ML20245H942
| ML20245H942 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/15/1989 |
| From: | Conway J, Michael Jones, Pao T NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17055E542 | List: |
| References | |
| NUDOCS 8903060102 | |
| Download: ML20245H942 (137) | |
Text
_. .
1 NIME MILE POINT UNIT 2 Supplemental Final Startup Report I. Report Review and. Acceptance Sg sture Date Title Written by:- W I//8/N Shift Test Supervisor
-Verified by: 4//d/89' Shift Test Engineer
. Approved by: ,2 /3 /diSite Operations Manager .
V.
Q Approved by: 7h 42 //3/#9 Power Ascension Manager-6' Approved by: k g,1.b A /W /65 Technical Superintendent U. i u Approved by:
b O//h/k tation Superintendent Nine Mile Point 2 II. Supplemental Final Startup Report Approval The Supplemental Final Startup Report is Approved By S.O.R.C.
Meeting No. 79-/9 Date: 42 / /5 / f7 The Supplemental Final Startup Report is Approved By the General Superintendent.
Signature: Date: 2. / E8 f 5
- e:
8903060102 890221 DR ADOCK0500((gO .
Page 1 of 132 Supplemental Final Startup Report As documented on Licensee Event Report (LER) No.88-045, the core flow at Nine Mile Point 2 was calibrated incorrectly during startup testing, such that when the indicated flow was 100%, the actual core flow was approximately 104.5%. This error was caused by an input error on the plant specific data for the JRPUMP program. This data was used for Power Ascension Test Procedure No. N2-SUT-35-3 and N2-SUT-35-6 starting from November 6, 1987. Therefore, the core flow and jet pump loop flow test data from November 6, 1987, through warranty test was approximately 1.045 times greater than recorded in the Power
' Ascension Test procedures. The correction factor of 1.045 was calculated based on the corrected JRPUMP run and the final test data recorded in N2-SUT-35-6.
Due to the core flow and loop flow calibration error, all the SUT's performed on or af ter November 6,1987 were evaluated and classified into the following categories:
A. The Procedures are not affected by the increased core flow event, as the core flow and the loop jet pump flow were not recorded or used in the procedure. Therefore, no action is required for the procedures listed below:
N2-SUT-1-3 CHEMISTRY N2-SUT-76-3 ESF AREA COOLING N2-SUT-77-3 E0P PIPE VIBRATION N2-SUT-5-6 CONTROL ROD DRIVE SYSTEM N2-SUT-71-6 RESIDUAL HEAT REMOVAL N2-SUT-75-6 DRWELL COOLING SYSTEM N2-SUT-76-6 ESF AREA COOLING N2-SUT-78-6 BOP PIPE EXPANSION N2-SUT-81-6 DRYWELL PENETRATION COOLING N2-SUT-80 EMERGENCY RECIRCULATION VENTILATION B. The test results of the following procedures are not affected, as the core.
flow and/or the loop jet pump flow were recorded for information only.
Corrected data is provided in this supplemental report.
N2-SUT-2-3 RADIATION MEASUREMENTS N2-SUT-12-3 APRM CALIBRATION N2-SUT-13-3 PROCESS COMPUTER N2-SUT-23-3 FEEDWATER SYSTEM, N2-SUT-33-3 DRWELL PIPING VIBRATION N2-SUT-74-3 0FFGAS N2-SUT-1-5 CHEMISTRY N2-SUT-16-5 SELECTED PROC. TEMPS.
N2-SUT-23-5 FEEDWATER SYSTEM N2-SUT-24-5 TURBINE VALVE TESTING 1 N2-SUT-77-5 BOP PIPE VIBRATION
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Page 2 of 132 :
Supplemental Final Startup Report (Cont'd)
B. (Cont'd)
N2-SUT-2-6 RADIATION MEASUREMENTS N2-SUT-12-6 APRM CALIBRATION N2-SUT-13-6 PROCESS COMPUTER N2-SUT-18-6 TIP U.1 CERTAINTY N2-SUT-25-6 MSIV N2-SUT-74-6 OFFGAS N2-SUT-77-6 BOP PIPE VIBRATION C. The initial power-flow conditions for the performance of these tests were either directly specified in terms of core flow, or as the eod line to be utilized (in which case core flow was used as input). In either case, the test results are not affected. In all situations, the selection of'the initial test condition was not tied to the test results. The corrected core flow and test rodline data can be found in this supplemental report.
N2-SUT-11-3 LPRM CALIBRATION N2-SUT-16-3 SELECTED PROCESS TEMPERATURES AND WATER LEVEL MEASUREMENTS N2-SUT-33-5 DRYWELL PIPING VIBRATION N2-SUT-1-6 CHEMISTRY N2-SUT-11-6 LPRM CALIBRATION N2-SUT-27-6 TURBINE TRIP AND GENERATOR LOAD REJECTION N2-SUT-33-6 DRYWELL PIPING VIBRATION D. The core flow data were directly and/or indirectly used for determination of the initial test condition, test result analysis or acceptance criteria evaluation. These procedures have been analyzed again, and the results documented in this supplemental report.
N2-SUT-19-3 CORE PERFORMANCE N2-SUT-22-3 PRESSURE REGULATOR N2-SUT-29-3 REACTOR RECIRC FLOW CONTROL N2-SUT-30-3 REACTOR RECIRCULATION SYSTEM N2-SUT-79-3 RPV INTERNAL VIBRATION N2-SUT-12-5 APRM CALIBRATION N2-SUT-19-5 CORE PERFORMANCE N2-SUT-22-5 PRESSURE REGULATOR N2-SUT-30-5 REACTOR RECIRCULATION SYSTEM N2-SUT-16-6 SELECTED PROCESS TEMPERATURES AND WATER LEVEL MEASUREMENTS N2-SUT-19-6 CORE PERFORMANCE N2-SUT-22-6 PRESSURE REGULATOR N2-SUT-23-6 FEEDWATER SYSTEM N2-SUT-24-6 TURBINE VALVE TESTING N2-SUT-29-6 REACTOR RECIRC FLOW CONTROL N2-SUT-30-6 REACTOR RECIRCULATION SYSTEM .
N2-SUT-79-6 RPV INTERNALS VIBRATION N2-SUT-20-W WARRANTY RUN (STEAM PRODUCTION) 1 h
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Supplemental Final Startup Report (Cont'd)'
Those procedures documenting . the error (N2-SUT-35-3 and N2-SUT-35-6) will not be recalculated. The. core flow: calibration will be performed in accordance with station procedure N2-RPSTP-6.after the next plant:startup.-
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Page 4 of 132 i Supplemental Final Startup Report Procedure No: N2-SUT-2-3 Radiation Measurements Corrected Recorded '
Data Data l
Step 4.2.4"/ OD-3 (11-08-87 1108) 1 WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 107.230 1.045 112.055 = 103.28% -98.83%
. 108.500 MWT RATED MWT % POWER 2243.190 3323.000 67.50%
Rodline = % Power = 65.99% 68.06%
.3+.7*%WT CONCLUSION: INCREASED CORE- FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
103.28% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
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.. Supplemental Final Startup Report Procedure No: N2-SUT-11-3 LPRM Calibration Corrected Recorded Data Data Step 6.1.1./ OD-3 (11-08-87 1512)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr.
106.800 1.045 111.606 , 102.86%' 98.'43%
108.500 MWT RATED MWI % POWER 2200.380- 3323.000- 66.22%
Rodline = % Power' = 64.92% 66.95%
.3+.78%WT CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
102.86% CORE FLOW CAN BE ACCEPTED AS IS PEF. ATTACHMENT .1.
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4 Page 6 of 132 Supplemental Final Startup Report Procedure No: N2-SUT-12-3 APRM Calibration Corrected Recorded-Data Data Step 4.1.2 / OD-3 (11-08-87 1054)
! M1b/He M1b/Hr 107.700 1.045. 112.547 =- 103.73% 99.26%
108.500 MWT RATED MWT % POWER 2180.840 3323 65.63%
Rodline = '% Power = 63.96% 65.97%
.3+.7*%WT Step 6.1.1 I, Reactor Physics Surveillance Procedure No. N2-RPSP-1 / P - 1 j Step 7.1.1.2 WT (M1b/Hr) = 111.68 106.97 PCT WT = 102.93% 98.50%
Step 9.1.2 Core Flow: WT must be < or = 108.5 M1bs/Hr mass flow.
The corrected core flow exceeds the acceptance criteria of'the RPSP-1 but can be accepted as is based on Increased Core Flow analysis.
CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.' .
103.73% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1. j 1
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i Page 7 of 132 Supplemental Final Startup Report Procedure No: N2-SUT-13-3 Process Computer corrected Recorded Data Data Step 6.2.2 P-1 (01-16-88 0926) SEQ. NO. 5 WT FACTOR WT* FACTOR PCT WT M1b/He M1b/Hr 106.090 1.045 110.864 = 102.18% 97.78%
108.500 MWT RATED MWT % POWER 2452.000 3323.000 73.79%
Rodline =- % Power = 72.68% 74.95%
.3+.7*%WT' Step 6.2.5 P-1 (01-16-88 0938) SEQ. NO. 6 WT FACTOR WT* FACTOR PCT WT M1b/He M1b/Hr 107.270 1.045 112.097 = 103.32% 98.87%
108.500 MWT RATED MWT % POWER 2449.000 '3323.000 73.70%.
Rodline = % Power = 72.03% 74.29%-
.3+.7*%WT Step 6.3.1 P-1 (01-16-88 1048) SEQ. NO. 7 WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 107.150 1.045 111.972 = 103.20% 98.76%
108.500 MWT RATED MWT % POWER 2449.000 3323.000 73.70%
Rodline = % Power = 72.08% 74.35% -
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Pa8e 8 of 132 Supplemental Final Startup Report Procedure No: N2-SUT-13-3 Process Computer Corrected Recorded'
-Data. Data Step 6.4.1.3 P-1 (01-16-88 1605) . SEQ. NO. 8 WT FACTOR WT* FACTOR PCT WT-M1b/Hr M1b/He 107.070 1.045 111.888 = 103.12% 98.68%
108.500"
' MWT RATED MWT % POWER 2448.000 3323.000 73.67%
Rodline = % Power = 72.09% 74.35%
.3+.7*%WT Step 6.4.4.3 P-1 (01-16-88 2315) SEQ. NO. 9 WI FACTOR WT* FACTOR PCT WT M1b/He M1b/He 106.950 1.045 111.763 .. 103.01% 98.57%
108.500 MWT RATED MWT % POWER 2442.000 3323.000 73.49%
Rodline = % Power , 71,97% 74.23%
.3+.7*%WT Step 6.4.4.5 P-1 (01-16-88 2323) SEQ. NO. 10 WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 106.170 1.045 110.948 = 102.26% 97.85%' .
108.500 '
MWT RATED MWT % POWER 2436.000 3323.000 73.31%
Rodline = % Power = 72.17% 74.43%
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Supplemental Final Startup Report )
'i Procedure No: N2-SUT-13-3 Process Computer Corrected Recorded Data Data ]
Step 6.4.4.8 P-1 (01-16-88 2333) SEQ. NO. 11 WT FACTOR WT* FACTOR PCT WT Mib/He M1b/He 107.300 1.045 112.129 = 103.34% 98.89%
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2440.000 3323.000 73.43% i Rodline = % Power = 71.75% 74.00%
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Step 6.4.4.19 P-1 (01-17-88 0026) SEQ. NO. 12
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, M1b/Hr M1b/Hr 105.820 1.045 110.582 = 101.92% 97.53%
108.500 MWT RATED MWT % POWER 2434.000 3323.000 73.25%
Rodline = % Power = 72.28% 74.54%
.3+.7*%WT Step 6.4.4.21 P-1 (01-17-88 0039) SEQ. NO. 13 WT FACTOR WT* FACTOR PCT WT M1b/He M1b/Hr' 107.580 1.045 112.421 = 103.61% 99.15%
108.500 MWT RATED MWT % POWER 2444.000 3323.000 73.55%
Rodline = % Power = 71.73% 73.99%
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Page 10 of 132 Supplemental Final Startup Report Procedure No: N2-SUT-13-3 Process Computer Corrected Recorded Data Data Step 6.4.4.31 P-1-(01-17-88 0522) SEQ. NO. 18 WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 106.800 1.045 111.606 = 102.86% 98.43%
108.500 MWT RATED MWT % POWER 2436.000- 3323.000 73.31%
Rodline = % Power = 71.87% 74.12%
.3+.7*%WT Step 6.4.4.44 P-1 (01-17-88 0555) SEQ. NO. 19 WT FACTOR WT* FACTOR PCT WT
. -M1b/Hr M1b/Hr 106.370 1.045 111.157 - 102.45% 98.04%
108.500 MWT RATED MWT % POWER 2441.000 3323.000 73.46%
Rodline = % Power = 72.22% 74.48%
.3+.7*%WT Max WT = 103.61% Rated Core Flow-CONCLUSION: 103.61% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
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- Supplemental Final Startup Report Procedure No: N2-SUT-16-3 Selected Process Temperatures and-Water Level Measurements.
Corrected Recorded Data Data Step 4.1.4 / OD-3 (11-08-87 0456)
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 108.750 1.045 113.644 = 104.74% 100.23%
108.500 MWT RATED MWT % POWER 2211.590- .3323.000 66.55%
Rodline = % Power = 64.42% 66.45%
.3+.7*%WT Step 4.2.2 / OD-3 (01-14-88'0907)
WT FACTOR WT* FACTOR PCT WT N1b/Hr M1b/Hr 106.250 1.045 111.031 = 102.33% 97.930%
108.500 MWT RATED MWT % POWER 2417.780 3323.000 72.76%
Rodline = % Power = 71.59% 73.83%
.3+.7*%WT Step 6.1.2 Data Sheet 1 Page 13 Total Core Flow FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 107.000. 1.045 111.815 = 103.06% 98.62%
108.500 Step 4.2.3 Data Sheet 4 Page 18 1
Total Core Flow FACTOR WI* FACTOR PCT WT M1b/Hr M1b/He 106.450 1.045 111.240 = 102.53% 98.11%
108.500 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS. ,j O / //DU C' SW /d$d$$ ' '
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Page 12 of 132 Supplemental Final Startup Report
.l Procedure No: N2-SUT-19-3 Core Performance Corrected Recorded 1 Data Data' Step 6.1.1 / OD-3 (11-09-87 0343)
WT FACTOR WT* FACTOR ' PCT WT M1b/Hr M1b/Hr i 106.640 1.045 111.439 = 102.71%' 98.29% 1 108.500 i MWT RATED MWT % POWER 2161.030. 3323.000 65.03%
Rodline = % Power = 63.82% 65.82%
.3+.7*%WT Step 6.1.1 Reactor Physics Surveillance Procedure No. N2-RPSP-1 / p - 1 Step 7.1.1.2 WT (mlb/hr) =. 111.6791 106.87
Step 9.1.2 Core Flow: WT must be < or = 108.5 M1bs/HR mass flow.
