75% respectively with a 40-100% demand output expected. An FCR was written to address this.
It is expected that the output vill cover a vider range during TC 6 testing.
Section 8.6 of STI-N27-023A for TDFPA and TDFPB is scheduled to be performed again in TC 6.
Attached are graphs of TDFPA and TDFPB flow versus % flov demand.
52
1 i
STARTUP TEST RESULTS (CONT.)
TSN-248 i
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STARTUP TEST RESULTS (CONT.)
TSN-248-
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STARTUP TEST RESULTS (CONT.)
RFP A LINEARITY CHECX 9
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STARTUP TEST RESULTS (CONT.)
4.11 STI-N27-023D Maximum Feedvater Runout Capability (TSN-302)
This test gathers a portion of the data which will be used (in TC 6) to i
verify that the feedvater system flow capabilities are within FSAR l
Chapter 15 assumed limits.
)
Acceptance Criteria N/A for TC 5 i
Results i
Reactor Feed pump (RFP) turbine speed, controller output, and flow to vessel data were recorded at 5% power intervals during this test. This data, together with TC 6 data, vill be used to calculate the effect of reactor pressure changes and RFP turbine speed changes on feedvater flovrates to the reactor vessel. Test data vill then be extrapolated to the plant conditions assumed for a feedvater controller failure in FSAR Chapter 15 to verify that Feedvater flow is within the specified limits.
4.12 STI-B21-025A MSIV Function Test (TSN-214, 215)
The purpose of this test is to functionally check each MSIV for proper operation at 30-55% reactor power, to determine valve closure times and to
{
obtain data which vill be used to determine the maximum power at which the full closure of a single MSIV can be performed without a scram.
Acceptance Criteria Level 1 The MSIV stroke time (t3) shall be no faster than 3.0 seconds (average of the fastest valve in each steam line).
For any individual valve, t must s
56
--____________-_-______-_A
I i
STARTUP TEST RESULTS (CONT.)
i STI-B21-025A (Cont.)
be between a minimum value of 2.5 seconds and a maximum value of 5 seconds. Total effective closure time for any individual MSIV shall be t,,3 plus the maximum instrumentation delay time (td) as determined in preoperational test 1B21C-P-001 and shall be less than or equal to 5.5 l
seconds.
l Level 2 1.
The reactor shall not scram or isolate.
2.
During full closure of individual valves peak vessel pressure must be 10 psi below scram, peak neutron flux must be 7.5% below scram, and steam flov in individual lines must be 10% below the isolation trip setting. The peak heat flux must be 5% less than its trip point.
1 Results Each MSIV vas manually closed, then reopened, at - 45% power allowing the reactor power and pressure transient to stabilize prior to each step.
During the valve closures, ERIS was used to monitor the MSIV position switches.
From the ERIS data, valve closure times were calculated.
Average MSIV stroke time was calculated to be 3.38 see (fastest in each steamline). The fastest MSIV vas 1B21-F022C which closed in 2.94 sec.
Plant data from the closure was used to calculate the scram margin for l
neutron flux, heat flux, reactor pressure, and steam flow. All margir.s were within the Acceptance Criteria and all other criteria were satirfied.
The data from the closure of the fastest MSIV (lB21-F022C) vill be t' sed to determine the maximum power at which the full closure of a single PSIV can be performed without a scram during subsequent testing at later trst j
l conditions.
l l
57 i
U____-___-___
STARTUP TEST RESULTS (CONT.)
STI-B21-025A (Cont.)
Stroke Total Effective MSIV Time (sec)*
Closure Time (sec)**
F022A 3.95 4.360 F022B 3.38 3.878 F022C 2.94 3.435 F022D 3.28 3.728 i
F028A 4.03 4.561 F028B 3.33 3.896 F028C 3.29 3.904 F028D 3.30 3.803
- Stroke time criteria must be between 2.5 and 5 sec.
- Total effective closure time must be less than 5.5 sec.
From transient due to closure of 1B21-F022C:
Parameter Margin to Scram Heat Flux 43.75%
Rx Pressure 116.7 psi Neutron Flux 74%
Steam Flow 85%
4.13 STI-B21-027 Turbine Trip and Generator Load Rejection (TSN-273) l This test verified the Bypass Valve Capacity to be greater than or equal to 35% of rated steam flov. Data was collected at various bypass valve positions while keeping all other steam loads constant up to approximately 90% of total bypass valve position.
Using the data obtained, a curve of bypass valve position versus steam flow was generated. The slope of the 58
STARTUP TEST RESULTS (CONT.)
STI-B21-027 (Cont.)
curve was determined and, using that slope, the curve was extrapolated to 100% bypass valve position. Actual bypass valve capacity was determined to be 35.7% of rated steam flow, which is above the 35.0% capacity assumed in the FSAR analyses.
Acceptance Criteria Level 1 None Level 2 Verify bypass valve capacity is equal to or greater than capacity assumed in FSAR analysis (35% NBR steam flov).
9 All Acceptance Criteria vere initially met. The data obtained showed good linearity between bypass valve position and bypass valve flow which provided assurance that the data being taken was acceptable and that the bypasa valves have linear flow characteristics. Attached are copies of the graphs developed from the data obtained.
It was later determined that the turbine throttle flov instrument was not accurate enough for measuring the Bypass Valve Capacity. A retest vill be performed at higher power in TC 6 using the much more accurate feedflow nozzles for determining this capacity.
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STARTUP TEST RESULTS (CONT.)
STI-B21-027 (Cont.)
TABLE FOR STEAM FLOV DATA CURVES X
l Y1 l
Y2 BPV TOTAL POSITION l
TURBINE STEAM FLOV l
MAIN STEAM FLOV C85EA011 l
C34EA031 l
SUM OF C34EA014 +
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+ C34EA017 I
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l 11.23 (CALC) l 9.87 (CALC) 10.63 l
10.67 l
9.91 19.19 l
10.27 l
9.94 29.78 l
9.725 l
9.97 39.76 l
9.112 l
9.97 50.56 l
8.618 l
10.03 59.38 l
8.168 l
10.04 73.24 -
l 7.426 l
10.07 80.76 l
6.993 l
10.11 91.66 l
6.414 l
10.13 I
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l 4.14 STI-B33-029A Recirculation Flow Control - Valve Position Loop
]
(TSN-267, 268, 269, 270) i The purpose of this test is to demonstrate the proper operation of the valve position control loops of the Recirculation Flow Control System, while in the loop flow manual mode.
Testing of the Recirculation Flow Control System follows a " building block" approach while the plant is ascending from lov to high power levels.
Components and inner control loops are tested first, followed by flow and power maneuvers to demonstrate outer control loop performance.
This particular test covered the performance testing of the flow control components and inner control loop (valve position). The outer control loops (flow, flux and master control loops) performance is demonstrated after position control loop testing during the performance of STI-B33-029B, Recirculation Flow Control-Flow Loop.
Additionally, scram avoidance capability was demonstrated by performing single loop flow ramps controlled by the reactor operator.
Acceptance Criteria Level 1 The transient response of any Recirculation System related variables to any test input must not diverge.
Level 2 1.
Recirculation System related variables may 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.
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STARTUP TEST RESULTS (CONT.)
STI-B33-029A (Cont.)
i 2.
Maximum rate of change of valve position shall be 10 1%/sec.
1 NOTE:
During TC 3 vhile operating on the high speed (60 Hz) source, gains and limiters shall be set using PTI-B33-P0001 to obtain the following response.
3.
Delay time for position demand steps shall be less than or equal to 0.15 seconds for step inputs of 0.5% to 5%.
4.
Response time for position demand steps shall be less than or equal to 0.45 seconds for step inputs of 0.5% to 5%.
5.
Overshoot after a small position demard input (1 to 5%) step shall be less than 10% of the magnitude of the input.
6.
The trip avoidance margins must be at least the following:
a.
For APRM, greater than or equal to 7.5%.
b.
For simulated heat flux, greater than or equal to 5.0%.
7.
The flow control valve duty cycle in any operating mode shall not exceed 0.2% Hz.
Flow control valve duty cycle is defined as:
Integrated Valve Movement in Percent
(% Hz) 2 x Time Span in Seconds Level 3 Position Loop deadband shall be less than 0.2% of full valve stroke.
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STARTUP TEST RESULTS (CONT.)
1 STI-B33-029A (Cont.)
4 Results
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Position Demand Step Testing With the plant operating on approximately the 70% rod line, the recirculation pumps on high speed and flow control in loop flow manual mode, small flow step changes (25%) were made at core flow conditions of 50%, 78%, and 100%. The system response data is presented below:
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l STARTUP TEST'RESULTS (CONT.)
1 STI-B33-029A (Cont.)
Results (Cont.)
The Level 1 Acceptance Criterion was satisfied. Several Level 2 Acceptance Criteria were not met. Their resolutions are detailed in TERs 267-1, 268-1, 268-2, and 269-1.
Approved resolutions for all four TERs were the same:
"G.E. to evaluate acceptance criteria violations prior to entering TC-7._ Continued opera-tion is acceptable based on preliminary evaluations which show the system to be responsive and stable." It should be added that in each case the incremental values by_vhich the criteria were exceeded are small'and have little or no effect on plant operation. All criteria violations were reviewed to ascertain that-there vere no unreviewed safety issues.
2.
Scram Avoidance Testing (TSN-270)
With the plant operating on the 60% rod line and initial core flow of 60%, a ramp increase of 15% vas input to the Recire Loop A Flow Controller. Once plant conditions had stabilized, loop A flow was returned to approximately its initial condition and the test repeated with a similar 15% ramp increase on the B loop.
Analyzed results and their respective comparisons to 1.evel 2 Acceptance Criteria are as follows:
i lL 66
STARTUP TEST RESULTS (CONT.)
STI-B33-029A (Cont.)
Scram Avoidance Test at TC 3 Hargin to Scram Setpoints For Peak Anticipated For Peak Anticipated Heat Flux Neutron Flux AC 2 5%
AC 2 7.5%
1 Loop A Ramp 0.2%
- 8.4%
Loop B Ramp
- 1.4%
- 9.7%
- Failure to meet the criteria vere documented in TER 270-1.
The Level 2 criteria for margin to scram for peak anticipated heat flux vere violated and documented in TER 270-1.
Final resolution has been postponed to TC 7 and is considered to be appropriate since the results presented here are extrapolated results.