The corrected core flow exceeds the acceptance criteria of the RPSP-1 but can be accepted as is based on Increased Core Flow analysis.
Step 7.1.1.4 Core flow is less than or equal to 108.5 MLB/HR. UNSAT Step 8.1.4 (Level 1 Criteria) Core flow should not exceed its rated value.UNSAT Step 8.1.2 (Level 1) Core flow is used by the process computer to determine
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-the MCPR limit, the process computer calculated critical bundle power will be lower than actual due to the higher flow rate which actually= existed in the bundle.
This results in conservative monitoring of the MCPR for each fuel bundle.
CONCLUSION: INCREASED CORE FLOW GENERATED A LEVEL 1 CRITERIA VIOLATION BUT 102.93% CORE FLOW CAN 8E ACCEPTED AS IS PER ATTACHMENT 1.
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Page 13 of 132 j Supplemental Final Startup Report Procedure No: N2-SUT-22-3 Pressure Regulator Corrected Recorded S Data Data Step 7.1.4.2 Verify extrapolated peak flux margin (7.5%):
Step 7.1.4.2.3 Peak flux margin determined to be. 4.65% 7.20%
Step 7.1.4.2.4 Peak flux margin determined to be 5.44% 7.95%
.The only! requirement for violation of Step 7.1.4.2 j is notification of the Lead STD & A. '
The extrapolated flux margin provided anticipated peak flux during pressure regulator testing at the higher power only.
Page 20 j
Step 7.2.4.2 Verify extrapolated APRM margin > 7.5% Verified as Shown on !
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Data sheet Page no. Parameter Date 1 28 Core Flow 11/11/87 97.50 93.30 1 28' Core Flow 01/01/88 100.32 96.00 2 29 Core Flow 11/12/87 97.19 93.00 2 29 Core Flow 01/02/88 99.28 95.00 3A 30 -Extr. Mars. APRM 11/14/88 i A Regulator +10 PSI STEP 14.07% 16.33%
Regular' fail to "B" 5.44% 7.95%
B Regulator +10 PSI STEP 11.56% 13.89%
Regulator fail to "A" 4.65% 7.20%
3B 31 Extr. Mars. APRM 01/05/88 A Regulator +10 PSI STEP 14.27% 17.30%
B Regulator +10 PSI STEP 17.46% 20.40%
4 33 Core Flow 11/12/87 97.19 93.00 5 34 Core Flow 01/02/88 97.19 93.00 1.
6 35 Extr. Mars. APRM 11/14/87 A Regulator +10 PSI STEP 15.86% 17.85%
B Regulator +10 PSI STEP 16.18% 18.15% am
O Page 14 cf 132
. Supplemental Final Startup Report Procedure No: N2-SUT-22-3 Pressure Regulator Corrected Recorded Data Data Step.4.1.1/6.1.5 OD-3 DATE 11/12/88 0132 WT FACTOR WT* FACTOR
- 4. 93.360 1.045 97.561 = 89.92% 86.05%
108.500 MWT RATED MWT % POWER 1967.470 3323.000 59.21%
. Rod line= 63.70% 65.62%
Step 6.1.15A 'CETARS Data Page 639 WT FACTOR WI* FACTOR 93.360 1.045 97.561 89.92%' 86.05%
108.500 100% Rodline S. S. Power = 92.94% 91.00%
100% Rodline APRM Flux Increase = 10.99% 10.67% -
100% Rodline Peak Power = 103.93% 101.67%
DS3A Extrapolated Margin 14.07% 16.33%
Step 6.1.23A GETARS Data Page 663 WT FACTOR WT* FACTOR 93.360 1.045 97.561 = 89.92% 86.05%
108.500 100% Rodline S.S. Power = 92.94% 91.00%
100% Rodline APRM Flux Increase = 13.50% 13.11%
100% Rodline Peak Power = 106.44% -104.11%
DS3A Extrapolated Margin 11.56% 13.89%
Step 4.1.1/6.1.5 OD-3 Date 11/12/88 3 WT FACTOR WT* FACTOR l 93.360 1.045 97.561 = 89.92% 86.05%
108.500 MWT RATED MWT % POWER !
1967.470 3323.000 59.21%
Rodline = 63.70% 65.62%
Step 6.1.29/30 GETARS Data Page 717 (P913)
WT FACTOR WT* FACTOR 93.360 1.045 97.561 = 89.92% 86.05% l 108.500 100% Rodline S.S. Power = 92.94% 91.00%
100% Rodline APRM Flux Increase = 20.41% 19.81% i 100% Rodline Peak Power = 113.25% 110.81%
DS3A Extrapolated Margin 4.65% 7.19%
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Page 15 of 132 Supplemental Final Startup Report Procedure No: N2-SUT-22-3 Pressure Regulator j Corrected Recorded Data Data Step 6.1.36/37 GETARS Data Page 745.
WI FACTOR WT* FACTOR 93.360 1.045 97.561 = 89.92% 86.05%
108.500 100% Rodline S.S. Power = 92.94% 91.00%
100% Rodline APRM Flux Increase = 19.62% 19.05%
100% Rodline Peak Power = 112.56% 110.05%
DS3A Extrapolated Margin 5.44% 7.95%
Step 4.2.5 WT FACTOR WT* FACTOR DS5 93.010 1.045 97.195 = 89.58% 85.77%
108.500 MWT RATED MWT % POWER
. 1961.250 3323.000 59.02%
Rod line = 63.66% 65.57%
Step 6.2.8 GETARS Data Page 969 WT FACTOR WT* FACTOR 93.010 1.045 97.195 = 89.58% 85.72%
108.500 100% Rodline S.S. Power = 92.71% 91.00%
100% Rodline APRM Flux Increase = 9.42% 9.15%
100% Rodline Peak Power = 102.13% 100.15%
DS6 Extrapolated Margin 15.87% 17.85%
Step 6.2.16 GETARS Data Page 862 WT FACTOR WT* FACTOR 93.010 1.045 97.195 = 89.58% 85.72%
108.500 100% Rodline S.S. Power = 92.71% 91.00%
100% Rodline APRM Flux Increase = 9.11% 8.85%
100% Rodline Peak Power = 101.82% 99.85%
DS6 Extrapolated Margin = 16.18% 18.15%
Step 4.1.1/6.1.5 OD-3 Date 01/02/88 WT FACTOR WT* FACTOR DS2 95.080 1.045 99.359 , 91.57% 87.63%
108.500 MWT RATED MWT % POWER 2027.560 3323.000 61.07%
Rod line = 64.84% 66.80%
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Page 16 of 132 Supplemental Final Startup Report Procedure No: N2-SUT-22-3 Pressure Regulator Corrected Recorded Data Data Step 6.1.41 OD-3 Date 01/03/88 WT FACTOR WT* FACTOR DS2 93.590 1.045 97.802 = 90.14%' 86.26%
108.500 MWT RATED MWT % POWER 2037.340 3323.000 61.31% '
Rod line = 65.86% 67.84%
Step 6.1.15B GETARS Data Page 137 WT FACTOR WT* FACTOR 93.590 1.045 97.802 = 90.14% 86.26%
108.500 100% Rodline S.S. Power = 93.10% 90.38%
100% Rodline APRM Flux Increase = 10.63% 10.32%
100% Rodline Peak Power = 103.73% 100.70%
DS3B Extrapolated Margin 14.27% 17.30%
Step 6.1.23B GETARS Data Page.215
-WT FACTOR WT* FACTOR 93.590 1.045 97.802 , 90.14% 86.26%
108.500 100% Rodline S.S. Power = 93.10% 90.38%
100% Rodline APRM Flux Increase = 7.44% 7.22%
100% Rodline Peak Power = 100.54% 97.60% . <
DS3B Extrapolated Margin 17.46% 20.40%
CONCLUSION: THE CORRECTED EXTRAPOLATED NEUTRON FLUX MARGINS ON REGULATOR FAILURE TEST WEEE LESS THAN- PREVIOUSLY CALCULATED, THIS INFORMATION IS FOR REFERENCE ONLY ON PRESSURE REGULATOR TESTING AT HIGHER POWER CONDITION. NO ACTION IS REQUIRED FOR LESS THAN 7.5% NEUTRON FLUX MARGIN BASED ON COMPLETION OF THE N2-SUT-22-6 TESTING.
ANY CORE FLOW DATA IN THE PROCEDURE NEEDS TO BE CORRECTED BEFORE ANY APPLICATION.
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CORE FLOW DATA IN THIS PROCEDURE SHALL BE CORRECTED WITH A FACTOR OF 1.045 FOR APPLICATION.
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.Page 23.of 132
!. Supplemental Final Startup Report-
-Procedure No: N2-SUT-23-3 Feedwater System o Corrected Recorded Data Data Step 6.1.4 Dated 01/04/88 WT FACTOR WT* FACTOR PCT WT 95.860 1.045 100.174 = 92.33% 88.35%-
108.500 MWT RATED MWT % POWER' 2064.970 3323.000 62.14%
Rodline =' 65.67% 67.66%
Step 6.2.4' OD-3 Dated 01/05/88 WT FACTOR WT* FACTOR PCT WT 97.930 1.045 102.337- 94.32% 90.26%
108.500 MWT RATED MWT % POWER 2045.940 3323.000 61.57%
Rodline = 64.12% 66.07%
Step 6.3.4 0D-3 Dated 01/12/88
-WT FACTOR WT* FACTOR PCT W 101'.640 1.045 106.214 = 97.89% 93.68%
108.500 MWT RATED MWT % POWER 2248.880 3323.000 67.68%
Rodline = 68.69% 70.81%
Step 4.4.7 Dated 01/09/88 WT FACTOR WT* FACTOR PCT WT 96.800 1.045 101.156 , 93.23% 89.22%
108.500 MWT RATED MWT % POWER 2180.030 3323.000 65.60%
Rodline = o8.87% 70.96%
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Page 24 of'132 Supplemental Final Startup Report Procedure.No: N2-SUT-23-3 Feedwater System Corrected Recorded Data Data Step 4.5.7 OD-3 Dated 01/12/88 WT FACTOR WT* FACTOR PCT WT 106.640 1.045 111.439- 102.71% 98.29%
108.500
. MWT RATED MWT % POWER 2269.660 3323.000 68.30%
Rodline = 67.03% 69.13%
Step 4.6.7 OD-3 Dated 01/12/88 WT FACTOR WT* FACTOR PCT WT 105.550 1.045 110.300 = 101.66% 97.28%
108.500 MWT RATED MWT % POWER 2210.810 3323.000 66.53%
Rodline = 65.77% 67.87%
The following lists the corrected and recorded core flow data in the procedure:
DATA SH. PAGE FACTOR WT* FACTOR PCT WT WT(MLB/HR) 1A 42 1.045 101.856 93.88% 97.470 1B 44 1.045 111.585 102.84% 106.780 IC 46 1.045 109.934 101.32% 105.200 2A 47 1.045 102.410 94.39% 98.000 2B 48 1 045 111.815' 103.06% 107.000 2C 49 1.045 109.725 101.13% 105.000 l 4A 53 1.045 98.544 90.82% 94.300 48 54 1.045 103.037 94.96% 98.600 AC 55 1.045 107.499 99.08% 102.870 SA 56 1.045 101.365 93.42% 97.000 SB 57 1.045 103.455 95.35% 99.000 SC 58 1.045 106.068 97.76% 101.500 MAK WI% 103.06%
CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS. MAX.
CORE FLOW OF 103.06% RATED CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
W Performed by
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Page 25 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control Corrected Recorded Data Data Page 27 Step 7.1.3.6 "A" Loop +.5% (Min FCV) APRM change = N/A 2.70%
"B" Loop +.5% (Min FCV) APRM change = N/A 2.29%
"A" Loop +.5% (Min FCV) APRM change = N/A 14.56%
"B" Loop +.5% (Min FCV) APRM change = N/A 15.97%
"A" Loop +.5% (65% Flow) APRM change = N/A C%
"B" Loop +.5% (65% Flow) APRM caanse = N/A 3.42%
"A" Loop +.5% (65% Flow) APRM change = N/A 16.32%
"B" Loop +.5% (65% Flow) APRM change = N/A' 20.50%
"A" Loop +.5% (9t% Flow) APRM change = 0% 0.00%
"B" Loop +.5% (98% Flow) APRM change = 0% 0.00%
"A" Loop +.5% (98% Flow) APRM change = 5.53% 5.30%
"B" Loop +.5% (98% Flow) APRM change = 7.68% 7.35%
Corrected data for position steps at Min FCV .
and 65% flow is N/A due to tests being performed prior to core flow calibration on 12/6/87.
Step 7.1.3.7 Checked and updated the data at 98% flow condition.
Page 28 Step 7.1.3.8 Verified that the APRM Trip Avoidance Margin in Step 7.1.3./ is greater than or equal to 7.5%.
Step 7.1.3.9 Checked and updated the data at 98% flow condition.
Step 7.1.3.10 Verified that the Simulated Heat Flux Trip Avoidance Margin in Step 7.1.3.9 is greater than or equal to 7.5%.
Page 34 Step 7.2.1.6 Checked, see notes for Data Sheet 9 on page 29 for corrected trip margin.
Step 7.2.1.7 TE N2-SUT-29-3-7 the margin value is -0.08% now. No further action is required to this deviation. The APRM trip margin of the other test conditions meet the requirement.
Step 7.2.1.8 Checked, see notes for Data Sheet 9 on page 29.
Page 35 Step 7.2.1.9 Verified that the Flow Biased Heat Flux Trip Avoidance Margin is greater than or equal to 5.0%.
Corrected Recorded
- Data Data Page 38 l Step 7.2.2.5 Core Flow (%) at Peak APRM Neutron Flux = 103.34% 98.89%
Step 7.2.6 Extrapolated Core Power = 102.34% 99.00% **
+
o Page 26 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recirc. Flow Control Corrected Recorded Data Data Page 39 Step 7.2.2.7 WT' FACTOR i/I* FACTOR PCT WT-106.680 1.045 111.481 108.500 =- 102.75% 98.32%
MWT RATED MWT % POWER 2144.000 3323.000 64.52%
Test Rod line = 63.30% 65.29%
(100%/ test rodline)1.5 , 1,99 1,90 Extrapolated APRM flux Change = 16.08% 15.35% .
Step 7.2.2.8 Calculated Peak Power = 118.47% 114.35%
Step 7.2.2.9 APRM Heat Flux Trip Margin = -0.42% 3.65%
Step 7.2.2.10 TE N2-SUT-29-3-11 still required, value
.42% vice 3.65%. Criteria on APRM Trip Avoidance Margin is s 7.5%.
Step 7.2.2.11 Extrapolated heat flux margin to 100% codline:
For +15% ramp = 20.32% 21.41%
For -15% ramp = 20.91% 22.04% .
Step 7.2.2.12 Verified that the simulated heat flux margin to avoid a trip is > 5%.
See Step 7.2.2.11.
Page 41 Step 7.3.1.5.1 68% Flow +t% step extra APRM change = 7.99% 7.67%
100% Flow +5% step extra APRM change = 6.96% 6.65%
Step 7.3.1.6 Verified that the APRM trip avoidance margin is > 7.5%. See step 7.3.1.5.1 and TE N2-SUT-29-3-5 still required.
Step 7.3.1.7 Evaluated as noted for Data Sheet 13, on page 30. _
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Page 27 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control Corrected Recorded Data ' Data Page 42 Step 7.3.1.8 Verified the Flow biased Heat Flux trip avoidance margin is > 7.5%.
Page 45 Step 7.3.2.5.1 68% Flow +8% step change extrapolated APRM ch 11.23% 10.80%
100% Flow +5% step change extrapolated APRM ch 13.44% 12.92%
Step 7.3.2.5.2 Evaluated as noted for Data Sheet 15 on Page 30. .
Step 7.3.2.6 100% Flow +5% step extrapolated trip margin = 3.77% TE-N2-SUT-29-3-6 still required.
Page 46.
Step 7.3.2.7 Evaluated as noted for Data Sheet 15 on Page 30.
Step 7.3.2.8 Verified the Flow Biased Heat Flux trip avoidance margin is > 7.5%.
Page 49 Step 7.3.3.5 Core Flow (%) at peak APRM Neutron Flux = 85.72% 82.03%
Step 7.3.3.6 Extrapolated Core Power = 90.00% 87.40%
Page 50 Step 7.3.3.7 Extrapolated APRM Flux Change = 6.07% 5.79%
Step 7.3.3.8 Calculated Peak Power = 96.07% 93.19%
Step 7.3.3.9 APRM Heat Flux Trip Margin = 21.93% 24.81%
Step 7.3.3.10 Verified the APRM trip avoidance margin is > 7.5% in Step 7.3.3 9 Step 7.3.3.11 Extrapolated Heat Flux Trip Margin = 20.62% 21.74%
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Page 28 of 132 l
l Supplemental Final Startup Report l
Procedure Number: N2-SUT-29-3 Reactor Recirc. Flow Control Corrected Recorded Data Data Step 7.3.3.12 Verified the Heat Flux Trip Margin in Step 7.3.3.11 is > 5%.~
Page 61 Dated 11/10/87 Data Sheet 1 B Jet Pump Loop Flow (M1b/Hr) 57.52 55.04 A Jet Pump Loop Flow (M1b/Hr) 55.17 52.79 Total Core Flow (M1b/Hr) 111.99 '107.17 Page 61 Dated 12/25/87 Data Shect 1 B Jet Pump Loop Flow (M1b/Hr) 23.70 22.68 A Jet Pump Loop Flow (M1b/Hr) 23.08 22.09 Total' Core Flow (M1b/Hr) 46.47 44.47 Page 69 Dated 11/12/87 .
Data Sheet 6 Trip Avoidance Margin (%)
9t% Loop A +0.5% -APRM 16.21% 19.00%
9t1 Loop A -0.5% APRM N/A N/A 98% Loop A +5% APRM 10.68% 13.70%
98% Loop A -5% APRM N/A N/A 98% Loop A +0.5% Heat Flux 20.63% 22.53%
98% Loop A -0.5% Heat Flux 20.63% 22.53%
98% Loop A +5% Heat Flux 20.40% 21.40%
9t% Loop A -5% Heat Flux 20.63% 22.53%
98% Loop B +0.5% APRM 16.21% 19.00%
9F% Loop B -0.5% APRM N/A N/A 98% Loop B +5% APRM 10.68% 11.65%
98% Loop B -5% APRM N/A N/A 98% Loop B +0.5% Heat Flux 21.07% 22.53%
98% Loop B -0.5% Heat Fluz 20.63% 22.53%
98% Loop B +5% Heat Flux 20.63% 22.06%
98% Loop B -5% Heat Flux 20.63% 22.53%
Page 70 Data Sheet 7 Step 4.2.3 Dated 11/10/87 {
B Jet Pump Loop Flow (M1b/Hr) 29.26 28.00 A Jet Pump Loop Flow (M1b/Hr) 29.05 27.80 Total Core Flow (M1b/Hr) 58.10 55.60 i 4
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Page 29 of 132 Supplementti Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control i Corrected Recorded Data Data i Step 4.2.3 Dated 11/11/87 B Jet Pump Loop. Flow (M1b/Hr) 29.24 27.98 A Jet Pump Loop Flow (M1b/Hr) 28.35 27.13 Total Core Flow (M1b/Hr) 57.34 54.87
. Step 4.2.3 Dated 11/12/87-B Jet Pump Loop Flow (M1b/Hr) 29.05 27.80 A Jet Pump Loop Flow (M1b/Hr) 28.32 27.10 .'
Total Core Flow (M1b/Hr) 57.16 54.70 Step 4.2.3 Dated 1/03/88 B Jet Pump Loop Flow (M1b/Hr) 56.95 54.50 A Jet Pump Loop Flow (M1b/Hr) 55.80 53.40 Total Core Flow (M1b/Hr) 111.82 107.00 ..
Page 74 Data Sheet 9 Section 7.2 Trip Avoidance Margin (%)
50% Core Flow +5.0% Step APRM 16.06% 19.14%
-5.0% Step APRM N/A- N/A
+5.0% Step Heat Flux 17.49% 18.23%
-5.0% Step Heat Flux 16.08% 16.76%
100% Core Flow +5.0% Step APRM -0.08%* 3.75%
-5.0% Step APRM N/A N/A
+5.0% Step Heat Flux 20.09% 21.77%
-5.0% Step Heat Flux 20.66% 21.17%
- TE N2-SUT-2f-3-7 already documents criteria failure to APRM trip avoidance margin. Accept as is disposition still holds.
Page 76 Data Sheet 11 Step 4.3.4 Dated 11/14/87 B Jet Pump Loop Flow (M1b/Hr) 56.57 54.13 A Jet Pump Loop Flow (M1b/Hr) 55.93 53.52 Total Core Flow (M1b/Hr) 112.25 107.42 Step 4.3.4 Dated 1/03/88 B Jet Pump Loop Flow (M1b/Hr) 38.05 36.41 /
A Jet Pump Loop Flow (M1b/Hr) 38.31 36.66 -
Total Core Flow (M1b/Hr) 76.21 72.93 I
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Page 30 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control Corrected Recorded Data Data Page 80 Data Sheet 13 Section 7.3.1 Trip Avoidance Margin (%)
68% Core Flow +8.0% Step APRM 23.92% 26.33%
-8.0% Step APRM N/A N/A
+8.0% Step APRM 19.26% 20.17%
-8.0% Step APRM 18.85% 19.74%
100% Core Flow +5.0% Step APRM 8.55% 12.00%
-5.0% Step APRM N/A N/A
+5.0% Step Heat Flux 20.37% 21.47%
-5.0% Step Heat Flux 20.79% 21.93%
Page 82 Data Sheet 15 Section 7.3.2 .
Trip Avoidance Margin (%)
68% Core Flow +8.0% Step APRM 18.57% 21.50%
-8.0% Step APRM N/A N/A
+8.0% Step APRM 18.94% 19.84%
-8.0% Step APRM 18.85% 19.74%
100% Core Flow +5.0% Step APRM 3.77% 7.20%
-5.0% Step APRM N/A N/A
+5.0% Step Heat Flux 20.37% 21.29%
-5.0% Step Heat Flux 20.79% 21.74%
Step 6.1.3.2 OD-3 11/09/87 0543 WT FACTOR WT* FACTOR PCT WT M1b/He 1.045 M1b/He 105.700 1.045 110.457 = 101.80% 97.42%
108.500 MWT RATED MWT % POWER 2129.690 3323.000 64.09%
Rodline = 63.29% 65.27%
Step 6.1.3.16 OD-3 11/09/87 0953 WT FACTOR WT* FACTOR PCT WT M1b/Hr 1.045 M1b/Hr 106.480 1.045 111.272 = 102.55% 98.14%
108.500 MWT RATED MWT % POWER 2097.000 3323.000 63.11% _
Rodline = 62.00% 63.94% v Je
Page 31 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control Corrected Recorded.
Data Data Step 6.1.1.3/6.2.1.1 OD-3 11/11/87 0057 WT FACTOR WT* FACTOR PCT WT M1b/Hr 1.045 M1b/He 55.080 1.045 57.559 = 53.05% 50.76%
108.500 MWT . RATED MWT % POWER 1620.470 3323.000 48.77%
Rodline = 72.64% 74.41%
Step 7.2.7/6.1.7/7.1.5 Gecars Data Page 415 WT FACTOR WT* FACTOR PCT WT .
M1b/He 1.045 M1b/He 55.080 1.045 57.559 = 53.05% 50.76%
108.500 100% Rodline S. S. Power = 67.13% 65.54%
100% Rodline APRM Flux Increase = 34.24% 33.03%
100% Rodline Peak Power = 101.38% 98.56%
Extrapolated APRM Trip Margin 16.62% 19.44%
Step 6.2.1.1 V-Mean Cetars Data Page 487 WT FACTOR WT* FACTOR PCT WT M1b/Hr 1.045 M1b/Hr .
54,.615 1.045 57.073 = 52.60% 50.34%
108.500 Avg. APRM Power % = 47.72%
Rodline = 71.42% 73.18%
Step 6.2.1.2 Getars Data Page 361 WI FACTOR WT* FACTOR PCT WT M1b/He 1.045 M1b/He 61.111 1.045 63.861 = 58.86% 56.32%
108.500 L
N
Page 32 of 132 Supplemental Final Startup Report'
' Procedure Number: N2-SUT-29-3 Reactor Recirc. Flow Control Corrected Recorded Data Data Step 7.2.1.8 Getars Data Page 084 WT FACTOR. WT* FACTOR PCT WT M1b/Hr 1.045 M1b/Hr.
54.615 1.045 57.073 = 52.60% '50.34%
108.500 100% Rodline S. S. Power = 66.82% 65.24%
100% Rodline APRM Flux Increase = 35.13% 33.86%
100% Rodline Pesk Power = 101.95% 99.10%
Extrapolated APRM Trip Margin 16.05% 18.90%
Getars Data Page 100 Min Ht Flux Margin = 31.00%. 31.00%
Extrapolated Margin = 17.49% 18.23%.
Step 6.2.1.4/7.2.1.8 Getars Data Page 108 Min Ht Flux Margin = 28.50% 28.50%-
Extrapolated Margin = 16.08% 16.76%
Step 6.2.2.1,1 OD-3 Date 11/09/87 1351 W FACTOR WT* FACTOR PCT WT M1b/Hr 1.045 M1b/Hr 106.950 1.045 111.763 = 103.01% 98.57%
108.500 MWT RATED MWT % POWER 2139.280 3323.000 64.38%
Redline = 63.05% 65.03%
Step 6.2.2.1.2/7.2.1.8 WT FACTOR WT* FACTOR PCT WT M1b/Hr 1.045 M1b/Hr 106.950 1.045 111.763 = 103.01% 98.6%
108.500 Getars Data Page 498 100% Rodline S. S. Power = 102.11% 99.02%
100% Rodline APRM Flux Increase = 15.98% 15.26% i 100% Rodline Peak Power = 118.08% 114.26% -
Extrapolated APRM Trip Margin -0.08% 3.75% 7 1m Getars Data 45.25%
Page 515 Min Ht Flux Margin = 45.25%
Extrapolated Margin 20.66% 21.77%
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l l Pese 33 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control Corrected Recorded Data Data Step 6.2.2.1 OD-3 Date 1/3/88 Getars Data Page 514 WT FACTOR WT* FACTOR PCT WT M1b/He 1.045 M1b/Hr
'106.950 1.045 111.763 = 103.01% 98.6%
108.500
'MWT RATED MWT % POWER 2139.280 3323.000 64.38%
Rodline'= 63.05% 65.03%
Step 6.2.2.1.4/7.2.1.8 Getars Data .