In reality, adequate margin to scram exists until the plant enters TC 7 testing.
4.15 STI-B33-029B Recirculation Flow Control (TSN-216, 264, 271, 274)
The purpose of this testing is to demonstrate the recirculation flow control system's capability while operating in the Flux Manual and Master Manual modes of operation and to verify that all electrical compensators, controllers, and limiters are set for the desired system performance and stability.
67
STARTUP TEST RESULTS (CONT.)
STI-B33-029B (Cont.)
Acceptance Criteria A.
Flow Loop (Flux Hanual Mode)
Level 1 The transient response of any Recirculation System Related variables to any test input must not diverge.
Level 2 1.
The decay ratio of the flov loop response to any test inputs shall be less than 0.25.
2.
Flov loops are for the purpose of maintaining steady-state flov equal in the two loops.
Flov loop gains should be set to correct a flow imbalance in less than 25 sec.
3.
The delay time for flow demand step (less than or equal to 5%)
shall be 0.5 seconds or less.
4.
The response time for flow demand step (less than or equal to 5%) shall be 1.2 second or less.
5.
The maximum allovable flov overshoot for step demand of less than or equal to 5% of r.ated shall be 6% of the demand step.
l 6.
The flow demand step settling time shall be less than or equal l
to 6 seconds.
l 68
i STARTUP TEST RESULTS (CONT.)
i i
STI-B33-029B (Cont.)
1 Level 3 1
Incremental gain from the function generator for valve position demand input to sensed drive flow shall not vary by more than 2 to 1 j
over the entire flow range.
B.
Flux Loop (Master Manual Mode) l l
Level 1 The flux loop response to test inputs shall not diverge.
Level 2-1.
FluxLovershoot to a flux demand step shall not exceed 2% of rated for a: step demand of less than or equal to 20% of rated.
2.
The delay time for flux response to.a flux demand step shall be-less than or equal to 0.9 seconds.
3.
The response time for flux demand step shall be less than or equal to 2.6 seconds.
4.-
The flux settling time shall be less than or equal to 15 seconds for a flux demand step less than or equal to 20% of rated.
C.
Flux Estimator Level 1 None l
69 l
l_
1 l.
d
STARTUP TEST RESULTS (CONTJ STI-B33-029B (cont.)
Level 2 1
l i
f 1.
Switching between estimated and actual flux should not exceed 5 times /5 minutes at steady state.
2.
During a flux step transient there should be no switching to actual flux or, if switching does occur, it should switch back to estimated flux vithin 20 seconds of the start of the transient.
Scram Avoidance and General Level 1 None Level 2 1.
For any one of the above loop's test maneuvers, the trip avoidance margins must be at least the following:
a.
For APRM: Greater than or equal to 7.5%.
b.
For simulated heat flux: Greater than or equal to 5.0%.
Flow Control Valve Duty Level 1 1
None l
)
70 l
STARTUP TEST RESULTS (CONT.)
STI-B33-029B (Cant.)
Level 2 The flow cor. trol valve duty cycle in any operating mode shall not exceed 0.2%-Hz.
Flov Control Valve duty cycle is defined as:
Integrated valve movement in percent l
%-Hz) 2 x time span in seconds j
1 Results A.
Linearity Data Collection This test was originally performed with the Recire Flow Control l
System in Loop Flow Manual. This mode of operation functions such that each flow controller generates a position demand signal to control the respective flow control valves individually. The data collected during the performance of this test was determined to be insufficient as the ERIS computer points used to collect the data did not monitor the required signals when operating in the Loop Flow Manual mode. TER 216-1 was initiated to document this fact and to reperform the test in Flux Manual Mode.
In this mode, a flow demand signal can be generated which vill result in a common input to each loop controller for controlling the respective recirculation flow control valve. The retest was successfully completed on June 7, 1987.
The linearity data for each loop are attached. Other pertinent information from the analyzed data are:
Loop A Loop B minimum slope 0.8 0.8 maximum slope 1.25 1.21 maximum incremental change 1.56 1.51 71
STARTUP TEST RESULTS (CONT.)
STI-B33-029B (Cont.)
Maximum incremental gain change (maximum slope to minimum slope) was verified not to exceed 2 to 1 over the entire flow range for each loop, thus satisfying the Level 3 criteria. No other Acceptance i
Criteria are applicable.
B.
Controlling Mode Testing l
1 Results Testing performed with the Recirculation System in the flow control mode (Flux Manual) verified the tuning at Test Condition 3 to be l
adequate for transients along the 60-75% load lines.
Five and ten percent step changes were inserted into the flow loop using a step generator.
Responses were analyzed for stability, delay time, FCV duty cycle, response time, overshoot, and settling time. Loop flows vere compared to verify balanced flov. Also, heat flux and neutron flux margins to scram were calculated. Although there vere several criteria violations, the system demonstrated stable responses. The l
criteria violations are due in part to the excessive noise in the 1
recirculation flov signals. This problem is currently being investi-gated by General Electric.
A summary of the test exceptions is shown below.
Description of Exceptions (Flov Loop)
Core Flow Step Parameters / Loop Measured Criteria 58-62%
-5%
overshoot /A 45%
f 6%
58-62%
+5%
overshoot /A 48%
$ 6%
58-62%
-5%
Settling Time /A
>30 see f 6 sec 58-62%
+5%
Settling Time /A
>30 see f 6 sec l
l l
72
STARTUP TEST RESULTS (CONT.)
STI-B33-029B (Cont.)
Description of Exceptions (Flow Loop) (Cont.)
Core Flov Step Parameters / Loop Heasured Criteria 78-82%
+5%
Delay Time /A 0.62 see f 0.5 sec j
78-82%
+5%
Response Time /A 1.3 sec f 1.2 sec 78-82%
-5%
overshoot /A 52%
f 6%
78-82%
-5%
Settling Time /A
> 6 sec
$ 6 sec 98-100%
-5%
Delay Time /A 1.05 see f 0.5 sec 98-100%
+5%
overshoot /A 32%
$ 6%
98-100%
+5%
Settling Time /A
>15 sec f 6 sec 58-62%
-5%
Overshoot /B 50%
$ 6%
58-62%
+5%
overshoot /B 45%
$ 6%
58-62%
-5%
Settling Time /B
>20 see f 6 sec 58-62%
+5%
Settling Time /B
>15 see f 6 sec 98-100%
-5%
Delay Time /B 0.67 see f 0.5 sec 58-62%
-5%
Balanced flov 2.8%
f 2%
58-62%
45%
Balanced flov 2.3%
f 2%
58-62%
+10%
Balanced flov 2.5%
$ 2%
78-82%
-5%
Balanced flow 3.6%
$ 2%
98-100%
-5%
Balanced flov 4.6%
f 2%
98-100%
+5%
Balanced flov 2.9%
$ 2%
98-100%
-10%
Balanced flov 7.5%
$ 2%
58-62%
-5%
Heat flux
-2.0%
1 5.0%
58-62%
+5%
Heat flux
-5.9%
1 5.0%
j 58-62%
+5%
Neutron flux
-50.89%
2 7.5%
73
-_--_______a
STARTUP TEST RESULTS (CONT.)
STI-B33-029B (Cont.)
Description of Exceptions (Flow Loop) (Cont.)
Core Flov Step Parameters / Loop
- Heasured, Criteria 58-62%
-10%
Heat flux
-6.0%
2 5.0%
58-62%
+10%
Heat flux
-7.3%
2 5.0%
58-62%
+10%
Neutron flux
-52.6%
2 7.5%
78-82%
-5%
Heat flux 0.0%
2 5.0%
78-82%
+5%
Heat flux
+3.7%,
2 5.0%
78-87%
+5%
Neutron flux
-12.8%
2 7.5%
98-100%
+5%
Neutron flux
+2.3%
2 7.5%
96-100%
+10%
Heat flux
+2.4%
25.0%
98-100%
+10%
Neutron flux
-11.9%
2 7.5%
Results (Flux Loop)
Testing performed with the Recirculation System in tha flux, control mode (Haster Manual) verified the tuning at Test Condition 3 to be adequate for transients along the 60-75% load lines.
Five percent flov eteps were performed at 80% core flow with 4% steps at 100% core flow. Each flux demand step was performed with and without the flux estimator in service. Although there vere several criteria viola-tions, they were relatively minor and did not require additional tuning at Test Condition 3.
Again, the violations are due in part to the excessive noise in the recirculation flow signals. A summary of the test exceptions is shown below.
i 74
y-.
S P
..g 4 't,
~
.[ t
, 'a i
]
STARTUP TEST RESULTS (CONT.)
t i
't y
1 t:
i 4g i
STI-B33-029B (Cont.)
)
3 r
{'.y i
s Description of Exceptions (Flux Loop)
[
"b Flux-3 y
(
Estf stor 9
Measured'%
~
\\
Core Flow Step Parameters / Loop
/ Criteria (Status Mi i,
178-82%
-5%
Heat Flux A Margin 0%
2 5%
Bypass.
NY j
M 78-82%
-5%
Heat Flux B Margin
-l% *t 1 15%
Bypass it. l
,5 w *.
78-82%
+5%
Heat Flux Margin 1.6U I 241" Bypass
)
.h t.
a i
n; 98-100%
-4%
Delay Time 1.01 sec ! f 0.'Osec Normal 98-100%
-4%
Response Time 4.38 seca f 2.6 see Normal' 4r
+y 78-82%
-5%
Response Time 3.0 see f 2.6 sec jNorr$1 g'l
'n, 78-82%
-5%
Settling Time 28.4 sec
.$15see Normal 78-82%
-5%
Heat Flux A Margin 4%
, y 5%
Normal
(
78-82%
-5%
Heat Flux B Margin 44 5%
Normal
+
a,,
78-82%
+5%
Heat Flux Margin 1.4%.
15%
1Armal
\\l E
6 All test exceptions for the flow and flux loops ere e l,tuated by t
General Electric and determined not to fapact 9}e e d eration.3. T Q
'7.,
Recirculation System vill be retuned priorito. '/rforming this test 3,)- } i'\\
[
i
<m><
again at Test Condition 6.
,'j
' p ^.