Page 514 WT FACTOR WT* FACTOR PCT WT 106.950 1.045 _111.763 = 103.01% 98.6%
108.500 Getars Data Data Page 514 Min Ht Flux Mar 5in = 44.00% 44.00%
Extrapolated Margin = 20.09% 21.17%
Step 6.2.3.1 P-1 Dated 1/3/88 Seq.4 Time 1418 WT FACTOR WT* FACTOR PCT WT 106.680 1.045 111.481 = 102.75% 98.32%'
108.500 MWT RATED MWT % POWER 2144.000 3323.000 64.52%
Redline = 63.30% 65.29%
Step 6.2.3 Getars Data Page 649 WT FACTOR WT* FACTOR PCT WT 107.300 1.045 112.129 = 103.34%
108.500 See Page 39 100% Rodline S. S. Power = 102.34% N/A 100% Rodline APRM Flux Increase = 16.18% 15.35%
100% Rodline Peak Power = 118.52% 114.35%
Extrapolated APRM Trip Mar 51n -0.52% 3.65%
Getars Date Page 701 Min Ht Flux Margin = 44.20% 44.20% -
Extrapolated Mar 51n 20.32% 21.41%
Getars Data 45.50% 45.50%
Page 694 Min Ht Flux Margin =
Extrapolated Margin = 20.91% 22.04%
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Page 34 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control
' Corrected Recorded Data Data i
Step 6.3.1.1 OD-3 Date 11/14/87 I WT FACTOR WI* FACTOR PCT WT )
73.010 1.045' 76.295 , 70.32% 67.29%
108.500
. MWT RATED MWT % POWER 1659.640 3323.000 49.94%
Rodline = 63.04% 65.29%'
Step 6.3.1.2 Getars Data Page 056 PEAK APRM WT FACTOR WT* FACTOR 83.200 1.045 86.944 = 80.13% 76.68% -
, 108.500 Getars Data Pa6e 056 100% Rodline S. S. Power = 86.09% 84.00%
100% Rodline APRM Flux Increase = 7.99% 7.67%
100% Rodline Peak Power = 94.08% 91.67%
Data Sh. 13 Extrapolated APRM Trip Margin 23.92% 26.33%
Min Ht Flux Margin = 42.20% 42.20%
Getars Data Page 264 Extrapolated Margin = 19.26% 20.17%
Getars Data Page 256 Min Ht Flux Margin = 41.30% 41.30%
Extrapolated Margin = 18.85% 19.74%
Getars Data Page 240 Min Ht Flux Margin = 41.50% 41.50%
Extrapolated Margin = 18.94% 19.84%
Step 6.3.1.11 Getars Data Page 073 PEAK APRM WT FACTOR WT* FACTOR 86.330 1.045 90.215 = 83.15% 79.57%
108.500 100% Rodline S. S. Power = 88.20% 85.70%
100% Rodline APRM Plux Increase = 11.23% 10.80%
100% Rodline Peak Power = 99.43% 96.50%
Extrapolated APRM Trip Margin 18.57% 21.50% .
y, Getars Data 41.30%
Page 548 Min Ht Flux Margin = 41.30%
Extrapolated Margin = 18.85% 19.74%
as
1 Page 35 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control Corrected. Recorded Data Data Step 4.3.3 OD-3 Dated 01-01-88 1623 WT FACTOR WT* FACTOR 107.070 1.045. 111.888 = 103.12% 98.68%
108.500 Step 6.3.2.1.1 OD-3 Dated 01-09-88 2046 WT FACTOR WI* FACTOR 106.990- 1.045 111.805 - 103.05% 98.61%
108.500 Step 4.3.3 00-3 Dated 01-10-88 0251 Reverification WT FACTOR WT* FACTOR 107.500 1.045 '112.338 = 103.54% 99.08%
108.500 -
~
Step 6.3.2.1.1 OD-3 Date 11/09/87 0324 WT FACTOR WT* FACTOR 106.760 1.045 111.564 = 102.82% 98.40%
108.500 MWT ' RATED MWT % POWER' 2089.380 3323.000 62.88%
Rod 11ne = 61.66% 63.60%
Step 6.3.2.1.3 Getars Data Page 316 WT FACTOR WT* FACTOR 4 107.500 1.045 112.338 = 103.54% 99.08% 1 1
108.500 Getars Data Page 621 100% Rodline S. S. Power = 102.48% 99.35%
100% Rodline APRM Flux Increase = 6.97% 6.65%
100% Rodline Peak Power = 109.44% 106.01%
Extrapolated APRM Trip Margin 8.56% 11.99%-
Getars Data .
I Page 966 Min Ht Flux Margin = 47.30% 47.30%
Extrapolated Margin = 20.79% 21.91%
Getaes Data Page 612 Min Ht Flux Margin = 46.34% 46.34% ;
Extrapolated Margin = 20.37% 21.47% .
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Page 36 of 132 Supplemental. Final Startuo Report Procedure Number: N2-SUT-29-3 Reactor Recire. Flow Control Corrected Recorded Data Data Step 6.3.2.4.5 Getars Data Page 075 WT FACTOR WT* FACTOR 105.000 1.045 109.723 = 101.13% 96.77%
108.500 Getars Data Page 095 100% Rodline S. S. Power = 100,79% 97.74%
100% Rodline APRM Flux Increase = 13.44% 12.83%
100% Rodline Peak Power = 114.23% 110.57%
Extrapolated APRM Trip Margin 3.77% 7.43%-
Getars Data Page 075 Min Ht Flux Margin = 46.34% 46.34%
Extrapolated Margin = 20.37% 21.47%
Step 6.3.3.1 P-1 Seq 10, 1/10/8
, WT FACTOR WT* FACTOR 107.300 1.045 112.129 = 103.34% 98.89%
108.500 MWI RATED MWT % POWER 2069.000 3323.000 62.26%-
Getars Data Page 746 Rodline = 60.84% 62.75%
Step 6.3.3.3/7.3.3.11 Getars Data Page 168 WT FACTOR WT* FACTOR 107.300 1.045 112.129 = 103.34% 98.89%
108.500 100% Rodline S. S. Power = 102.34% N/A Min Ht Flux Margin = 48.00% 48.00%
Extrapolated Margin = 20.62% 21.74%
i Step 6.3.3.4/7.3.3.2 !
WT FACTOR WT* FACTOR 89.000 1.045 93.005 = 85.72% 82.03%
82.03% 108.500 100% Rodline S. S. Power = 90.00% N/A 100% Rodline APRM Flux Increase = 6.07% 5.79%
100% Rodline Peak Power = 96.07% N/A Extrapolated APRM Trip Margin 21.93% N/A CONCLUSION: THE MAX CORRECTED CORE FLOW IS 103.54%, THIS CAN BE ACCEPTED PE2 ,j ATTACHMENT 1.
NO NEW TEST EXCEPTION IS GENERATED BY INCREASED CORE FLOW EVENT. 'f' 1 ell + PW i ibo/r7 %).C 6 k n i 4 0/n
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Perfotmed by Verifie6 by i
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- .l,1 Page 37 of 132 Supplemental-Final Startup Report Procedure Number: N2-SUT-30-3 Reactor Recirc. System Corrected Recorded Data Data' i
Page 26 . .
I Step 7.1.2 The estimated' core flow shortfall = 4.94% 0.09%
Corrected data meets < 5% requirement. _j Page 2:8: . .
Step 7.2.6 Simulated heat-flux trip margin.is > 5% SAT. SAT. !
Step 7.2.8 APRM trip margin analysis:
1 Step;7.2.8.1 ' Extrapolate Core Power (100% loadline)= 54.97% 52.60% !
Page' 29 Step 7.2.8.2 Extrapolated APRM change = 24.47% 23.80% ,
I
Step 7.2.9- APRM trip margin is > 7.5%- -SAT. SAT.
- Page 39 Figure 1,.seetattached flg. Corrected Data Recorded Data Avg. FCV Pos. Wt -Pct Wt Wt Pct Wt 3.945 N/A N/A 41.95'.38.66%-
14.3965 N/A N/A 54.14 49.90% ~ ~ " ~
34.8245 N/A N/A 81.17 74.81% ;
67.424 111.72 102.97% 106.91 98.53% '
Corrected Data for <67. 42% ' Avg. FCV Pos. is N/A due to tests
-being performed prior to core flow calibration on 11/6/87.
Corrected Recorded Data Sheet .Page No. Parameter Date Data Data 1 42 A LP Flow (M1b/He) 11/09/87 56.97 54.5165 B LP Flow (M1b/He) 55.08 52.7114 43 Core Flow (N1b/Hr) 111.75 106.94 5 51 A LP Flow (M1b/He) '11/09/87 56.60 54.16
)
B LP Flow (M1b/Hr) 55.47 53.08 )
Core Flow (M1b/Hr) 111.72 106.91 L
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_________._____m_____ _ _ . . _ _ _ . _ . _ _ _ . _ . _ . _ _ _ _
Page 38 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-30-3 Reactor Recire. System Corrected Recorded Data Sheet Page No. Parameter Date Data Data
.5- 52 Core Flow (M1b/Hr) 4.94% 0.10%
Averaged FCV (%) 68.93 68.82 CFP (M1b/Hr) 117.53 107.01
(% Rated) 108.38% 98.63%
CFA (M1b/Hr) 111.72 106.91
(% Rated) 102.97%. 98.53%
6 53 A LP Flow (M1b/Hr) 01/14/88 56.13 53.71 B LP Flow (M1b/Hr) 56.51 54.08 54 Core Flow (M1b/Hr) 112.10 107.27 7 57 A LP Flow (M1b/Hr) 55.70. 53.30 -
B LP Flow (M1b/Hr) 56.12 53.70 Core Flow (M1b/Hr)- 111.80 106.99-8 59 A LP Flow (M1b/Hr) 01/34/88 54.97- 52.60 B LP Flow (M1b/Hr) 13.06 12.50 Core Flow (M1b/Hr) 67.30 64.40 9 61 A LP Flow (M1b/Hr) 28.63 27.398 B LP Flow (M1b/Hr) 28.91 27.664 Core Flow (M1b/Hr) 56.86 54.410 i 10 63 Pre-Trip Total Core Flow (M1b/Hr) 110.77 106.00 l
Post Trip Total Core Flow (M1b/Hr) 57.48 55.00 Post Restart Core Flow (M1b/Hr) 51.62 49.40 1
64 Peak Flux Margin Pump Trip 30.50% 30.00%
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Page 39 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-30-3 Reactor Recire. System Corrected Recorded Data Sheet Page No. Parameter Date Data Data 10 64 Heat Flux Margin Pump Restart 15.80% 16.30%
APkN Margin 39.89% 41.60%
11 65 A LP Flow (M1b/Hr) 01/12/88 54.97 52.60 B LP Flow (M1b/Hr) 58.94 56.40 66 Core Flow (M1b/Hr) 112.34 107.50 12 69 A LP Flow'(M1b/Hr) 56.58 54.14 i
B LP Flow (M1b/Hr) 55.36 52.98 Core Flow (M1b/Hr) 112.58 107.73 13 71 A LP Flow (M1b/Hr) 20.02 19.16 B LP Flow (M1b/Hr) 20.51 19.63 Core Flow (M1b/Hr) 40.73 38.98 14 73 A LP Flow (M1b/Hr) 01/10/88 54.09 51.76 B LP Flow (M1b/Hr) 54.27 51.93 74 Core Flow (M1b/Hr) 108.13 103.47 j 15 77 A LP Flow (M1b/Hr) 01/11/88 55.49 53.10 B LP Flow (M1b/Hr) 54.24 51.90 Core Flow (M1b/Hr) 109.93 105.20 l 16 79 A LP Flow (M1b/Hr) 01/11/88 19.90 19.045 l
l B LP Flow (M1b/Hr) 20.52 19.637 Core Flow (M1b/Hr) 39.35 37.66 L
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Page 40 of 132 Supplemental Final Startup Report' Procedure Number: N2-SUT-30-3 Reactor Recirc. System Corrected Recorded Data Sheet' Page No. Parameter Date Data Data 17- 81 Init. Wt.-(M1b/Hr) 01/15/88 109.44- J104.73 Final Wt -(M1b/Hr) 54.21 51.88 Heat Flux Margin. 32.07% 32.60%
Rod:Line 59.06% 60.90%
18 82 A LP Flow (M1b/Hr) 01/10/88 56.43 54.00 !
l B LP, Flow (M1b/Hr) 54.34 52.00 Core Flow (M1b/Hr) 111.29 '106.50 -
19 86 Core Flow (M1b/Hr) 106.38 101.80 -
Step 6.2.4/7.2.5 Getars Data Page 253 WT FACTOR WT* FACTOR 106.99 1.045 '111.805- 103.05% 98.61%
108.500 MWT RATED MWT .% POWER 2436.56 3323.000 73.32%
Rodline = 71.79% 74.05%
. Extrapolated Heat Flux Margin 30.50% 30.98%
(30%)-
Step 6.2.15/7.2.5 A Pump Restart Getars Data Page 301 WT FACTOR WT* FACTOR 35.06 1.045 36.638- 33.77% 32.31%
108.500
% POWER .
36.08%
Rodline = 67.27% 68.6%
Extrapolated Heat Flux Margin 15.80% 16.32%
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Page 41 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-30-3 Reactor Recire. System Corrected Recorded Data Data l
Step 6.2.15/7.2.3/7.2.8 A Pump Restart Getars Data Page 311 WT FACTOR WT* FACTOR ]
35.060 1.045 36.638- 33.77% 32.31%
108.500 100% Rodline S. S. Power = 53.64% 52.60%
100% Rodline APRM Flux Increase = 24.47% 23.80%
100% Rodline Peak Power = 78.11% 76.40% i Extrapolated Margin 39.89% '41.60%-
Step 6.4.1.b OD-3 Dated 01/11/88 Time 0043 MWT FACTOR -WT* FACTOR 105.2 1.045 109.934- 101.32% 96.96%
108.500 MWT RATED MWT % POWER 1980.7 3323.000 59.61%
Step 6.4.3/7.4.4 Getars Data a '
Page 387 Rodline = 59.06% 60.90%
100% Rodline S. S. Power = 100.93% 91.00%' I Getars Page !
Page 388 Test Rodline Heat Flux Margin = 41.73% 41.73% 1 100% Rodline Heat Flux Margin = 32.07% 32.57% .