\\
5
\\
?,
} g
- i j
r
,l t
k<
f l
8 1 -
i 1
I
)' (
t i
+
c j
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r.
g
(
75 s.
a
.\\ '
i
.: y
^ -
~,
a p
4 I
j Y
s
\\
'\\
i STARTUP TEST RESULTS1 CON'i.'i.'
.k I
h, s
a-f t
,4 t
c
'g TSN-216 & 264
.s s
4 4
i LINEARITY DATA PLOT-LOOP A I
1 tm 3
,.s..._--_-.._.._.
(
l 1Yh 1
1
,,0
.. 7 N
kJ.
- 1
- on.
s n
64
- e$
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4; 8
M-
=
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.o.
___ b.
ex:
. ca s
.s k
ge
_e.
e
=
e-t
/.
y,.
a
'A
+
l.._
-_.._~,;..
.l y.
3(fe,k)
< 70 90 tto DRIVE FLOW DEMAND (%)
t e
..t
[
'i 3
)
76 t
.s i
r l
- e.
1
.]
f STARTUP TEST RESULTS (CONT.)
TSN-216 & 264 L1NEARITY DATA PLOT-- LOOP B
- j5 d
P
,,0..
.__I_%
ion.
/
e4.
v go.
/_.
n.
8 v.ey a
~
g 3
. __ g._.
g so.
I..
4
=
=
4g.
O' 30 50 70 SO 110 DRIVE FLOW DEMAND (%)
I 77
STARTUP TEST RESULTS (CONT.)
4.16 STI-B33-030A One Recirculation Pump Trip and Restart (TSN-275)
The purposes of this test are: 1) to obtain recirculation system performance data during the pump trip, flow coastdown, and pump restart, i
and 2) to verify that the feedvater control system can satisfactorily control vater level without a resulting turbine trip / scram.
Acceptance Criteria Level 1 i
The reactar shall not scram during the one pump trip recovery.
Level 2 1.
The reactor vater level margin to avoid a high level trip shall be greater than or equal to 3.0 inches during the one pump trip.
NOTE:
Margin to trip is defined as:
Margin - L8 - [1/2 (L4 + L7) + AL] where at is the magnitude of the level swell during the one pump trip test.
2.
The simulated heat flux margin to avoid a scram shall be greater than or equal to 5.0 percent during the recovery from the one pump trip.
3.
The APRM margin to avoid a scram shall be greater than or equal to 7.5 percent during the one pump trip recovery.
4.
The time from zero pump speed to full pump speed shall be greater i
i than 3 seconds.
i i
78 l
L i
STARTUP TEST RESULTS (CONT.)
STI-B33-030A (Cont.)
Results From an initial power of 60% and core flow of 104%, Reactor Recirculation Pump A vas manually tripped. Since TDFP A was secured, a Recirc FCV runback vas received when Level 4 was experienced during the level tran-sient following the pump trip. The recire pump was not immediately restarted due to other testing in the single loop operation condition.
Once these were completed, the recire pump was restarted successfully, During the pump trip, the reactor water level margin to turbine trip / scram setpoint was 12.1 inches as determined from the narrow range level transmitters. The margin to APRM scram setpoint was 55.2%.
During the recirc pump restart, the margin to the Flov Biased Simulated Thermal Power scram setpoint was 24% and the pump came up to speed in 4.5 seconds.
79 I
STARTUP TEST RESULTS (CONT.)
~
{-62%
- RECIRCULATION PUMP A TRIP (Sheet I of 2)
- - - - - - - - - ~ - - - - - ~ ~ - - - - - - -
. 4....
r 4
RECIRC, PUMP A SPEED 5
~~
RX WIDE'RANCE LEVEL B
\\
/
I m
- \\
m h
RX WIDE RANGE. LEVEL L
~
2 f
yf)th Y$
AS ss -
2
{
i73 Inches-4 b.
k V RX WIDE RANGE LEVEL A
+
172 Inches g
s f.h 172 Inches
- u 6
~
T a: -
cRECIRC PUMP A TRIP c
]
14 E,
n RECIRC FCV RUNBACK INITIATED GRID INTERVAL: 2 Seconds 80
STARTUP TEST RESULTS (CONT.)
l TSN-275 RECIRCULATION PUMP A TRIP _
(Sheet 2 of 2)
~
g "o
C WIDE RANGE LEVELS B
s 197 Inches m
2 4
l r
L 195 Inches o
A 196 Inches j
~
w gg.e 27% m sk.
APRM A FLU..g
~
/_. -
N.
s l
/
ff?
Yf
~
I 0' RPM
~16%
iD*
(PUMPSPEED g
iso W
Q.
e 81
I l
i i
STARTUP TEST RESULTS (CONT.)
i
.TSN-275 RECIRCULATION PUMP A RESTART
)
17'80 RPM 45.
4-WIDE RANGE LEVELS
~
B
';p"'
54%
4 L = 199 Inches..
- i...
2:
,,.g_ --
n A
.l--
. JJh,L 15111.
b 19.4 Inches h
I 2
~ 4 3"f APRM A FLUX -.--
i r-FUMP SPEED g
f
..j.
...p
+
t 0 RPM i
c
- 4. 5 SECONDS --->
ZERO SPEED TO FULL PUMP SPEED
~'
l t
82
STARTUP TEST RESULTS (CONT.)
1 4.17 STI-B33-030B RPT Trip of Two Pumps (TSN-285)
The purpose of this test is to verify the proper operation of the l
recirculation pump trip (RPT) circuitry and to demonstrate that the flov j
coastdown of the recirculation loops is satisfactory prior to the turbine I
generator trip tests and subsequent commercial power operations.
Acceptance Criteria Level 1 The two pump drive flow coastdown transient during the first 3 seconds must be bounded by the limiting curves.
(These curves have been determined based on measurements of the recirculation flow delta P, using the elbov flow meters, and transmitter j
l time delay and time constant).
Level 2 None l
Results This test was initiated by jumpering across the Turbine Control Valve and Turbine Stop Valve contacts to initiate an EOC RPT trip of the RPT circui-try.
The length of time between initiation of the RPT signal and opening of the breakers was verified to be less than 140 milliseconds. The pump coastdown was found to be faster than the Acceptance Criteria limiting curves vith bounds of pump inertia time constant between 4 and 5 seconds.
Analysis by GE has shown that an inertia time constant from 3.5 to 5 seconds is acceptable. The measured time constant was greater than 3.5 seconds; therefore, it was concluded that the coastdown was acceptable.
83
STARTUP TEST P.ESULTS (CONT.)
I 1
Becira'1= tion Drive Flow Coastdown,1400 A TSN-285
_- d.
.1, u
-x
.s.
.....-.4 N...,........
.1~........m.......
.. ~..
_..._i.
3
. L....._s
.. W
-m x
x x
)
'x w
t p
X esp
- '\\
'x M Iseftia*-
e Time Canstant = $ aws x
x 9_.. _
e
~
~
'9
=_
'x 47 w
x
_M NN" M
=.
e5 e
~,
c a
~
=
e=
m h.
7 m
w Ns I
. _ =.. _
L as -
l J
e s.o
' 2.s J.o 4.0 5.0 Time Af te-Pusrj Trip (excluding 0.140 see delay) seconda
}
l l
l 84 1
STARTUP TEST RESULTS (CONT.)
j recirculation Drive riow coastdown. toco a 1
TSN-285-
. _... ~...
1
-m m
w
_s
'N
~
. _.s._.
=
_E.
._...._. # x
__x. x m
i.
g --
_._.. 3 x,- %.
w.
g
~
~
-~
~
. rum, t,31s
~
1
...J.....4....
N % %,,,,3.
.e g,
~
x e
~
q
~
~
- 1a. es sme.s -
~m s
m m
m m
~
~. -
~
- 'n.
N o
-W ~x _
s-so
- =
+
as e
s.o 2.o J.o 4.o 3.e Time After P. asp Trip (excluding 0.140 sec delay), seconds
.j
{
85
1 I
I l
STARTUP TEST RESULTS (CONT.)
4.18 STI-B33-030C Recirculation System Performance (TSN-265, 277, 284, 311)
The purposes of this test are to obtain Recirculation System performance data for certain steady state one pump and natural circulation operations, and the two pump operation ramp maneuvers along a constant rod line.
Acceptance Criteria Level 1 None l
Level 2 l
l 1.
The core flow shortfall shall not exceed 5% at rated power.
2.
The measured core dP shall not be greater than 0.6 psi above prediction.
3.
The calculated jet pump M ratio shall be greater than the prediction minus 0.2.
4.
The drive flov shortfall shall not exceed 5% at rated power.
5.
The measured recirculation pump efficiency shall not be greater than 8% below the vendor tested efficiency.
6.
The nozzle and riser plugging criteria shall not be exceeded.
7.
The peak to peak core plate 6P shall not exceed 3.2 psi during single loop operation.
86
STARTUP TEST RESULTS (CONT.)
STI-B33-030C (Cont.)
8.
The peak to peak APRM noise shall not exceed 30% of rated during single loop operation.
Results 1.
Two Pump Performance (TSN-265)
Vith the plant operating at 40% power (APRM-A) and the recirculation system in normal two pump operation with minimum FCV position, initial data was recorded. Core flow was then increased to 50% and required data were recorded after conditions had stabilized.
I Subsequent data vere obtained in similar manner at core flows of 65%,
75%, 90%, 100%, and maximum core flow. Core flow data vere evaluated using the JRPHP03 computer program for the 40%, 75%, 100%, and max flow data sets. Results indicated the following Level 2 violations.
a.
M-Ratio criteria not met at 75%, 100%, and max flow.
b.
Riser plugging criteria not met at 40% flow.
c.
Nozzle plugging criteria not met at 40% and 100% flow.
These test exceptions are documented in TER 265-1.
The resolutions as stated in that TER vere as follows:
Approved Resolution:
a.
M-ratio discrepancies have been reviewed by General Electric.
The conclusion was that there is not a problem provided that core plate 6P does not exceed 24.1 psi when above rated core J
flow or 22.0 psi at 100% core flov. A final and more accurate
)
J 1
l evaluation vill be made after completion of testing in TC 6.
1 Core 6P is not expected to exceed design limits.
87
i.
STARTUP TEST RESULTS (CONT.)
l l
l STI-B33-030C (cont.)
l l
b.
Nozzle and riser plugging violations are not uncommon at low core flows. The program (JRPUMP) is known to give inaccurate results at low coce flows.
j c.
Nozzle 12 plugging at 99.7% core flow is not considered a problem. Other data sets at high flows do not indicate nozzle plugging. This data point vill be observed again when the test is performed at TC 6.
s All other Acceptance Criteria vere satisfied.
2.
Single Pump Performance (TSN-284 for Loop A, TSN-277 for Loop B)
In these two tests Recirculation System data vere obttined during one loop operation following the one pump trips performed per STI-B33-030A. The data vere analyzed for core plate dP and APRM neutron flux stability. The one loop operation data vare also compared with the predicted core.and loop flow.
All Acceptance Criteria vere satisfied.
3.
Natural Circulation (TSN-311)
The plant was placed into natural circulation conditions (43% Core Pover, 25% Core Flov, TC 4).
Once stable conditions were reached, ERIS data vere collected by the statistical analysis function. All baseline data vere collected satisfactorily. There are no Acceptance Criteria for this test.
l l
4.19 STI-B33-030E Recirculation System Cavitation (TSN-278, 283, 295)
I The purpose of this test is to verify that no recirculation system cavitation vill occur in the operable region of the pover-flow map.
{
88
(
STARTUP TEST RESULTS (CONT.)
STI-B33-030E (Cont.)
Acceptance Criteria Level 1 None Level 2 i
1.
Recirculation cavitation interlocks shall have settings adequate to prevent operation in areas of potential cavitation.
2.
Cavitation shall not occur during Sinagle Loop Operation while i
operating above the procedural limit defined by the following:
% power - 3 * (% core flov) - 110 Results Vhile the Recirculation Systen is in Single Loop Operation following trip-ping of an individual recire pump by other tests, pump A for ETI-B33-030A and pump B for STI-F41-034, existence of indications of cavitation is in-vestigated. When in Single Loop Operation, the differential temperature interlock is not effective in preventing cavitation in the operating loop, therefore, a procedural limit is imposed. Following the trip of either pump, it was found that the reactor was operating below this limit.
Data at this point was compared with the steady-state data prior to tripping the Recirculation Pump, i.e., normal two-pump operation.
In neither test vere any indications of cavitation observed.
Vith the recirculation FCV's vide open to obtain maximum core flow on l
approximately the 60% rod line, control rods vere inserted until a Recirculation Pump fast-to-slov speed transfer was initiated by the differential temperature interlock. This interlock compares stean, dome 89
STARTUP TEST RESULTS (CONT.)
STI-B33-030E (Cont.)
temperature with recirculation loop suction temperature and has a nominal setpoint of 9.8'F to provide cavitation protection for the recirculation pumps and jet pumps. The transfer was initiated at 50.1% power (approxi-mately 7.6*F), no indications of cavitation were observed prior to the transfer. TER 295-1 was issued to document the trip to 'off' vice 'slov' of Recirculation Pump A.
Condition Report 87-305 was issued to investi-gate this problem.
l' l
4.20 STI-B21-033 NSSS Vibration / Strain l
STI-P99-122 B0P Thermal and Vibration Steady State 1.
Vibration Recirculation Flow Ramp TSN-211 - 8.1 NSSS Steady State Vibration / Strain STI-B21-033 Performance of this test required monitoring NSSS Main Steam and Recirculation piping for steady state vibration / strain during the recirculation flow ramp for power ascension in Test Condition 3.
Data was collected and analyzed at 50%, 75% and maximum recirculation flow. Lanyard potentiometers and strain gages recorded vibration / strain data which were processed through the ERIS computer.
Statistical Analysis and Time History Functions vere used to determine maximum zero to peak q
levels for comparison to Acceptance Criteria. All results were satisfactory. Vibration / strain levels at each step in the flow ramp were determined to be well below the Level 1 and 2 Acceptance Criteria.
90 i
STARTUP TEST RESULTS (CONT.)
STI-B21-033 and STI-P99-122 (Cont.)
Transient 2.
Vibration Reci_rculation One Pump Trip / Restart TSN-272 - 8.3 NSSS Transient Vibration / Strain.
STI-B21-033 Performance of this test required monitoring NSSS Main Steam and Recirculation piping for transient vibration /strein during the trip / restart of Recirculation Pump A.
The trip was performed from maximum core flow. Similar testing vill be performed on Pump B during TC 6.
Lanyard potentiometers and strain gages recorded vibration / strain data which vere processed through the ERIS computer. Statistical Analysis and Time History Functions 1
vere used to determine maximum zero to peak levels for comptri-l son to Acceptance Criteria. All results were satisfactory.
Vibration / strain levels for both the trip and restart were determined to be below the Level 1 and 2 Acceptance Criteria.
e Transient 3.
Vibration Recirculation Two-Pump Trip TSN-292 - 8.3 NSSS Transient Vibration / Strain STI-B21-033 Performance of this test required monitoring ESSS Main Steam and Recirculation piping for transient vibration strain during the two Recirculation Pump trip (downshift to elev speed). The trip was performed from maximum core flow.
Lanyard potentiometers and strain gages recorded vibration / strain data which vere processed through the ERIS computer.
Statistical Analysis and Time History Functions were used to determine maximum zero to peak levels for comparison to Acceptance Criteria. All results were satisfactory. Vibration / strain levels for the two pump trip were determined to be below the Level 1 and 2 Acceptance Criteria.
I 1
l 1
91 1
STARTUP TEST RESULTS (CONT.)
~STI-B21-033 and STI-P99-122 (Cont.)
Steady State 4.
Vibration 75% Steam Flov TSN-299 - 8.1 NSSS Steady State Vibration / Strain STI-B21-033 Performance of this test required monitoring NSSS Main Steam and i
Recirculation piping for steady state vibration / strain.during plant operation at 75% ( 5%) of rated steam flow. Lanyard potentiometers and strain gages recorded vibration / strain data which were processed through the ERIS computer.
Statistical Analysis and Time History Functions were used to determine maximum zero to peak levels for comparison to Acceptance Criteria. Vibration / strain levels at 71% (actual recorded) of rated steam flow were determined to be well below the Level 1 and 2 Acceptance Criteria.
Steady State 5.
Vibration 75% Reactor Power TSN-300 - 8.3 BOP Pipe Vibration - Power Plateau
~
STI-P99-122 Performance of this test required monitoring selected portions of B0P piping for steady state vibration during plant operation at 75% (25%) of rated reactor power. Lanyard potentiometers and accelerometers recorded data which were processed through the ERIS computer.
Statistical Analysis and Time History Functions were used to determine maximum zero to peak levels of displace-ment and' acceleration. As required, the Time Series Analysis Function was used to convert acceleration to displacement.
These values were used for comparison to Acceptance Criteria.
All test results were satisfactory with the exception of one accelerometer.
Review of the data indicated that the response was characteristic of a failed sensor. TER 300-1 vas issued to 1
l 92 i
STARTUP TEST RESULTS (CONT.)
STI-B21-033 and STI-P99-122 (Cont.)
document the sensor failure. Subsequent rework of the sensor during en unplanned outage revealed a broken moun*.ing stud which affixes the accelerometer to a mounting block strapped to the pipe. The sensor was repaired and will be tested during the scheduled 100% power test. With this single exception due to sensor failure, vibration levels on B0P piping at 73% power (actual recorded) vere determined to be within the Level 1 and 2 Acceptance Criteria.
4.21 STI-F41-034 Reactor Internals Vibration (TSN-217, 276, 281, 286, 289, 296, 310)
Seven, Internals Vibration tests were conducted during Test Conditions 3, 4, and 5.
These included vibration measurements along the 60% rod line (TC 3), steady-state measurements while in natural circulation (TC 3 and 4), high flov-low power (TC 5) and for single and two pump trip transients (TC 3).
Preliminary results indicate that all Acceptance Criteria vere satisfied with no operational restrictions due to unaccept-able flow induced vibration. Final results vill be included in a final report to be delivered to CEI after the completion of the Startup Test Program.
Acceptance Criteria Level 1 The peak stress intensity may exceed 10,000 psi (single amplitude) when the component is deformed in a manner corresponding to one of its normal or natural modes, but the fatigue usage factor must not exceed 1.0.
93
p STARTUP TEST RESULTS-(CONT.)
STI-F41-034 (Cont.)
f' Level 2 l
The peak stress intensity shall not exceed 10,000 psi (single amplitude) when'the component'is deformed in a manner corresponding to one of its normal or natural modes. This is the lov stress limit which is suitable for the design life of the reactor components.
Results Vibration amplitudes and frequencies were monitored during various power and flow configurations, transient and steady-state.
Sensors were mounted on the following equipment:
1.
Top of the shroud head, lateral acceleration (displacement).
2.
Top of.should, lateral displacement.
3.
Jet pump riser braces, bending and extension strains.
4.
Jet pump diffusers, bending strain.
5.
Control rod guide tubes, bending strain.
6.
Incore housings, bending strain.
7.
Core spray sparger piping, bending strain.
Vibration data vere collected during steady-state and transient conditions.
Steady state data vere collected along the 60% rod line at minimum FCV position, 64% flow, 90% flow, and maximum core flow.
Maximum core flow vas limited by the flow control valves opening to their maximum flow position and, depending on the power-flow conditions, varied between 108.9 H1b/hr to 112 H1b/hr, or 104.7% and 107.7% of rated core flow. The 94 C---___--__-__________________
STARTUP TEST RESULTS (CONT.)
STI-F41-034 (Cont.)
absolute maximum core flow recorded (112 M1b/hr) was achieved in con-junction with STI-B33-030E (cavitation interlock test) in the lov power high flow region of the power-flow operating map. Natural circulation data vere collected during TC 3 and 4.
During the natural circulation vibration recording for Test Condition 3, a reactor scram occurred approximately 4 minutes after entering natural circulation. The vibration engineer had a sufficient amount of data recorded on magnetic tape to perform the required analysis.
l Transient data vere collected during single recirculation pump trips and during the two pump downshift performed in Test Condition 3.
During the recirculation pump A trip, a flow control valve runback occurred. The trip data were collected by the vibration engineers, then the FCV's were placed in their pre-tripped positions and data recording continued. It was concluded that the data were satisfactory and that another trip of the A Recirculation Pump was not required.