Ref. Step No. Data Type Date Time Parameter (M1b/Hr) (M1b/He) 6.1.4.1.a P-1 11/09/87 0252 WT 111.68 106.87 4.2.4 P1/RPSP-1 01/14/88 0638 WT 112.06 107.23 4.2.4 OD-3 01/14/88 0907 WT 111.03 106.25 4.2.8 HISTOGRAM 01/14/88 0736 JP-A-FLO 56.13 53.71 Data Page 175 JP-B-FLO 56.51 54.0768 WT 112.10 107.2742 6.2.1 P-1 01/14/88 0947 WT 117.098 112.05*
OD-3 01/14/88 0957 WT 111.80 106.99 6.2.2 V-MEAN 01/14/88 1004 JP-A-FLO 55.67 53.276 Data Page 215 JP-B-FLO 56.12 53.707 WT 111.27 106.482 l
- The WT in F1 is from substitute value. ,
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- _ . . - - . - _ . - . _ _ _ _ _ _ _ _ _ _ _ i
Page 42.of 132 Supplemental Final Startup' Report Procedure Number: N2-SUT-30-3 Reactor Recirc. System Corrected Recorded Data Data Ref. Step No. Data Type Date Time Parameter (M1b/Hr) (M1b/Hr) 6.2.6 P-1 01/14/88 1059 WT 54.97 52.60 OD-3 1106 WT 54.97 52.60 6.2.7 V-MEAN 01/14/88 1112 JP-A-FLO 13.11 12.545 DataPage 248 JP-B-FLO 67.31 64.412 WT 54.93 52.563 6.2.15 P-1 01/14/88 1453 WT 43.89 42 OD-3 1453 WT 43.89 42 6.2.4 V-MEAN 01/14/88 1042 JP-A-FLO 56.27 53.847 Data Page 238 JP-B-FLO 56.66 54.216 WT 112.40 107.558-6.2.15 V-MEAN 01/14/88 1527 JP-A-FLO 1.42 1.362 Data Page 391 JP-B-FLO 35.22 33.699 ;
WT 33.96 32.502 !
. 6.2.17a P-1 01/14/88 1556 WT 57.11 54.65 6.2.17b OD-3 01/14/88 1555 WT 56.86 54.41 l 6.2.18 V-MEAN 01/14/88 1602 JP-A-FLO 28.63 27.398 Data Page 391 JP-B-FLO 28.91 27.664 WT 57.36 54.894 4.3.9 HIST 01/12/88 1318 JP-A-FLO 53.69 51.3783 P1 JP-B-FLO 59.03 56.4891 WT 112.44 107.5953 HIST 01/12/88 1329 JP-A-FLO 55.05 52.6777 Data Page 334 JP-B-FLO 58.93 56.3946-WT 113.71 108.8111 6.3.1 P-1 0/12/88 1446 WT 117.178 112.12*
OD-3 1445 WT 112.58 107.73 V-MEAN 01/12/88 1447 JP-A-FLO 56.60 54.163 Data Page 382 JP-B-FLO 55.36 52.98 WT 111.70 106.887 6.3.6 P-1 01/12/88 1523 WT 48.75 44.74 OD-3 1523 WT 40.73 38.98 6.3.7 V-NEAN 01/12/88 1447 JP-A-FLO 20.03 19.164 Data Page 382 JP-B-FLO 20.52 19.632 WT 40.46 38.719 4.4.7 HIST 01/10/88 2150 JP-A-FLO 54.09 51.7639 Data Pa6e 858 JP-B-FLO 54.26 51.9254
J
Page 43 of 132 i Supplemental Final Startup Report -
Procedure Number: N2-SUT-30-3 Rer.ctor Recirc. System Corrected Recorded Data Data Ref.' Step No. Data Type Date Time Parameter (M1b/Hr) (M1b/Hr) 6.4.la P-1 01/11/88 0044 WT- 108.95 104.26 6.4.lb OD-3 0043 WT 109.93 105.2 6.4.1c V-MEAN ' 42 JP-A-FLO 55.48 53.093 Data Page 883 JP-B-FLO 54.19 51.854 I WT 109.44 104.732 6.4.6a P-1 01/11/88 0343 WT 46.47 44.47 6.4.6b OD-3' 0348 WT 39.35 37.66 6.4.3 Y-MEAN 0042 JP-A-FLO 27.61 26.417 Data Page 416 JP-B-FLO 26.70 25.55 WT 54.22 51.883 4.5.7 HIST 01/10/88 0822 JP-A-FLO 57.16 54.6971 Data Page 639 JP-B-FLO 54.35 52.0057 6.5.2 V-MEAN WT 111.36 106.4677 Data Page 672 01/10/88 1424 JP-A-FLO 53.14 50.843 JP-B-FLO 52.74 50.47 WT 105.66 101.11 P-1 01/10/88 1413 WT 105.72 101.17 OD-3 1418 WT 105.64 101.09 6.5.7 P-1 01/10/88 1451 WT 105.97 101.41 OD-3 1457 WT 105.89 101.33 P-1 1509 WT 105.57 101.02 OD-3 1532 WT 105.85 101.29 P-1 1554 WT 105.97 101.41 OD-3 1559 WT 105.36 100.82 P-1 1620 WT 106.66 102.07 OD-3 1626 WT 106.58 101.99 P-1 1639 WT 106.54 101.95 OD-3 1645 WT 105-52 100.98 P-1 1651 WT 106 26 101.68 OD-3 1657 WT 106.02 101.45 P-1 1705 WT 105.44 100.90 OD-3 1711 WT 106.58 101.99 P-1 1725 WT 106.54 101.95 OD-3 1730 WT 105.81 101.25 P-1 1746 WT 105.68 101.13 OD-3 1752 WT 106.05 101.48 P-1 1825 WT 106.50 101.91 OD-3 1832 WT 105.85 101.29 P-1 1838 WT 106.95 102.34 OD-3 1845 WT 106.58 101.99 P-1 1854 WT 106.38 101.80 OD-3 1900 WT 105.93 101.37 ,
MAI WT 113.71
'e
Page 44 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-30-3 Reactor Recirc. System Second Order Fit for FCY Pos Versus Core Flow Valve Pos (Valve Pos)2 Core Flow
% % Regression Output:
3.50 12.25 45.8 Constant 40.21080280 9.00 81.00 52.6 Std Err of Y Est 0.44990418 16.50 272.25 62.3 R Squared 0.99976143 25.80 665.64 73.8 No. of Observations- 8 33.70 1135.69 82.7 Degree of Freedom 5
. 46.00 2116.00 93.3 61.98 3341.52 104.4 % Coefficient (s) 1.487152 -0.0072277 !
86.00 7396.00 114.7 Std Err of Coef. 0.022234 0.00024509 i INDICATED ACTUAL CALCULATED i FCY POS FCV POS CORE FLOW 68.82 68.93 108.3786%
-117.5322 M1b/Hr CONCLUSION: THE MAI. CORRECTED CORE FLOW RECORDED IN THIS PROCEDURE IS 113.71 MLB/HR. THIS CONDITION CAN BE ACCEPTED AS IS PER :
ATTACHMENT 1.
DATA ANALYSIS AND CRITERIA EVALUATION WAS PERFORMED AND NO TEST EXCEPTIOh-IS GENERATED DUE TO INCREASED CORE FLOW EVENT. FIGURE 1 IS REPLOTTED WITH 60% LOAD LINE DESIGN DATA AND SECOND ORDER DATA REGRESSION, THE CORRECTED CORE FLOW SHORTFALL IS 4.94%.
W / $f {- //30 69 Performed by Verified'by /'
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F L: Page 45 of 132-l l Supplemental Final Startup Report Procedure Number: N2-SUT-30-3 Reactor Recire. System l FIGURE 1 DATA l .
FCV POS CORE FLOW DESIGN DATA CFP CFA 0 40.21080 N/A N/A N/A 3.50 N/A 45.8 N/A N/A 4 46.04376 N/A N/A N/A 8 51.64544 N/A N/A N/A 9.00 N/A 52.6 N/A N/A.
12 57.01583 N/A N/A N/A
'16 62.15493 N/A N/A. N/A 16.50 N/A 62.3 N/A N/A 20 67.06274 N/A N/A N/A 24 71.73927 N/A N/A N/A.
25.80 N/A 73.8 N/A N/A 12 8 76.18450 N/A N/A N/A
'32 80.39845 N/A N/A N/A ,
33.70 ..N/A 82.7 N/A N/A 36 84.38112 N/A N/A N/A 40 88.13249 N/A N/A N/A 44 91.65257 N/A- N/A N/A 46.00 N/A 93.3 N/A N/A 48 94.94137 N/A N/A N/A 52 97.99888 N/A N/A N/A 56 100.8251 N/A N/A N/A 60 103.4200 N/A N/A N/A 61.98 N/A 104.4 N/A N/A 62 104.6307 N/A N/A N/A 64 105.7836 N/A N/A N/A 68 107.9160 N/A N/A N/A 68.82 N/A N/A 108.3246 102.97 70 108.8954 N/A N/A N/A 72 109.8171 N/A N/A N/A 76 111.4869 N/A N/A N/A 80 112.9253 N/A N/A N/A 82 113.5579 N/A N/A N/A 84 114.1326 N/A N/A N/A.
86.00 N/A 114.7 N/A N/A 88 115.1085 N/A N/A N/A L.
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l Page 47 of 132 t
Supplemental Final Startup Report Procedure Number: N2-SUT-33-3 Drywell Piping Vibration-Corrected- Recorded ~
Data Data LStepf4.1.7- '0D-3 (01-14-88 0907)
WT FACTOR WT* FACTOR PCT WT-M1b/Hr M1b/Hr 106.250. 1.045 111.031 = 102.33% 97.93%
, 108.500 MWT RATED MWr % POWER 2417.780- 3323 72.76%
-% Power Rodline = .3 + .7*%WT. = 71.59% 73.83%
Step 4.1.2 Data Sheet 1 Page 14 -
Total Core Flow (M1b/Hr) = 112.651 '107.8 PCT WT (%) = 103.83% 99.35%
Step 4.2.5 OD-3 (01-12-88 1356)
'WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He-107.070 1.045 111.888 = 103.12% 98.68%
108.500 MWT RATED MWT % POWER 2086.340 3323 62.78% ,
% Power Rodline " .3+.7*%WT = 61.44% 63.37%
Data Sheet 2 Page 17 Total. Core Flow (M1b/Hr) = 112.44 107.60 PCT WT (%) = 103.63% 99.17%
CONCLUSION: THE TESTS FOR RECIRC. SYSTEM PIPING VIBRATION WERE MARGINALLY IMPROVED BECAUSE THE DATA WAS COLLECTED OVER A GREATER RANCE OF RECIRC. FLOW.
103.83% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1
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..1 Page 48 of 132 Supplemental Final 3tartup Report-Procedure Number: N2-SUT-74-3 Offgas System.
Corrected Recorded Data Data ,
Step 6.1.1' Data Sheet A'. Page 16 Total Core Flow (M1b/Hr) =. 111.72 106.91' PCT CORE FLOW = 102 97% 98.53%
I CONCLUSION: 102.97% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
INCREASED CORE FLOW EVENT HAS NO IMPACT ON VALIDITY OF RESULTS.
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Page 49 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-79-3 RPV Internals Vibration Corrected Recorded Data Data Step 4.1.1/6.1.16, OD-3 Date: '11-08-87 0833.
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/Hr 105.620 1.045 110.373 = 101.73% 97.35%
108.500 MWT RATED MWT % POWER 2209.220 3323 66.48%
% Power Rodline = .3+.7*%WT = 65.69% 67.74%
Step 4.2.1/6.2.1, OD-3 Date: 11-08-87 0833 WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr -
106.250 1.045 111.031 = 102.33% 97.93%
108.500 MWT RATED MWT % POWER 2417.780 3323 72.76%
% Power Rodline = .3+.7*%WT = 71.59% 73.83%
Step 4.3.1/6.3.1, OD-3 Date: 01-12-88 WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 106.020 1.045 110.791 = 102.11% 97.71%
108.500 .
MWT RATED MWT % POWER 2081.500 3323 62.64%
% Power Rodline = .3+.7*WT = 61.73% 63.66%
Step 4.1.4, Data Sheet 1 I
FACTOR Page 16 A JP LP 1.045 57.06 54.60 i B JP LP 1.045 55.39 53.00 Page 17 WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 107.350 1.045 112.181 = 103.39% 98.94%
108.500 , . .
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Page 50 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-79-3 RPV Internals Vibration Corrected Recorded Data Data Step 6.1.1/6.1.2 Data Sheet 2, Page 18 Date 11-04-87 Data Corrected on 11/8/87' FACTOR A JP'LP -1.045 13.84 13.24 B JP LP 1.045 11.16 10.68 WT FACTOR WT* FACTOR PCT WT 40.700 1.045 42.532 .. 39.20% 37.51%
108.500 MWT RATED MWT. % POWER 1333.000. 3323.000 40.11%
Rodline = 69.84%- 71.30%
Step 6.1.1/6.1.2 Data Sheet 2. Page 18 Additional FACTOR A JP LP 1.045 22.99 22.00 B JP LP 1.045 19.65 R1:8.80 WT FACTOR WT* FACTOR PCT WT 40.757 1.045 42.591 = 39.25% 37.56%
108.500 MWT RATED MWT % POWER.
1165.48 3323.000 35.07%
Rodline = 61.02% 62.30%
Step 6.1.1/6.1.2 Data Sheet 2. Page 18 Additional 2 FACTOR A JP LP 1.045 20.33 19.45 B JP LP 1.045 20.68 19.79 WT FACTOR WT* FACTOR PCT WT 39.200 1.045 40.964 = 37.75% 36.13%
108.500 MWT RATED MWT % POWER 1174.780 3323.000 35.35%
Rodline = 62.65% 63.94%
L Jun'
1 I
i Page 51 of 132 Supplemental Final Startup Report;
' Procedure Number: N2-SUT-79-3 RPV Internals Vibration Corrected Recorded' Data Data Step.6.1.7. Data Sheet 2,:Page 19 Dated 11/5/88
. Data. Corrected'on 11/8/87-FACTOR A JP LP 1.045 18.726' 17.92 B JP LP 1'045 18.225 17.44' WT FACTOR WT* FACTOR 51.767 1.045 54.097 = -49.86%- 47.71%
108.500 MWT s RATED MWT % POWER m 1428.160 3323.000. 42.98%
Rodline =. 66.22% 67 79%
Step 6.1.7. Data Sheet 3. Page 19 Additional __
FACTOR A JP LP 1.045 37.62 36.00 B JP LP- 1.045 35.53 34.00 WT- FACTOR WT* FACTOR M1b/Hr M1b/He 68.000 1.045 71.060 = 65.49% 62.67%'
108.500 MWT RATED MWT % POWER 1536.000 - 3323.000 46.22%
Rodline = 60,94% 62.57%
Step 6.1.12 Data Sheet 4, Page 20 Dated 11/5/88 Data Corrected on 11/8/87 FACTOR A JP LP 1.045 40.76 39.002 B JP LP 1.045 40.62 38 875 WT FACTOR WT* FACTOR M1b/Hr M1b/He 77.899 1.045 81.405 = 75.03% 71.80%
108.500 MWT RATED MWT % POWER J 1656.420 3323.000 49.85% i Rodline = 60.41% 62.11% )
l 1
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- j. Page 52 of'132 Supplemental Final Startup Report Procedure Number: N2-SUT-79-3 RPV Internals Vibration Corrected Recorded Data Data
~
Step 6.1.17 Data Sheet 5, Page 21 Dated 11/8/88 FACTOR A JP LP 1.045 56.71 54.27 B JP LP 1.045 55.65 53.25
. WT FACTOR WT* FACTOR 107.000 1.045 111.815 = 103.06% 98.6T%
108.500 MWT RATED MWT % POWER 2209.220 3323.000 66.48%
Rodline = 65.09% 67.13%
Step 4.2.3, Data Sheet 6 .