For Internals Vibration testing conducted in Test Conditions 3, 4, and 5, all Level 1 or Leve) 2 criteria were satisfied. All data analysis conducted for these tests is preliminary and is based upon spectral density plots and time history plots. A complete analysis is performed by General Electric using the data recorded on magnetic tapes. A final report detailing the results from the Internals Vibration Testing Program vill be presented to CEI within 120 days of the end of the Startup Test Program.
l 4.22 STI-B33-035 Recirculation System Flow Calibration l
(TSN-232, 241, 242) j i
The purpose of this test is to perform a total calibration of the installed Recirculation Flow Instrumentation System at or near the 100%
rated core flow condition.
95 U
STARTUP TLST RESULTS (CONT.)
STI-B33-035 (Cont.)
Acceptance Criteria Level 1 None Level 2 1.
Jet pump flow instrumentation shall be adjusted such that the jet pump total flow recorder vill provide a correct core flow indication at rated conditions.
2.
The APRM flow-bias instrumentation shall be adjusted to function properly at rated conditions.
Pesults Core flow indication is one of the most important of all reactor para-meters in the BVR because of its inherent relationship to the control of reactor power.
For this reason, significant importance is placed on refining adjustments to the Recirculation Flow Instrumentation System such that accurate core flow indication is available, especially at the most critical reactor operating conditions. These conditions usually exist at the high flov end of each respective power rod line where the thermal hydraulic margins are at a minimum. Due to the inherent non-linearity of the Individual instrumentation, the total system calibration and adjust-ments are also performed at the "near rated" flow conditions. This test was performed several times at TC 3, with each successive attempt result-ing in coming slightly closer to meeting the Level 2 criteria.
Only one of the two Level 2 criteria could be satisfied and final resolution was postponed to TC 6 testing.
I i
I i
96
v, STARTUP TEST RESULTS (CONT.)
STI-B33-035 (Cont.)
In the course of performing this test, the actual core AP and actual core.
flow was analyzed to be slightly different from design prediction data.
This information does not affect the startup testing-in any way, nor pre-sent any unreviewed safety concerns. This is strictly an operational con-sideration, specifically in the "beyond rated core flow region" such as the " Maximum Extended Operating Domain" (ME0D) by possibly restricting the' maneuverability in these regions. A letter from General Electric (PY-GEN /
CEI-2704), dated June 4, 1987, documents this fact and is part of the original data for this test at TC 3.
This test was performed three times at TC 3.
The first attempt (TSN-232) resulted in gain adjustment fattors (GAFs) for APRMs and Core Flows to fall outside the respective error bands to satisfy the Level 2 criteria.
Adjustments were made to the loop flow summers and the test was repeated at a slightly different core flov and reactor power conditions (TSN-241).
j The adjustments appear to have over corrected the situation and the cri--
teria were again not met.
Further refinement was made to the loop flow summers and the test performed at rated core flow (TSN-242). This resulted in satisfactory GAF for cere flow but the APRM GAFs were still not acceptable. They ranged from 1.231 to 1.267 vith an overall average of the eight APRM GAFs being 1.244.
Coupled to the APRM set down factor of 0.8, this results in an average GAF of 0.9952, with a range of 0.9848 to 1.0136. The acceptance band is 1.00 to 1.02.
At this point, it was decided to postpone the resolution of this issue to TC 6, where the final gain adjustment to the total core flow would be made. The final exceptions for TSN-242 are documented in TER 242-1.
o 97
STARTUP TEST RESULTS (CONT.)
STI-B33-035 (Cont.)
Core Flow Calibration Results Parameter TSN-232 TSN-241 TSN-242 Core Flov 94%
90.4%
100%
Core Power 63%
52%
70%
Rx Pressure 950 psig 945 psig 968 psig Core AP 12.1 psid 16.3 psid 20 psid ERIS Data No Yes Yes Criteria met for Core Flov GAF No(1)
No( )
Yes APRM GAF No(1)
No(2)
No( )
(1) TER 232-2 issued to initiate adjustments to core flow instrumentation system, then retest.
(2) TER 241-1 issued to initiate second try at adjustments to core flow instrumentation, then retest.
(3) TER 242-1 issued to postpone satisfying APRM gains criteria to TC-6.
4.23 STI-G33-070 Reactor Vater Cleanup System (TSN-316)
The purposes of this test are to demonstrate during operation with the Recirculation Pumps secured that 1) adequate NPSH exists such that RVCU pumpr do not cavitate, and 2) the RVCU system vill prevent thermal stratification in the bottom head of the RPV.
I l
98 i
1
____________________J
STARTUP TEST RESULTS (CONT.)
STI-G33-070 (Cont.)
Acceptance Criteria Level 1 None Level 2 1.
In the " Hot Shutdown" mode (defined by the process flow diagram) the available punip NPSH shall not be less than 13 feet.
2.
Pump vibration shall not exceed 2 mils peak-to-peak measured in any direction.
Results This test was performed at TC 4 (natural circulation) to verify RVCU vill prevent stratification in the RPV when Reactor Recirculation pumps are secured. Also, since the RUCU pumps vill have lov NPSH during this startup test mode of operation, the test verifies that cavitation does not exist at the pump suction.
Data vere collected during normal RVCU system operation and again during maximum RPV drain flov operation. Vibration measurements were taken during the maximum drain flow period of time.
Level 2 Acceptance Criteria vere satisfactorily met.
99
)
STARTUP TEST RESULTS (CONT.)
P 4.24 STI-C95-099 ERIS (Emergency Response and Information System)
(TSN-245, 246 247)
ERIS testing conducted in Test Condition 3 consisted of two Plant Specific Constant Recalculation tests and one Validated Parameter Verification test. A Reactor Level Cons
- ant called CORE FL COMP FAC vas calculated in TSN-245, and two Core Flow Constants, JET PUMP K CAL COEF (1 to 4) and CORE FL CURSN CONST 1, were calculated in TSN-246. The single Parameter Validation test was on Reactor Level at Rated Conditions in TSN-247.
Acceptance Criteria Level 1
\\
Not Applicable
,s Level.2 1.
All ERIS validated data vill agree with actual plant data within 3%
(or rated).
2.
All ERIS validated data on the various BASIC ERIS displays (taken as near simultaneously as possible) vill agree with each other within a 2 sigma deviation.
1.
Reactor Level Constants (8.1.1)
Results The purpose of this test was to calculate a constant called CORE FL COMP FAC to input into the ERIS processors. This constant relates the expected deviation in Narrow Range Level and Vide Range Level as a function of core flov. This deviation is caused by the velocity head which the lover vide range instrument tap develops as core flow increases. When the nev i
100
j STARTUP TEST RESULTS (CONT.)
STI-C95-099 (Cont.)
calculated constant was input to the ERIS RTAD processors, the composed level point was much more consistent as can be seen on a copy of ERIS screen 051 attached.
Calculated CORE FL COMP FAC vas determined to be 16.0 inches.
e 2.
Core Flov-Constants (8.1.8)
Results This test was performed to update the ERIS JET PHP K CAL COEF'S and CORE FL CVRSN CONST 1 based on actual plant data versus the "best estimates" that vere originally input to the data bases. These constants relate double tap jet pump calibration coefficients to the calculated M-ratios from the jet pump calibration program JR-PUMP, and relate single tap jet pump flows to double tap jet pump flows.
Calculated JET PHP R CAL COEF:
1 0.1732
- 3 1
2 0.1745 0.1744 3
0.1722 4
CORE FL CURSN CONST 1 was calculated to equal 9.79.
s All analysis was satisfactory and the constants were entered, as required, into the ERIS processors.
4.
101 g4
v
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(
$s y
STARTUP TEST RESULTS (CONT.)
STI-C95-099 (Cont.)
3.
Reactor Level - Rated TC 3 (8.2.5)
Results The purpose of this test was to compare the calculated I.RIS validated reactor level parameters with the measured levels at rated cors. flow. The comparison vould verify processor algorithms, plant specific constants, and data bases have been correctly set up and inst.nlled.
. i.
ERIS reactor water level data was verified to be acceptable with the
,g exception of the "ERIS average density compensated level" for vide range instrumentation. TER 247-1 vas issued to track the resolution of this discrepancy which was determined to be minor with no corrective action required.
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9 STARTUP TEST RESULTS (CONT.)
I 4.25 STI-P42-114 Emergency C,1,osed Coeling System Retests (TSN-235, 236)
These were retests per PORC tetion Item #87-109 06, (TER 162-1) for Loop "A", and PORC Action Item 87-109-07, (TER 166-2) ror Loop "B".
Parameters h
.for which Level 2 Acceptance Critaria failed during TC 1 vere retested.
l The parameters that failed durinF TC 1 were: Control Complex Chillers "A"
& "B" chilled water outlet temperature were 3 degrees higher than the Acceptance Criteria, and the ECC pump area ambient air temperature was several degrees lover than the Acceptance Criteria.
Acceptance Criteria for Retest Level 1 None Level 2 1.
The Control Complex Chillers (OP47-B001A & OP47-B001B) are capable of t
maintaining a chilled vater outlet temperature of 45'F or less.
2.
The Emergency Closed Cooling Areas Cooling Air Handling Units (OM28-B001B and OM28-B001B) are capable of maintaining the temperatures in the areas containing the ECC Pumps and Heat Exchangers within the required temperature limits: Minimum 81*F, Maximum 89*F.
Results ECC Systems - Loop "A" and Loop "B" During these retests, the Control Complex Chillers "A" and "B" outlet temperatures were lowered, being within the Level 2 Acceptance Criteria band, by adjusting the chiller's outlet temperature thermostat. The ECC Loops "A" and "B" proved they could maintain this lover temperature.
104
_________A
- I 1
STARTUP TEST RESULTS (CONT.)
STI-P42-ll4 (Cont.)
ECC pump area ambient air temperature again failed its Level 2 criteria with an area reading of 68.8'F for Loop "A",
and 70.7'F for Loop "B" TER's 235-1 and 236-1 vere written. These test exceptions were found acceptable by engineering. Their evaluation of'the below anticipated normal opet-ating minimum temperature was that the lov building temperature indicates a better than expected environment for plant equipment. In addition, it should be noted that the temperature does not violate the minimum building temperature of 60*F min.
4.26 STI-T23-123 Concrete Temperature Survey at High Power (TSN-243)
The purpose of this test is to demonstrate the ability of natural heat transfer to cool the concrete surrounding selected pipe penetrations.
Acceptance Criteria Level 1 Exterior Dryvell and Shield Building concrete temperatures at selected penetrations shall not exceed a temperature of 200'F minus loop accuracy.
Results Due to the high radiation fields present in the Steam Tunnel, remote monitoring was performed by attaching thermocouple to the concrete and routing the thermocouple vire to lov radiation areas.
Concrete temperature data was collected from near the Main Steam, Feed-water, and Reactor Vater Cleanup penetrations.
The maxiuum allovable concrete temperature was determined to be 195'F based on a 5'F maxiinum thermocouple loop-digital thermometer error. The following table lists the maximum temperatures recorded:
105 i
L___1__________________
J
STARTUP TEST RESULTS (CONT.)
STI-T23-123 (Cont.)
Maximum Recorded Temperature ('F)
Location Dryvell Shield Bldg Main Steam 119.2 169.1 Feedvater 119.6 125.9 Reactor Vater Cleanup 114.0 143.5 The maximum recorded temperature was 25.9'F below the Level 1 analysis limit thus satisfying all criteria.
4.27 STI-N22-126 Main, Reheat Extraction, and Miscellaneous Drains (TSN-237, 238)
The pu,rposes of these tests are:
1.
To demonstrate that the First (INBD) MSIV Before Seat Drain, Second (OTBD) MSIV Before Seat Drain and Main Steam Normal Drains are operating properly with steam flov to the Main Turbine Generator at l
45% of design flev.
2.
To demonstrate the Shutoff Valve Before Seat Drain and Second (OTBD)
MSIV Before Seat Drain closings at 50% Main Steam flow to the Main Turbine Generator during unit startup.
Acceptance Criteria Level 1 None l
l 106 I
j
i STARTUP TEST RESULTS (CONT.)
STI-N22-126 (Cont.)
Level 2 The steam line drain temperatures for the following drain lines are at 6
6 greater than 200'F at 40% to 50% (6.161 x 10 to 7.701 x 10 lb/hr) Main Steam flov indicating proper operation of the associated drain line:
(8.1) a.
1B21-F033, INBD MSIV BEFORE SEAT NORM DRN b.
1B21-F069, OTBD MSIV BEFORE SEAT NORM DRN c.
1B21-F071, MSL LOV POINT NORMAL DRN 0
The following valves close at !9% to 51% main steam flov (7.547 x 10 and 6
7.B55 x 10 lb/hr) shutting off drain systems to conserve cycle steam:
(8.2) a.
1B21-F069, OTBD MSIV BEFORE SEAT NORM DRN b.
1N22-F450, SHUT 0FF VLV BEFORE SEAT NORM DRN VLV Results 1.
Steam Line Drain Temperatures (TSN-237)
Vith the reactor operating at 49% (APRM-E) and an approximate steam flow of 45%, steauline drain temperature data vere obtained to verify that they exceed 200*F, it.dicating sufficient flows through these drain lines. Temperatures were recorded for the following drain lines:
Inboard MSIV Before Seat Normal Drain Outboard MSIV Before Seat Normal Drain Main Steam Line A Lov Point Normal Drain i
Main Steam Line B Low Point Normal Drain Main Steam Line C Lov Point Normal Drain Main Steam Line D Lov Point Normal Drain 107 J
STARTUP TEST RESULTS (CONT.)
STI-N22-126 (Cont.)
Temperatures for all drain lines were greater than or equal to 540'F and, therefore, the Acceptance Criteria vere satisfied.
2.
Steam Drainline Valve Closure (TSN-238)
This test verified auto closure of the Outboard MSIV Before Seat Normal Drain Valve (1B21-F069) and the Shutoff Valve Before Seat Normal Drain Valve (1N22-F450) at 50 i 1% rated steam flow. This test was performed using Turbine Steam Flov (based on First Stage Turbine Pressure) to determine steam flow at time of valve closure.
As indicated by Turbine Steam Flow, the valves closed at greater than 51% and a test exception was initiated. Due to inaccuracies in determining steam flow based on First Stage Turbine Pressure and the fact that the closure signals come off the individual steam line flow i
transmitters, the test data was reevaluated. The reevaluation showed I
that the sum of the individual steam line flows at the time of valve closure was 7.6074 M1b/hr or 49.4% satisfying the Acceptance Criteria of 50 1 1%.
4.28 STI-N33-129 Steam Seal (TSN-266) l This test gathered steady state data with the Main Steam System supplying the Steam Seal Evaporator (SSE), and also verified the auto transfer to the Extraction Steam Supply.
Acceptance Criteria Level 1 1.
With the Main Turbine increasing load, Extraction Steam Supply valves, IN31-F035, EXST TO ST SEALS NON RTN CHK VLV, and 1N33-F150, 108
STARTUP TEST RESULTS (CONT.)
STI-N33-129 (Cont.)
EXST TO ST SEALS NON RTN CHK VLV, automatically opened at 60% (t10%)'
turbine load.
2.
'The Steam Seal Header temperature is maintained greater than or equal to 265'F When the SSE is supplied heating steam from the Main Steam System and the Extraction Steam System.
Results Criterion 1 was satisfied when the transfer from Main Steam to Extraction Steam occurred at 60% turbine load. The transfer was verified by observ-ing the evaporator shell and tube side pressure controller outputs.
Critorion 2 was not satisfied. Measured temperatures ranged from 197'F to 207'F.
Upon further evaluation it was determined that the Acceptance Criteria was too high, since the point of measurement is far downstream of the evaporator. The TER resolution was " acceptable as-is."
The-criteria is planned to be revised before this test is run in TC 6.
4.29 STI-R63-133 Mose Parts Monitoring System (TSN-218, 219, 220, 303, 304, 315)
The Loose Parts Monitoring System (LPMS) was successfully used to collect steady state baseline data at various reactor powers and core flow during Test Condition 3 (TC 3), Test Condition 4 (TC 4), and Test Condition 5 (TC 5).
109
STARTUP TEST RESULTS (CONT.1 STI-R63-133 (Cont.)
Acceptance Criteria Level 1 None Level 2 Initial baseline data was obtained for steady state conditions established for the appropriate test conditions TC 3, TC 4, or TC 5.
Results l
For TC 3, data was collected for three different sets of plant conditions,
- 1) 50% power and 68% core flow, 2) 65% power and 100% core flow, and 1
- 3) 61% power and maximum core flow. At all times the generator was synchronized to the grid and the Reactor Recirculation pumps were on fast speed.
For TC 4, data was collected at 45% power with both Reactor Recirculation l
pumps tripped off (natural circulation), and the generator was synchronized.
I l
For TC 5, data was collected for two different sets of plant conditions,
- 1) 63% power and 56% core flov, 2) 77% power and 65% core flov. At all times the generator was synchronized to the grid and the Reactor Recirculation pumps were on fast speed.
All twelve vibration and loose parts channels for the reactor vere monitored for this test. The baseline data was collected on three cassette tapes lasting approximately 11 minutes each. All baseline data was collected satisfactorily with the noise plots showing the expected characteristic vaveform distribution.
4 110
l.
SECTION 5 ATTACHMENTS l
111
[
)
Startup Test Performance Index j
1 Test Serial Number 1 to 316 il Test Serial No.
STI No. - Section STI Title (Section)
Pre-Test Condition OV 001 D21-002-8.1 General Survey Performance 002 D21-002-8.3 Transfer Tube Survey 003 P35-001-8.1 Chemistry Data Pre-Fuel Load Test Condition Open Vessel 004 OV-200-8.1 Open Vessel Testing 4
005 C11-005-8.1 CR-Insert /Vithdrav Timing e
006 C11-055-8.2 CR-Friction Testing 007 J11-003-8.1 Fuel Loading 008 C11-005-8.3 Single Rod Scram Testing 009 C95-099-8.4.1
'Seram Timing Verification 010 C51-006-8.1 SRM Functional Tasting 011 J11-033-8.3 Installation of CF-252 Neutron Sources 012 J11-003-8.2 Verification of Core Loading 013 G42-119-8.1 SPCU Performance Test 014 C95-099-8.2.12 Dryvell Temperature - Cold 015 B33-029A-8.1 Flow Control Valve Stroking 016 G42-119-8.1 SPCU Performance Test (Retest) 017 C95-009-8.4.1 Scram Timing Verification (Retest) 018 C11-005-8.3 Single Rod Scram Timing (Retest) j 019 J11-004-8.1 Full Core Shutdovn Margin
)
020 C51-010-8.1 SRM-IRM Overlap 021 D21-022-8.1 General Survey Performance - Post Fuel Load 112
, (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition Open Vessel (Cont.)
022 C11-005-8.4 Ganged Rod Timing 023 P35-001-8.2 Chemistry Data Pre-Heatui.
024 C91-013-8.1 TIP Alignment After TIP System Installation 025 C91-013-8.5 DSTC-Pre-Startup Operation l
l Test Condition Heatup 026 HU-201-8.1 Heatup Plateau Testing 027 B21-033-8.1 NSSS Steady State Vibration / Strain Measurements 1
028 B21-033-8.3 NSSS Transient Vibration / Strain Measurements 029 N33-129-8.4 Steam Seal Flovpath Verification 030 F41-034-8.1 Pre-Nuclear Heatup Flov Test 031 P44-116-8.2 TBCC System-Hech. Vac. Pump Data 032 B21-016B-8.2 Shutdown Range Data j
033 B21-017-8.1 NSSS Piping Expansion, Thermal Cycle No 1 034 B21-033-8.2 NSSS Visual Vibration
)
035 P99-122-8.1 BOP Piping Test - Reactor Heatup 036 B21-033-8.3 NSSS Transient Vibration / Strain - SRV Functionals 037 P99-122-8.2 BOP Piping Test - Transients 038 C11-005-8.6 CRD Hydraulics Test
)
113 i
_ _ - _ - _ _ _ - _ _ _ _ _ _ _ _ _ - _ - - - _ _ _ _. (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition Heatup (Cont.)