. FACTOR Page 22 A JP LP 1.045 56.95 54.5 B JP LP 1.045 55.91' 53.5 WT FACTOR WI* FACTOR 107.5 1.045 112.338 = 103.54% 99.08%
108.500 Step 6.2.2, Data Sheet 7. Page 24 Dated 1/14/88 FACTOR A JP LP 1.045 56.18 53.76 B JP LP 1.045 56.90 54.45 WT FACTOR WI* FACTOR 107.7 1.045 112.547 = 103.73% 99.26%
108.500 MWT RATED MWT % POWER 2417.780 3323.000 72.76%
Rodline = 70.91% 73.14%
Step 6.2.8, Data Sheet 8. Page 25 Dated 1/14/88 FACTOR A JP LP 1.045 13.17 12.60 B JP LP 1.045 67.40 64.50 WT FACTOR WI* FACTOR 49.900 1.045 52.146 = 48.06% 45.99%
108.500 ,,
MWT RATED MWT % POWER 1534.670 3323.000 46.18%
Rodline = 72.57% 14.26%
ami
Page 53 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-79-3 RPV Internals Vibration Corrected Recorded Data Data Step 6.2.8, Data Sheet 8, Page 25 1/14/48 Additional 1 FACTOR A JP LP 1.045 9.48 9.07 B JP LP 1.045 58.42 55.90 WT FACTOR WT* FACTOR 47.400 1.045 49.533 = 45.65% 43.69%
108.500 MWT RATED MWT % POWER 1359.390 3323.000 40.91%
Rodline = 66.03% 67.53%
Step 6.2.8, Data Sheet 8 Page 25 1/14/88 Additional 2 .
FACTOR A JP LP 1.045 3.24 3.10 B JP LP 1.045 47.44 45.4 WT FACTOR WT* FACTOR 42.680 1.045 44.601 = 41.11% 39.34%
'108.500 MWT RATED MWT % POWER 1226.970 3323.000 36.92%
Rodline = 62.82% 64.18%
Step 4.3.3, Data Sheet 9 Page 26 FACTOR A JP LP 1.045 53.30 51 l B JP LP 1.045 58.52 56 Page 27 WT FACTOR WI* FACTOR 107.500 1.045 112.338 = 103.54% 99.08%
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Page 54 of 132-Supplemental Final Startup Report Procedure Number: N2-SUT-79-3~RPV Internals Vibration Corrected Recorded Data Data Step 6.3.1/6.3.2, Data Sheet 10, Page 28 FACTOR A JP LP 1.045 57.27 54.8 B JP LP 1.045 55.49 53.1 WT FACTOR WT* FACTOR 107.600 1.045 112.442 = 103.63% 99.17%
108.500 MWT RATED MWT % POWER 2081.500 3323.000 62.64%
Rodline = 61.09% 63.01%
Step 6.3.8. Data Sheet 11. Page 29 ,
FACTOR A JP LP 1.045 19.95 19.09 B JP LP 1.045 20.57 19.68 WT FACTOR WT* FACTOR 38.690 1.045 40.431 = 37.26% 35.66%
108.500 MWI RATED MWT % POWER 1085.400 3323.000 32.66%
Rodline = 58.24% 59.43%
CONCLUSION: 4 CAN JOSE SHALL USE THE CORRECTED DATA (FACTOR 1.045) FOR ,
VDRATION DATA ANALYSIS, SEE ATTACHMENT 1.
MAX CORRECTED CORE FLOW DOCUMENTED IN THIS TEST =103.73% RATED.
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Page 55 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-1-5 Chemistry .
I Corrected Recorded -
Data Data i Step 4.1.4/6.1.1, OD-3 (01-19-88 1011)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 55.000 1.045 57.475 = 52.97% 50.69%
108.500 MWT RATED MWT % POWER 2082.130 3323.000 62.66%
% Power Rodline = .3+.78%WT = 93.41% 95.68%
CONCLUSION: CALCULATED RODLINE IS SLIGHTLY LESS THAN 95% BUT THE TEST CONDITION IS WITHIN TC-5 WINDOW AS DEPICTED ON FIG. 14.2-5 0F ,
NINE MILE POINT 2 FINAL SAFETY ANALYSIS REPORT.
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Page 56 of 132 Supplemental Final Startup Report
. Procedure Number: N2-SUT-12-5 APRM Calibration ]
Corrected Recorded Data Data Step 4.1.2 OD-3 (01-18-88 2100)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 59.060 1.045 61.718 = 56.88% 54.43%
108.500 MWT- RATED MWT % POWER 2'130.870 3323.000 64.12%
%' Power Rodline =~ .3+.7*%WT = 91.85% 94.16%
Step 4.1.2/6.1.1 Reactor Physics Surveillance Procedure No. N2-RPSP-1 / P-1 Step 7.1.1.2 WT (mlb/hr) = 61.12 59.06 PCT WT = 56.88% 54.43%
CONCLUSION: THE CORRECTED CORE FLOW MOVED THE TEST CONDITION SLIGHTLY BELOW THE TEST CONDITION 5 WINDOW AS DEPICTED ON FIG. 14.2-5 0F NINE MILE POINT 2 FINAL SAFETY ANALYSIS REPORT. HOWEVER THE INCREASED CORE FLOW EVENT HAS NO. IMPACT ON VALIDITY OF THE TEST RESULTS.
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Page 57 of 132 l- Supplemental Final Startup Report Procedure Number: N2-SUT-16-5 Selected Process Temperatures and Water Level Measurements - Natural Circulation Corrected Recorded Data Data Step 4.1.2 OD-3 (01-20-88 0453)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 52.540 1.045 54.904 = 50.60% 48.42%
, 108.500 MWT RATED MWT % POWER 2100.000 3323.000 63.20%
% Power Rodline = .3+.7*%WT = 96.60% 98.90 Step 4.1.2 OD-3 (02-09-88 '0151) -Retest 1 WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 54.490 1.045 56.942 = 52.48% 50.22%
108.500 MWT RATED MWT % POWER 2102.560 3323.000 63.27%
% Power Rodline = .3+.7*%WI = 94.81% 97.11 Step 6.1.2 OD-3 (02-09-88 0409)
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 30.000 1.045 31.350 = 28.89% 27.65%
108.500 MWT RATED MWT % POWER 1303.720 3323.000 39.23%
% Power Rodline = .3+.7*%WT = 78.11% 79.49 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
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Page 58 of 132
,. Supplemental Final Startup Report-Procedure Numbar: N2-SUT-19-5 Core Performance l
corrected Recorded.
Data Data i
Step 6.1.1 OD-3 (02-08-88 0046)
WT FACTOR WT* FACT 0k PCT WT i M1b/Hr M1b/He
$4.180 1.045 f 56.618 = '52.18% 49.94% i 108.500 MWT RATED MWT % POWER 2118.220 3323.000 63.74%
% Power Rodline = .3+.7*%WT = 95.82% 98.14%
Step 6.1.2 Reactor Physics Surveillance Procedure No. N2-RPSP-1 / P-1 Step 7.1.1.2 WT (M1b/Hr) = 56.74 54.30 PCT WT = 52.30% 50.05%
Procedure Number: N2-SUT-19-5 Core Performance Step 6.2.1 OD-3 (02-09-88 1103)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 30.490 1.045 31.862 = 29.37% 28.10%
108.500 MWT RATED MWT % POWER 1384.390 3323.000 41.66%
% Power Rodline = .3+.7*%WT = 82.41% 83.87%
Step 6.2.2 Reactor Physics Surveillance Procedure No. N2-RPSP-1 /P-1 Step 7.1.1.2 WT (M1b/hr) = 31.86 30.49 PCT WG = 29.36% 28.10%
CONCLUSION: CORE FLOW IS USED BY THE PROCESS COMPUTER TO DETERMINE THE MCPR LIMIT. THE PROCESS COMPUTER CALCULATED CRITICAL BUNDLE POWER WILL BE LOWER THAN ACTUAL DUE TO THE HIGHER FLOW RATE WHICH ACTUALLY EXISTED IN THE BUNDLE. THIS RESULTS IN CONSERVATIVE L MONITORING OF THE MCPR FOR EACH FUEL BUNDLE. THERE ARE NO OTHER IMPACTS TO THE TEST RESULTS OF THIS TEST PROCEDURE CAUSED BY THE INCREASED CORE FLOW EVENT.
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Page 59 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-22-5 Pressure Regulator I 1
t Corrected Recorded Data Data Page 13 Step 7.1.4.2 Verified Extrapolated Peak Flux See DS 3A See DS 3A Margin in Data Sh. 3 is > 7.5% Below Below Page 14/17 Step 7.1.6/7.2.6 Maintain a plot of the Peak Pressure and Extrapolated Peak Neutron Flux along the 100% See Att'd In Test rodline. DS 7.8,9,10 Procedure Page 16 Step 7.2.4.2 Verified Extrapolated Peak Flux .See DS 6 See DS 6 Margin in Data Sh. 6 is > 7.5% Below Below Data Sheet Page No. Parameter Date 1 24 Core Flow 01/18/88 61.66 59.00 2 25 Core Flow 01/18/88 61.66 59.00 3A 26 Extr. Mars. APRM 01/19/88 A Regulator +
10 psi Step 42.14% 43.96%
B Regulator + -
10 psi Step 40.62% 42.47%
4 28 Core Flow 01/19/88 58.52 56.00 5 29 Core Flow 01/20/88 55.39 53.00 6 30 A Regulator +
10 psi Step 46.38% 47.00%
B Regulator +
10 psi Step 46.63% 47.25%
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Page 60 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-22-5 Pressure Regulator Corrected Recorded.
Data Data Step 4.1.1/4.1.4 OD-3 Date 01/18/8E 2240 WT FACTOR WT* FACTOR 58.980 1.045 61.634' = 56.81% 54.36%
108.500-MWT RATED MWT % POWER 2131.660 3323.000 64.15%
Rodline =- 91.95% 94.26%
Step 6.1.5' Getars P123 WT FACTOR WT* FACTOR 58.980 1.045 61.634 = 56.81% 54.36%
108.500 -
100%'Rodline S. S. Power = 69.76% 68.10%
100% Rodline APRM Flux Increase = 6.09% 5.94%
100% Rodlino Peak Power = 75.85% 74.04%
DS3A Extrapolated Margin 42.15% 43.96%
Step 6.1.15 Getars P184 WT FACTOR WT* FACTOR 58.980 1.045 61.634 = 56.81% 54.36%
108.500 .
100% Rodline S. S. Power = 69.76%. 68.10%
100% Rodline APRM Flux Increase = 7.61% 7.43%
100% Rodline Peak Power = 77.38% 75.53%
DS3A Extrapolated Margin 40.62% 42.47%
Step 4.2.5 00-3 Date 01/19/88 2115 WT FACTOR WT* FACTOR 53.120 1.045 55.510 = 51.16% 48.96%
108.500 MWT RATED MWT % POWER 2074.410 3323.000 62.43%
Rodline = 94.85% 97.13%
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Page 61 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-22-5 Pressure Regulator Corrected Recorded Data Data Step 6.2.1.2 OD-3 Date 01/20/88 0235 Step 6.2.7 WT FACTOR WT* FACTOR 52.660 1.045 55.030 = 50.72% 48 . 5 3%' '
108.500 MWT RATED MWT % POWER 2132.470 3323.000 64.17%
Rodline = 97.97% 110.31%
Getars P913
.WT FisCTOR WT* FACTOR 52.660 1.045 55.030 = 50.72% 48.53%
108.500 -
100% Rodline S. S. Power = 65.50% 65.00%
100% Rodline APRM Flux Increase = 6.12% 6.00%
100% Rodline Peak Power = 71.63% 71.00%
Data Sheet 6 . Extrapolated Margin 46.37% 47.00%
Step 6.2.15 Getars P921 WT FACTOR WT* FACTOR 52.660 1.045 55.030 = 50.72% 48.53%
108.500 100% Rodline S. S. Power = 65.50% 65.00%
100% Rodline APRM Flux Increase = 5.87% 5.75%
100% Rodline Peak Power = 71.37% 70.75%
Data Sheet 6 Extrapolated Margin 46.63% 47.25%
CONCLUSION. TEST RODLINE IN SECTION 6.1 WAS LESS THAN REQUIRED BUT CAN BE ACCEPTED BASED ON EXTRAPOLATED FLUX TRIP MARGIN IS WITHIN REQUIRED LIMIT: THE SELECTION OF THE TEST ROD LINE WAS TO RESTRAIN THE PLANT OPERATION CONDITION WITHIN 100% LOAD LINE LIMIT.
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THE CORRECTED TEST RESULT MEETS THE ACCEPTANCE CRITERIA. CORE FLOW DATA IN THIS PROCEDURE SHALL BE CORRECTED WITH A FACTOR OF 1.045 FOR APPLICATION.
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Page 66 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-23-5 Feedwater System Corrected Recorded Data Data Step 4.1.7 OD-3 Dated 02/10/88 1326 WT FACTOR WT* FACTOR PCT WT 56.840 1.045 59.398 ,, 54.74% 52.39%
108.500 MWT RATED MWT % POWER 2162.000 3323.000 65.06%
Rodline = 95.23% 97.59%
Step 4.2.7 OD-3 Dated 02/08/88 2207 WT ~ FACTOR WT* FACTOR PCT WT 53.670 1.045 56.085 = 51.69% 49.47%
108.500 MWT RATED MWT % POWER 2124.620 3323.000 63.94%
Rodline = 96. 60% -- 98.93%
Step 4.3.7 OD-3 Dated 02/10/88 1829 WT FACTOR WT* FACTOR PCT WT
~57.070 1.045 59.638 = 54.97% 52.60%
108.500 ,
MWT RATED MWT % POWER 2150.660 3323.000 64.72%
Rodline = 94.57% 96.86%
DATA SHEET PAGE NO. FACTOR WT* FACTOR % RATED WT(MLB/HR) 1A 18 1.045 59.461 54.80% 56.90 18 20 1.045 56.430 52.01% 54.00 1C 22 1.045 59.544 54.88% 56.98 2A 23 1.045 59.565 54.90% 57.00-28 24 1.045 54.863 50.56% 52.50 2C 25 1.045 59.565 54.90% 57.00 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
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Page 67 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-24-5 Turbine Valve Surveillance Corrected Recorded Data Data Step 4.1.4 OD-3 Dated 01/19/88 0825 WT FACTOR WT* FACTOR PCT WT 55.270 1.045 57.757 = 53.23% 50.94%'
108.500
. MWT RATED MWT % POWER ,
2082.590 3323.000 62.67% ):
Rodline = 93.17% 95.45%
DATA SHEET PAGE NO. FACTOR WT* FACTOR % RATED WT(MLB/HR) 1 11 1.045 58.259 53.69% 55.75' 2 13 1.045 57.715 53.19%- 55.23 -
STEP NO. DOC TYPE FACTOR WT* FACTOR % RATED WT(MLB/HR) 4.1.4 P-1 1.045 57.715 53.19% 55.23 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS. THE CORE FLOW AND RECIRC LOOP FLOW DATA IN THE PROCEDURE SHALL APPLY A CORRECTION FACTOR OF 1.045 FOR THE TRUE VALUE.
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Page 68 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-30-5 Reactor Recirculation System Corrected Recorded Step No. Page Tyh.e Parameter Unit . Data Data 4.1.3 9 DSI. WT M1b/He 56.85 54.40 A LP Flow M1b/Hr- 28.74 27.50 B LP Flow- M1b/Hr 28.74 27.50 6.1.1 11 DS2 WT M1b/He 31.35 30.00 A LP Flow M1b/Hr 15.78 15.10 B LP Flow M1b/He 15.88 15.20 /
6.1.2 13 D33 WT M1b/He 24.82 23.75 True WT M1b/Hr 37.24 35.637 A LP Flow M1b/He 31.03 '29.69 B LP Flow M1b/He 6.21 5.947.
6.1.3 15 DS4 WT M1b/Hr 50.62 48.44 A LP Flow M1b/Hr 25.50 24.40 B LP Flow M1b/Hr 25.39 24.30 6.1.1 NAT. CIRC P-1 WT M1b/Hr 31.35 30.00 ~
PRE START P-1 WT M1b/He 31.86 30.49 OD-3 WT M1b/He 31.86 30.49 6.1.2 A START P-1 VT M1b/He 24.82 23.75 OD-3 WT M1b/Hr 24.82 23.75 6.1.3 B START P-1 WT M1b/He 50.45 48.28 OD-3 WT M1b/He 50.62 48.44 l
CONCLUSION: ANY USER TO THIS PROCEDURE SHALL APPLY A CORRECTOR FACTOR OF 1.045 TO THE CORE FLOW DATA IN THIS PROCEDURE. NO IMPACT TO THE VALIDITY OF THE TEST RESULT.
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I Page 69 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-33-5 Drywell Piping Vibration corrected Recorded Data Data Step 4.1.6 OD-3 Dated 01/18/88 1956 WT FACTOR WT* FACTOR PCT WT 58.750 1.045 61.394 = 56.58% 54.15%.
108.500 MWT RATED MWT % POWER 2136.530 3323.000 64.30%
Rodline = 92.37% 94.69%
DATA SHEET PAGE NO. FACTOR WI* FACTOR % RATED WT(MLB/HR) 1 11 1.045 61.655 56.82% 59.00 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF TEST RESULT.
THE CORE FLOW AND RECIRC LOOP FLOW DATA IN THE PROCEDURE SHALL APPLY A CORRECTION FACTOR OF 1.045 FOR THE TRUE VALUE. 56.58%
CORE FLOW IS SLIGHTLY HIGHER THAN STEP 4.1.6 SPECIFIED BUT CAN BE ACCEPTED PER ATTACHMENT 1.
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Page 70 of 132 Supplemental Final Startup Report Procedure' Number: N2-SUT-77-5 BOP Piping Vibration Corrected Recorded Data Data Step 4.2.3 0D-3 Dated 01/19/88 1012 WT FACTOR WT* FACTOR PCT WT 55.040 1.045 57.517 -
53.01% 50.73%-
108.500 MWT RATED MWT % POWER 2077.280 3323.000 62.51%
Rodlina = 93.15% 95.42%
Step 4.3.5 OD-3 Dated 02/10/88 1845 WT. FACTOR WT* FACTOR PCT WT 56.680 1.045 59.231 = 54.59% 52.24%
108.500 ..
MWT RATED MWT % POWER 2159.380 3323.000 64.98%
Rodline = 95.26% 97.62%
DATA SHEET PAGE NO. FACTOR WI* FACTOR % RATED WT(MLB/HR)
(M1b/Hr)
IB 18 1.045 57.98 53.43% 55.48 1B 24 1.045 59.57 54.90% 57.00 ,
CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
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1 Page 71'of 132 Supplemental Final Startup Report Procedure Number:N2-SUT-1-6 Chemistry Corrected Recorded Data Data Step 4.2.2 required no Core Flow adjustment to (MLB/HR) (MLB/HR) maintain steady state condition for Moisture Carryover test, the Data Sheet 3 provided proof. I Step 6.2.1.1 The Core Flow recorded on Data Sheet 3, p47, needs to be corrected by multiplying with a factor of 1.045. This is also applied to the' data 113.28 108.40 source OD-3 in Appendix II of the test 112.83 107.97 procedure. 112.79 107.93 112.83 107.97 112.87 108.01 112.50 107.66 113.43 108.55 112.91 108.05 ,
, 112.46 107.62
. 112.95. 108.09-112.13 107.30 113.69 108.79 112.50 107.66 112.01- 107.19 112.79 107.93 112.13 107.30 110.86 106.09 113.24 108.36 113.74 108.84 MAX CORE FLOW 113.74 MAX CORE FLOW (%) 104.83%
CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
104.83% MAI CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
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Page 72 of 132
. Supplemental Final Startup Report Procedure Number: N2-SUT-2-6 Radiation Measurements Corrected Recorded Data Data Step 4.1.5 OD-3 (02-24-88 0822)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 106.02 1.045 110.791 = 102.11% 97.71%
108.500 MWT . RATED MWT % POWER 3249.500 3323.000 97.79%
% Power Rodline = .3+.7*%WT = 96.36% 99.38% ;
Step 4.2.4 OD-3 (02-26-88 0221)
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 107.890' 1.045 112.745 = 103.91% 99.44%
108.500 MWT RATED MWT % POWER .j 3314.130 3323.000 99.73%
% Power Rodline = .3+.7*%WT = 96.36% 100.13%
1 Step 6.1.2 N2-RTP-4 DATA corrected Recorded l Proc. No. Date Parameter Unit Data Data N2-RTP-4 02-24-88 Core Flow MLB/HR 109.36 104.65 N2-RTP-4 02-25-88 Core Flow MLB/HR 110.71 105.94 ,
N2-RTP-4 02-25-88 Core Flow MLB/HR 112.79 107.93 N2-RTP-4 02-25-88 Core Flow MLB/HR 110.71 105.94 MAX CORE FLOW 112.79 MLB/HR 103.95%
CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
103.95% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
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Page 73 of 132 .l Supplemental Final Startup Report Procedure Number: N2-SUT-11-6 LPRM Calibration Corrected Recorded Data Data Step 4.1.1/6.1.1 OD-3 (02-26-88 0234)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 107.770 1.045 112.620 = 103.80% 99.33%
108.500 MWT RATED MWT % POWER 3303.810 3323.000 99.42%
% Power Rodline = .3+.7*%WT = 96.85% 99.89%
CONCLUSION: ' INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
103.8% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
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Page 74 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-12-6 APRM Calibration Corrected Recorded Data Data Step 4.1.2 OD-3 (02-26-88 2332)
.M1b/Hr M1b/He 107.820 1.045 -112.672 = 103.85% 99.37%
108.500 MWT RATED MWT % POWER 3274.160- 3323.000 98.53%
% Power Rodline = .34.7*%WT = 95.95% 98.96%
Step 6.1.1 Reactor Physics Surveillance Procedure No. N2-RPSP-1 / P - 1 Step 7.1.1.2 WT (M1b/Hr) = 112.46- 107.62 PCT WT = 103.65% 99.19%
Step 9.1.2 Core Flow: WT must be < or = 108.5 M1bs/HR mass f'.ow.
The corrected core flow exceeds the acceptance criteria of the RPSP-1 but can be accepted as is based on Attachment'1.
CONCLUSION: -INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.-
'103.85% CORE FLOW CAN 8E ACCEPTED AS IS PER ATTACHMENT 1. .
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Supplemental Final Startup Report Procedure Number: N2-SUT-13-6 Process Computer.
Corrected Recorde'd Data Data Step 6.2.10.1 OD-3 (03-03-88 2001)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr l 104.300 1.045 108.993 = 100.45% 96.13%
108.500 l MWT RATED MWT % POWER 3253.630 3323.000 97.91%
% Power Rodline = .3+.7*%WT = 97.60% 100.64%
Step 6.1.1.6 P-1 (03-04-88 0552)' Seq. No. 21 & OD-11 WT or P1WT. FACTOR WT* FACTOR PCT WT ,
M1b/He M1b/Hr 107.150 1.045- 111.972 = 103.20% 98.76%.
108.500 MWT RATED MWT % POWER 2408.000 3323.000 72.46% ~ ~ ~
% Power Rodline = .3+.7*%WT = 70.88% 73.10%
OD-11 (03-04-88 0638 to 0659)
Step 6.1.1.9 to 6.1.1.20 P1WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 106.33 1.045 111.113 = 102.41% 98.00%
108.500 PICTP RATED MWT % POWER 2409.800 3323.000 72.52%
% Power Rodline = .3+.7*%WT = 71.32% 73.55%
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Page '/6 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-13-6 Process Computer i
Corrected Recorded Data Data Step 6.1.1.6 of 6.1.1.13 P-1 (03-04-88 0925) SEQ. No. 25 Step 6.1.1.13 OD-11's (03-04-88 0927 to 1019)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 105.940 1.045 110.707 = 102.03% 97.64%
108.500 MWT or PICTP RATED MWT % POWER 2393.200 3323.000 72.02%
% Power Rodline = .3+.7*%WT = 71.01% 73.23%
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Step 6.1.1.18 P-1 (03-04-88 1047) SEQ. NO. 27 And OD-11's WT or P1WT FACTOR WI* FACTOR PCT WT M1b/Hr M1b/Hr 105.940 1.045 110.705 = 102.03% 97.64%
108.500 MWT RATED MWT % POWER 2401.400 3323.000 72.27%
% Power Rodline " .3+.7*%WT = 71.25% 73.48%
Step 6.1.1.18 P-1 (03-04-88 1055) SEQ. NO. 28 And OD-11's WT or P1WI FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 106.290 1.045 111.072 = 102.37% 97.96%
108.500 MWT RATED MVT % POWER 2391.700 3323.000 71.97%
% Power Rodline = .3+.7*%WT = 70.80% 73.02%
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Page 77 of 132 Supplemental Final Startup Report Procedure Number: :N2-SUT-13-6 Process Computer Corrected Recorded Data Data Step 6.1.1.18 P-1 (03-04-88 1102) SEQ. NO. 29 l And OD-11's WT FACTOR WT* FACTOR- PCT WT M1b/He M1b/He
. 105.080 1.045 109.807 m. 101.20% 96.85%
108.500 MWT RATED MWT % POWER 2393.400 3323.000 72.03%
% Power Rodline = .3+.7*%WT = 71.42% 73.65%
- i-Step 6.1.1.18 P-1 (03-04-88 1137) SEQ. NO. 30 And OD-11's WT FACTOR WT* FACTOR PCT WT M1b/He M1b/Hr 107.305 1.045 112.134 = 103.35% 98.90%
108.500 MWT RATED MWT % POWER 2404.200 3323.000 72.35% ,
% Power Rodline = .3+.7*%WT = 70.69% 72.91%
Step 6.2.1 P-1 (03-01-88 2256) SEQ. NO. 11 WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 51.600 1.045 53.922 = 49.70% 47.56%
108.500 MWT RATED MWT % POWER 1977.000 3323.000 59.49% ;
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% Power !