039 C51-010-8.1 SRM and IRH Overlap 040 C51-006-8.2 SRM Non-Saturation 041 C51-010-8.2 IRM Range Correlation Adjustment 042 C95-099-8.2.1 Reactor Pressure - Lov 043 E51-014-8.1 RCIC Discharge to the CST 044 C95-099-8.2.3 RPV/ Press /2D Plot / Limit Tag (Low Press) 045 B21-026-8.1 SRV Functional Test 046 C95-099-8.3.4 SRV Test - ERIS 047 N33-129-8.1 Steam Seal Evaporator 048 C51-012-8.1 Constant Heatup APRM Calibration 049 E51-014-8.1 RCIC Discharge to CST 050 C11-005-8,5 Scram Timing of Selected Rods -
600 psig 051 N62-130-8.1 SJAE Lov Steam Flow 052 N64-074-8.1 Off Gas System Test - Startup 053 C11-005-8.5 Scram Timing of Selected Rods -
800 psig 054 P99-122-8.2 B0P Piping Test-Transient RCIC Hot Quick Start 055 P99-122-8.1 B0P Piping Test-Reactor HU-RCIC 2 Hr. Run I
056 B21-033-8.1 NSSS Steady State Vibration / Strain-RCIC 2 Hr. Run 057 D21-002-8.1 General Survey Performance 058 P35-001-8.3 Chemistry Data Heatup Tests 059 C11-005-8.2 Friction Testing l
114
__ (Cont.)
Startup Test Performance Index (Cont.)
Test i
Serial No.
STI No. - Section STI Title (Section)
Test Condition Heatup (Cont.)
060 G33-070-8.1 RVCU Normal Mode 061 B21-016B-8.1 Reference Leg Temperature Meas.
062 T23-123-8.1 Concrete Temperature Survey at Low Power 063 G33-070-8.2 Rx Ve'ssel Bot tom Head Drain Flow Ind.,
Cal. Check
- 064 3
065 C51-010-8.3 IRM-APRM Overlap 066 C51-011-8.1 LPRM Verification 067 E51-014-8.1 RCIC Disch. to CST (Rated Press) 068 E51-014-8.2 RCIC 2 Hr. Run 069 C11-005-8.3 Single Rod Scram Timing @ > 950 psig 070 B21-025A-8.1 MSIV Function Test 071 C95-099-8.4.1 Scram Timing Verification - Single Rod 072 C51-012-8.1 Constant Heatup APRM Calibration
- 076
- 077
- 078 079 N64-074-8.1 Off-Gas System - Normal Ops
- 080 081 R63-133-8.1 Loose Parts Monitoring System Data 082 C11-005-8.3 Single Rod Scram Timing (Retest) 115
_ _ _ - _ _ - _ _ _ _ _ - _ (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition Heatup (Cont.)
083 B21-017-8.2 NSSS Piping Expansion - Thermal Cycle #2 084 P99-122-8.1 B0P Piping Test - Rx Heatup (Retest) 085 C51-010-8.1 SRM/IRM Overlap (Retest) 086 C95-099-8.2.1 Rx Press - Lov (Retest) 087 C95-099-8.2.3 RPV Press /2D Plot / Limit Tag - Low Press (Retest) 088-C91-013-8.2 TIP Alignment @ Rx Startup (Retest) 089 C11-005-8.2 Friction Testing (Retest of 10-15) 090 C95-099-8.2.2 Reactor Press - Rated 091 C95-099-8.2.3 RPV Press /2D Plot / Limit Tag - Rated Press.
092 G33-070-8.3 RUCU Blovdown Mode l
093 C95-099-8.2.7 Reactor Power - Lov 094 C95-099-8.2.16 Containment Temperature - Normal Test Condition 1 095 LP-202-8.1 Test Condition 1 Testing 096 B21-017-8.3 NSSS Piping Expansion Thermal Cycle #3 097 P99-122-8.1 B0P Piping Test - Rx Heatup (Retest) 098 C51-012-8.1 Constant HU APRM Calibration (Retest) 099 C95-099-8.2.6 Reactor Level - Limit Tags 100 C95-099-8.1.3 Reactor Vessel Temperature Constants at TC 1 101 C95-099-8.2.11 Dryve11 Pressure l
i l
l 116 i
_-_-______---_-__--_a
- - _ _ _ _ _ _ _ _ _ _ _ _ _ __, (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition 1 (Cont.)
102 C95-099-8.2.15 Containment Pressure 103 C95-099-8.2.13 Dryvell Temperature - Normal 104 C95-099-8.2.17 Suppression Pool Temperature - Normal 105 C95-099-8.2.18 Suppression Pool Level 106 N64-074-8.1 Off-Gas System Test 1
107 C51-011-8.1 LPRM Verification (TER Retest) 108 C51-011-8.3 LPRM Calibration v/o Process Computer 109 N27-120-8.1 FV Data - Lov Power 110 T23-123-8.2 Concrete Temperature @ High Power 111 N27-023A-8.3 (RFP A)
FV Startup Rx Level Controller Steps j
- 112 113 R63-133-8.1 LPMS Baseline Data 114 N27-023A-8.3 FV Startup Rx Level Controller (MFP) 115 D21-002-8.1 General Survey Performance 116 N27-023A-8.3 FV Startup Rx Level Controller (RFP-B) l
- 117 l
118 N27-023A-8.1 (MFP)
FV Low Flov Valve Test (MPP) l 119 N27-023A-8.1 (RFP-A)
FV Lov Flov Valve Test (RFP-A) 120 N27-023A-8.1 (RFP-B)
FV Lov Flov Valve Test (RFP-B) 121 P44-116-8.3 TBCC System - Motor Driven Feed Pump 122 G33-070-8.3 RVCU Blovdown Mode 123 P44-116-8.3 TBCC System-MDFP Data (Retest) 124 B21-033-8.1 NSSS Steady State Vibration / Strain 125 P99-122-8.3 B0P Piping Test-Power Plateaus l
126 C91-013-8.3 LPRM Cal. & TIP Plotter Adjustment 127 C91-019-8.1 Core Thermal Power Determination i
1 117
- -____. _ (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition 1 (Cont.)
128 C91-019-8.2 Core Thermal Limits Determination 129 P35-001-8.4 Chemistry Data & Power Ascension 130 M99-100-8.2 Integrated HVAC Data 131 C91-013-8.6 DSTC-Data Init. by 0D-15 132 C91-013-8.7 DSTC-Plant Sensor Checks 133 C91-013-8.8 DSTC-Verif. of Prog. En. by OD-15 134 C91-013-8.9 DSTC-LPRM Calibration 135 C91-013-8.10 DSTC-Puver Dist. & Th. Limits 136 C91-013-8.11 DSTC-Daily & Monthly Logs 137 D21-002-8.2 RVCU Resin Transfer Survey 138 C85-022-8.3 Press. Regulator Test v/ Bypass Valves 139 C85-022-8.5 Press. Regulator Deadband 140 M99-100-8.1 Computer Room Data 141 C95-099-8.3.1 Event Target Ver.-Div. 1 Diesel Gen.
142 C91-013-8.8 DSTC-Verif. of Prog. En. by OD-15 143 C91-013-8.12 DSTC-0D-18 Verification 144 C91-013-8.13 DSTC-0D-2 Verification 145 C91-013-8.29 BOP Calculations 146 C95-099-8.3.2 Div. 2 Diesel Event Markers 147 N27-023A-8,5 FV Master Ccatroller RFP A 148 N27-023A-8,5 FV Master Controller RFP B 149 G42-119-8.1 SPCU Performance Test 150 B21-026-8.2 SRV Flov Test 151 E12-071-8.2 Supp. Pool Cooling Loop "A" 152 E12-071-8.2 Supp. Pool Cooling Loop "B" 153 B21-033-8.3 NSSS Pip Vib.-SRV Manual Test 118
_ - _ _ - _ _ _ _ - _, (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition 1 (Cont.)
154 P99.-122-8.2 B0P Pipe-Transient SRV Manual Test 155 C51-012-8.2 APRM Calibration at High Power 156 P99-122-8.4 B0P Piping Test Steam Condensing 157 C95-099-8.3.3 DIV. 3 Diesel Generetor (Event Marker) 158 M99-134-8.1 RHR A Pump Room Cooler Data 159 M99-134-8.3 RCIC Pump Room Cooler Data 160 P45-117-8.1 ESV Syster,. - Loop A 161 M99-134-8.6 LPCS Pump Room Cooler Data 162 P42-114-8.1 ECC System - Loop A 163 E12-071-8.1 Steam Condensing Capacity & Stability 164 M99-134-8.4 RHR C Pump Room Cooler Data 165 P45-117-8.2 ESV System - Loop B 166 P42-114-8.2 ECC System - Loop B 167 M99-134-8.2 RHR B Pump Room Cooler Data 168 M99-134-8,5 HPCS Pump Room Cooler Data 169 C61-028-8.1 Shutdown Prom Outside Control Room i
170 C61-028-8.2 Cooldown Prom Outside Control Room
)
l i
171 C11-005-8.7 Scram Timing During Planned Scram j
172 C95-00?-8.3.5 Scram (B-1) Test 173 C95-099-8.4.2 Scram Timing During Planned Scram 174 B21-033-8.3 NSSS Pipe Vibration-Remote S/D 175 B33-029A-8.2 Position Loop & Deadband Test @ TC 1 176 P99-122-8.2 BOP Piping Test-Transient Remote S/D I
119
__-____a
-- (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition 2 177 MP-203-8.1 Test Condition 2 Testing 178 P99-122-8.1-B0P Exp. Cycle #4 (Retest) 179 C51-010-8.3 IRM-APRM Overlap
- 180
- 181 182 N27-C23A-8.6 FV. Control Linearity (MFP) 183 R63-133-8.1 LPMS Baseline Data 184 P99-122-8.2 B0P Piping Test - Transients - RCIC Trip / Restart 185 E51-014-8.3 RCIC Discharge to Vessel-(Rated) 186 B21-033-8.1 NSSS SS Vib/ Strain - Rx @ 50% Steam Flow 187 P99-122-8.3-B0P Pipe Vib. - Power Plateau -
Rx 0 50% Power 188 N27-023A-8.4 FV Pump Open Loop Steps (RFPA) 189 N27-023A-8.4 FV Pump Open Loop Steps (RFPB) 190 N27-023A-8.4 FV Pump Open Loop Steps (MFP) 191 N27-023A-8.3 FV S/U Rx Lvl Controller Steps (RFPA) 192 N27-023A-8.3 FV S/U Rx Lvl Controller Steps (RFPB) 193 N27-023A-8.3 FV S/U Rx Lvl Controller Steps (MFP)
(.
194 C91-019-8.1 Core Thermal Pover Determination l
195 C91-019-8.2 Core Thermal Limits Determination 196 C51-012-8.2 APRM Calibration High Power 197 P35-001-8.4 Chemistry Data Pover Ascension 120 e
i
! (Cont.')
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section.
STI Title (Section)
Test Condition 2 (Cont.)
l 198 E51-014-8.4 RCIC Cold Quick Start to Vsl - 1st Run 199 E51-014-8.5 Operation of RCIC'from Remote Shutdown Panel
- 200
- 201 l
202 C85-022-8.1 Pressure Reg Test with Control Valves L
203 C85-022-8.3 Pressure Reg Test with Bypass Valves 204 N27-023A-8,5 FV Haster Rx Level Controller Steps -
'RFPA & B 205 N27-023A-8,5 FV Master Rx Level Controller Steps -
HFP & RFPA 206 N27-023A-8,5 FV Haster Rx Level Controller Steps -
HFP & RFPB 207 B33-030E-8.1 FCV Cavitation Interlock Test 208 R43-031-8.1 Loss of Turbine - Generator & Offsite Power 209 B21-027-8.1 Generator Load Reject within Bypass l
l Valve Capacity i
Test Condition 3 210 MP-203-8.2 Test Condition 3 Teating 211 B21-033-8.1 NSSS Steady State Vibration / Strain 212 E51-014-8.4 RCIC Cold Quick Start to Vessel (Rated) 213 C85-022-8.4 Pressure Regulator Linearity 4
121
___-____ _______ (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition 3 (Cont.)
214 B21-025A-8.1 MSIV Closure Time Measurements 215 B21-025A-8.2 Full Closure of the Fastest MSIV at 55%
Power 216 B33-029B-8.1 Linearity Data Collection 217 F41-034-8.2 Balanced Flow Vibration Test 218 R63-133-8.1 LPMS Baseline Data (Max Core Plov) 219 R63-133-8.1 LPMS Baseline Data (50% Pover) 220 R63-133-8.1 LPMS Baseline Data (65% Pover)
C51-011-8.2 LPMS Calibration with Process Computer 221 l
222 C51-012-8.2 APRM Calibration at High Power 223 C91-013-8.7 DSTC - Plant Sensor Checks 224 C91-013-8.10 DSTC - Power Distribution and Thermal Limits Calculation 225 C91-013-8.14 DSTC - P1 Symmetry Check 226 C91-013-8.15 DSTC - OD-12 Verification 227 C91-013-8.16 DSTC - Computer Initialization Check on F1/0D Phase I 228 C91-013-8.17 DSTC - Computer Initialization Check on F1/0D Phase II 229 C91-013-8.19 DSTC - Verification of Validity of BLIP Correlation 230 C91-013-8.20 DSTC - Simultaneous P1/0D-2 Check 231 C91-013-8.28 DSTC - P5 Testing 232 B33-035-8.1 Recire Core Flow Calibration 233 D21-002-8.1 General Survey Performance 4
i i
122 i
i
1 4
l (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section) k Test Condition 3 (Cont.)
234 E51-014-8.7 RCIC Surveillance Baseline Test 235 P42-114-8.1 ECC System - Loop A (Retest) 236 P42-114-8.2 ECC System - Loop B (Retest) 237 N22-126-8.1 Steam Line Drain Temperatures - 45%
Steam Flov 238 N22-126-8.2 Steam Drain Line Valve Closure 239 N27-023A-8.6 FV Control Linearity - RFP A 240 N27-023A-8.6 FV Control Linearity - RFP B 241 B33-035-8.1 Recirc Core Flow Calibration (Retest) 242 B33-035-8.1 Recirc Core Flow Calibration (Retest) 243 T23-123-8.2 Concrete Temperature Survey at High Power j
244 B21-016A-8.2 Drain Line Thermocouple Data 245 C95-099-8.1.1 Reactor Level Constants 246 C95-099-8.1.8 Core Flow Constant - JET PMP K CAL COEF and Core FL CVRSN CONST 1 247 C95-099-8.2 5 Reactor Level - Rated 248 N27-023A-8.4 FV Pump Steps (RFP A) 249 N27-023A-8.4 FV Pump Steps (RFP B) 250 N27-023A-8.4 FV Pump Steps (MFP) 251 P35-001-8.4 Chemistry Data Power Ascension 252 C91-019-8.1 Core Thermal Power (CTP) Determination 253 C91-019-8.2 Core Thermal Limits Determination l
254 N27-023A-8.3 FV Startup Controller Steps (RFP A) i I
123
J (Cont.)
Startup Test Performance Index (Cont.)
Test Serial No.
STI No. - Section STI Title (Section)
I Test Condition 3 (Cont.)
255 N27-023A-8.3 FV Startup Controller Steps (RFP B) 256 N27-023A-8.3 FV Startup Controller Steps (MFP) i 257 N27-023A-8,5 FV Master Controller Steps (RFP A) j 258 N27-023A-8,5 FV Master Controller Steps (RFP B) 259 N27-023A-8.5 FW Master Controller Steps (RFP A & B) 260 N27-023A-8,5 FW Master Controller Steps (MFP &
RFP A) 261 N27-023A-8.5 FV Haster Controller Steps (MFP &
RFP B) 262 C85-022-8.1 Pressure Regulator Test with Control Valves 263 C85-022-8.2 Pressure Regulator Test with Bypass Valves Incipient 264 B33-029B-8.1 Linearity Data Collection (Retest) 265 B33-030C-8.1 Recirc Two Pump Data 266 N33-129-8.2 Extraction Steam Supply 267 B33-029A-8.3 Position Loop Steps (50% Flov)
(
268 B33-029A-8.3 Position Loop Steps (80% Flov) 269 B33-029A-8.3 Position Loop Steps (100% Flov) 270 B33-029A-8.4 Scram Avoidance Test 271 B33-029B-8.2 Flow Loop Testing 272 B21-033-8.3 NSSS Transient Vibration / Strain -
1 Pump Trip 273 B21-027-8.2 Bypass Valve Capacity Measurement 274 B33-029B-8.3 Flux Loop Testing 275 B33-030A-8.1 Recirculation One Pump Trip and Restart 124
q I (Cont.)
{
Startup Test Performance Index (Cont.)
f i
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition 3 (Cont.)
276 F41-034-8.3 Vibration Measurements During STI-B33-030A 277 B33-030C-8.2 Recirc One Pump Data 278 B33-030E-8.3 Single Loop Pump Cavitation Test 279 B21-016A-8.3 One Pump Trip Temperature Data 280 C91-013-8.7 DSTC - Plant Sensor Checks (Retest) 281 F41-034-8.4 Vibration Measurements During the Trip One Recirculation Pump
- 282 283 B33-030E-8.3 Single Loop Pump Cavitation Test 284 B33-030C-8.2 Recirc One Pump Data 285 B33<030B-8.1 E0C-RPT Trip of Two Pumps 286 F41-034-8.5 Vibration Measurements During STI-B33-030B 287 D21-016A-8.4 Two Pump Trip Temperature Data
- 288 289 F41-034-8.8 Vibration Measurements During Natural l
Circulation
- 290
2 Pump Trip l
125 l
l
i l
l
. (Cont.}'
)
I Startup Test Performance Index (Cont.)
l l
Test Serial No.
STI No. - Section STI Title (Section)
Test Condition 5 293 HP-204-8.1 Test Condition 5 Testing 294 E51-014-8.7 RCIC Surveillance Baseline Test 295 B33-030E-8.2 Pump Cavitation Interlock Test 296 F41-034-8.7 Vibration Measurements During High Flov, Lov Power Conditions 297 P35-001-8.4 Chemistry Data Power Ascension 298 E51-014-8.6 RCIC Discharge to the Vessel (150 psig) 299 B21-033-8.1 NSSS Steady State Vibration / Strain -
75% Steam Flow 300 P99-122-8.3 BOP Piping Test - Power Plateaus -
75% Rx Power 301 C51-012-8.2 APRM Calibration at High Power 302 N27-023D-8.1 Low Pover RFP Data 303 R63-133-8.1 LPMS Baseline Data - 65% CTP 30t.
R63-133-8.1 LPMS Baseline Data - 75% CTP 305 C91-013-8.7 DSTC - Plant Sensor Checks 306 N27-023A-8.3 FV Startup Controller Steps (RFP B) 307 N27-023A-8.3 FV Startup Controller Steps (RFP B) 308 N27-023A-8,5 FW Startup controller Steps (RFP A & B)
Test Condition 4 l
309 HP-204-8.2 Test Condition 4 Testing 310 F41-034-8.8 Vibration Measurements During Natural Circulation 311 B33-030C-8.3 Natural Circulation Data 312 B21-016A-8.4 Two Pump Trip Temperature Data 126
__.-_____m i
I (Cont.)
j Startup Test Performance'Index (Cont.).
Test Serial No.
STI No. - Section-STI Title (Section) 1 Test Condition 4 (Cont.)
313 C91-019-8.1 Core Thermal Power-(CTP) Determination 314 C91-019-8.2 Core Thermal Limits Determination 315 R63-133-8.1 LPMS Baseline Data - Natural Circulation 316 G33-070-8.4 RUCU Hot Shutdown Mode
- Void
- Cancelled
)
127 - LAST
=- '
i-r
I THE CLEVEL AND ELECT.RIC.lLLUMIN ATING COM P ANY P O. BOX $000 - CLEVELAND, OHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BloG - 55 PUBLICSQUARE 1
l Serving The Best Location in the Nation l
l L
MURRAY R. EDELMAN en e,ce mesorwr August 25, 1987 Nuc u An PY-CEI/NRR-0706 L i
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Perry Nuclear Power Plant Docket No. 50-440 Supplemental Startup Report
( Supplement //2)
Dear Sir:
Attached is the second Supplemental Startup Report for Perry Unit I covering the time period from May 16, 1987 through June 27, 1987, inclusive. This report is submitted in I
accordance with Regulatory Guide 1.16 and Perry Technical f
Specifications, Section 6.9.
Please feel free to contact me if you have any questions.
Very truly yours,
[
M Murray R..Edelman Senior Vice President Nuclear Group MRE: cab Attachment cc:
T. Colburn K. Connaughton USNRC Region III Director, Of fice of Resource Management
[S.
S
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