Rodline = .3+.78%WT
= 91.83% 94.00%
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Page 78 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-13-6 Process Computer Corrected Recorded Data Data j Step 6.2.4 OD-4 (03-01-88) ]
TIME PARAMETER' i 2311 WT (MLB/HR) 54.13 51.8 '
2312 WT (NLB/HR) 53.92 51.6 l 2312 WT (MLB/HR) 53.71 51.4 2313 WT (NLB/HR) 53.71 51.4 2313 WT (NLB/HR) 53'82
. 51.5 I 2314 WT (MLB/HR) 53.82 51.5 )
2314 WT (MLB/HR) 54.03 51.7 2314 WT (NLB/HR) 53.82 51.5 2315 WT (MLB/HR) 53.82- 51.5 2315 WT (NLB/HR) 53.71 51.4 Step 6.2.4 OD-5 (03-01-88 2316)
WT (MLB/HR)= 53.80 51.48 Step 6.2.8 OD-6 (03-01-88) l TIME PARAMETER 2256 WT (MLB/HR)' 53.80 51.48 Step 6.2.8 OD-6 (03-02-88)
TIME PARAMETER ;
0003 WT (MLB/HR) 53.68 51.37 i
Step 6.2.10.3 OD-3 (03-03-88 2116)
WT PACTOR WTAFACTOR PCT WT M1b/He M1b/He 107.110 1.045 111.930 = 103.16% 98.77% ,
108.500 l MWT RATED MWT % POWER 2365.160 3323.000 71.18%
% Power Rodline = .3+.7*%WT = 69.63% 71.87% .
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Page '79.of 132 Supplemental Final Startup Report.
Procedure Number: N2-SGT-13-6 Process Computer Corrected Recorded Data Data Step 6.2.10.4 P-1 (03-03-88 2118) SEQ. NO. 14 ,
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 106.720 1.045 111.522 = 102.79% 98.36%
108.500 MWT RATED MWT .% POWER 2353.000 3323.000 70.81%
% Power' Rodline'= . 3+.7*%WT = 69.46% .71.63%
Step 6.2.10.6 -OD-4 (03-03-88) i
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TIME PARAMETER
, 2137 WT (MLB/HR) 113.49 108.6 2137 .WT (MLB/HR) 113.28 108.4 2137 'WT (MLB/HR) 113.28 108.4 2137 WT (MLB/HR) .112.76 ~1 07.9-2138 WT (MLB/HR) 112.76' 107.9 2138 WT (MLB/HR) 112.65 107.8 2138 WT (MLB/HR) 112.55 107.7 !
i Step 6.2.10.8 OD-5 (03-03-88 2151) 112.55 107.7 !
WT (MLB/HR)=
. I Step 6.2.10.10 OD-6 (03-03-88 2118) ,
WT (MLB/HR)= 112.55 107.7 Step 6.2.11.2/6.2.11.4 OD-3 )
DATE TIME PARAMETER 03-02-88 0105 WT-(MLB/HR) 53.84 51.52 0208 WT (MLB/HR) 85.19 81.52 03-05-88 0614 WT (MLB/HR) 77.31 73.98 I I
0641 WT (MLB/HR) 112.25 107.42 i
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-1 Page 80 of 132 Supplemental Final Startup Report 1
Procedure Number: N2-SUT-13-6 Process Computer Corrected Recorded ,
Data' Data !
Step 6.2.11.6 P-1 (03-02-88 0210) SEQ. 13 WT (MLB/HR)= 85.44 81.76 Step 6.2.11.8 OD-4 (03-02-88)
TIME . PARAMETER 0218 WT (MLB/HR) 84.85 81.2 0218 WT (MLB/HR) 85.17 81.5 0218 WT (MLB/HR) 85.38 81.7 0219 WT (MLB/HR) 85.27 81.6 0219 WT (ML8/HR) 85.06 81.4 .
0219- WT (MLB/HR) 84.96 81.3 0219 WT (MLB/HR) 85.06 81 4 0220 WT (MLB/HR) 85.17 81.5 Step 6.2.11.10 OD-5 (03-02-88 0220)
WT (MLB/HR)= 85.40 81.72 Step 6.2.11.12 OD-6 (03-02-88 2110)
WT (MLB/HR)= 85.40 81.72 Step 6.3.1 P-1 (02-27-88 0031) SEQ. NO. 3 WT or P1WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 107.620 1.045 112.463 = 103.65% 99.19%
108.500 MWI or PICTD RATED MWT % POWER 3261.000 3323.000 98.13%
% Power Rodline = .3+.7*%WT = 95.69% 98.69%
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1 Page 81 of 132
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Supplemental Final.Startup Report Procedure Number: N2-SUT-13-6 Process Computer Corrected Recorded Data Data Step 6.3.6 Daily NSS Core Performance Los I
l (02-27-88 0000) SEQ. NO. 19 WT or P1WT FACTOR WT* FACTOR PCT WT M1b/He M1b/Hr 108.670 1.045 113.560 = 104.66% 100.16%
108.500 MWT'or PICTP RATED MWT % POWER 3286.0000 3323.000 98.89%
% Power Rodline = .3+.78%WT
= 95.76% 98.78%
Step 6.4.2 P-1 (03-01-88 0706) SEQ. NO. 13 WT or P1WT FACTOR WT* FACTOR PCT WT _
M1b/Hr M1b/He 107.460 1.045 112.296 = 103.50% 99.04%
108.500 MWT or PICTP RATED MWT % POWER 3301.000 3323.000 99.34%
% Power Rodline * .3+.7*%WT
= 96.96% 100.01%
Step 6.4.4 Daily NSS Core Performance Log (03-01-88 0706) SEQ. NO. 1 WT or P1WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 106.480 1.045 111.272 = 102.55% 98.14%
108.500 MWT or PICTP RATED MWT % POWER 3280.000 3323.000 98.71%
% Power Rodline = = 96.97% 100.01%
.3+.7*%WT Step 6.4.8 OD-6 (03-01-88 0706) l WT = 112.30 107.46 Max WT = 104.66% Rated Core Flow CONCLUSION: 104.66% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
INCREASED CORE FLOW EVENT HAS NO IMPACT ON VALIDITY OF RESULTS. ,
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Page 82 of 132 Supplemental Final Startup Keport Procedure Number: N2-SUT-16-6 Water Level Measurements and Selected Process h Temperatures Corrected . Recorded Data Data Step 4.1.2- OD-3 (02-11-88 0351)
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 49.A50 1.045 51.675 = 47.63% 45.58%
. 108.500 MWT RATED MWT % POWER 1917.060 3323.000 57.69%
% Power Rodline = .3+.7*%WT = 91.08%- 93.19%
Step 4.1.3 Data Sheet 1 __
Total Core Flow (B22-R613) (P603)= 51.73 (M1b/Hr) 49.5 Step 6.1.2 OD-3 (02-12-88 1632)
WT FACTOR -WT* FACTOR PCT WT M1b/Hr M1b/Hr 70.740 1.045 73.923 = 68.13% 65.20%
108.500 MWT RATED MWT % POWER 2464.000 3323.000 74.15%
% Power Rodline " .3+.7*%WT = 95.44% 98.03%
Step 6.1.2 The core flow specified in this step is 65(+2,-2)%, but the corrected value is 68.1%. This deviation does not affect the test result.
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Page 83 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-16-6 Water Level Measurements and Selected Process Temperatures Corrected Recorded Data Data Step 6.1.3 Data Sheet 2 Total Core Flow (D22-R613) (P603)= 74.20 (M1b/Hr) 71.00 Step 6.1.4 OD-3 (02-13-88 2107)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/Hr 91.130 1.045 95.231 - 87.77% 83.99%
108.500 MWT RATED MWT % POWER 2855.590 3323.000 85.93%
% Power ~
Rodline = .3+.7*%WT = 93.98% 96.78%
Step 6.1.5 Data Sheet 3 Total Core Flow (B22-R613) (P603)= 95.10 (M1b/Hr) 91.00 Step 6.1.6 OD-3 (02-24-88 0448)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 106.600 1.045 111.397 - 102.67% 98.25%
108.500 MWT RATED MWT % POWER 3269.810 3323.000 98.40%
% Power Rodline = .3+.7*%WT
= 96.59% 99.62%
Step 6.1.7 Data Sheet 4 Total Core Flow (B22-R613) (P603)= 111.82(M1b/Hr) 107.00 Step 4.2.2 OD-3 (03-01-88 0933)
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/Hr 106.720 1.045 111.522 = 102.79% 98.36%
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I Page 84 of 132 Supplemental Final Startup Report'
- Procedure Number: N2-SUT-16-6 Water Level Measurements and . Selected Process Temperatures Corrected Recorded Dsta - Data Step 6.2.2 OD-3 (03-01-88 .1140)
WT FACTOR WT* FACTOR PCT WT-M1b/He M1b/Hr.
55.00 1.045 57.475 , 52.97% .50.69%
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108.500 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON- VALIDITY OF RESULTS. SEE ATTACHED CORRECTED FIGURE ' FOR PAGE 92 0F ' FINAL POWER ASCENSION TEST REPORT.
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Page 86 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-18-6'Tip Uncertainty Corrected Recorded Data Data Core Flow data was recorded in Process Computer OD-3 and P-1 Edits only in this test:
Step No. Doc. Type Date Parameter Unit 6.1.1.2 OD-3 02-14-88 WT MLB/HR 93.23 89.22 6.1.1.3 OD-3' 02-14-88 WT MLB/HR 93.15 89.14 6.1.1.3 P-1 02-14-88 WT MLB/HR 93.23 89.22 6.1 2.1 P-1 02-15-88 WT MLB/HR 93.64 89.61 6.1.2.10 P-1 02-15-88 WT MLB/HR 93.36 89.34 ,
CONCLUSION: CORE FLOW DATA WAS NOT USED FOR DATA ANALYSIS OR EVALUATION OF THE ACCEPTANCE CRITERIA. THEREFORE, THE ONLY IMPACT TO THIS TEST -BY THE INCREASED CORE FLOW EVENT IS CORE FLOW DATA CORRECTION, AS NOTED.ABOVE.
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l Page 87 of 132 Suppismental Final Startup Report Procedure Number: N2-SUT-19-6 Core Performance-Corrected Recorded i Data Data J Step 6.1.1 OD-3 (02-27-88 0041)
WY FACTOR WT* FACTOR PCT WT M1b/Mr M1b/Hr 107.890 1.045 112.745 =
103.91% 99.44%
108.500 MWI RATED MWT % POWER 3265.910 3323.000 98.28%
% Power Rodline = .3+.7*%WT = 95.66% 98.67 Step 6.1.1 Reactor Physics Surveillance Procedure No. N2-RPSP-1 / P-1 Step 7.1.1.2 WT (M1b/Hr) = 112.46 107.62 PCT WT = 103.65% 99.19%
Step 9.1.2 Core Flow: WT must be < or = 108.5 M1bs/Hr mass flow.
The corrected core flow exceeds the acceptance criteria of the RPSP-1 but can be accepted as is based on Increased Core Flow analysis.
Step 7.1.1.4 Core flow is less than or equal to 108.5 M1b/Hr. UNSAT Step 8.1.4 (Level 1 Criteria) Core flow should not exceed its rated value.UNSAT Step 8.1.2 (Level 1) Core flow is used by the process computer to determine the MCPR limit, the process computer calculated critical bundle power will be lower than actual due to the higher flow rate which actually existed in the bundle. This results in conservative monitoring of the MCPR for each fuel bundle.
CONCLUSION: INCREASED CORE FUAi CENERATED A LEVEL 1 CRITERION VIOLATION BUT 1 103.91% CORE FLOh CAN BE ACCEPTED AS IS PER ATTACHMENT 1. -l W/ / / 30 ff ;
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Page 88 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-22-6 Pressure Regulator Cerrected Recorded Data Data Page 21 Step 7.2.4.2 Extrapolated peak fluz margin > 7.5% See DS S See DS 5 Data Below Data Below If not notify the Lead STD & A Engineer. Notified Notified Page 22 Step 7.2.6 Maintain a plot of the Peak Pressure See New See DS9/10 and the extrapolated peak Neutron Flux Plot of in the values along the 100% cod line. DS9/10 Procedure Page 24/25 Step 7.3.4.2 Extrapolated peak flux margin > 7.5%. See DS 8 See DS 8 Dat a Below Data Below If not notify the Lead STD & A Engineer Notified Notified .
Page 2 Step 7.3.6 Maintain a plot of the Peak Pressure See New See DS9/10 and the extrapolated peak Neutron Fluz Plots of in Proc.
values along the 100% cod line. DS 9/10 Data Sheet Page No. Parameter Date 1 35 Core Flow (MLB/HR) 02/20/88 36.58 35.00 3 38 Core Flow (MLB/HR) 02/28/88 111.92 107.10 4 39 Core Flow (MLB/HR) 02/28/88 111.82 107.00 5A 40 Extr.' Mars. APRM 03/02/88 A Regulator +10 PSI Step 7.60% 11.10%
A Regulator Failure to B 2.41% 6.00%
B Regulator +10 PSI Step 6.30% 9.70%
B Regulator Failure to A 6.85% 10.20%
5B 41 Extr. Mars. APRM 03/02/88 A Regulator +10 PSI Step 6.82% 10.20%
B Regulator +10 PSI Step 2.99% 6.51%
6 42 Core Flow (MLB/HR) 02/29/88 111.82 107.00 7 44 Core Flow (MLB/HR) 02/29/88 111.82 107.00 .
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l Page 89 of 132 )
Supplemental Final Startup Report l
Procedure Number: N2-SUT-22-6 Pressure Regulator l
Corrected Recorded Data Sheet Page No. Parameter Date Data Data i I
8A ' 45 Extr.' Mars. APRM 03/03/88 A Regulator +10 PSI Step 10.09% 13.35%
A Regulator Failure to B 9.72% 12.97%
B Regulator +10 PSI Step 6.24% 9.62%
B Regulator Failure to A 7.01% 10.37% !
88 46 Extr. Mars. APRM 03/03/88 A Regulator +10 PSI Step 9.63% 12.91%
B Regulator +10 PSI Step 10.26% 13.52%
Step 4.2.5 OD-3 (02-28-88 2119)
WT FACTOR WT* FACTOR 106.990 1.045 111.805 = 103.05% 98.61%
108.500 MWT RATED MWT % POWER 3255.560 3323.000 97.97%
% Power Rodline = .3+.7*%WT = 95.93% 98.93%
Step 6.2.7A GETARS Data Page 013 Step 7.2.4.2 WT FACTOR WT* FACTOR 107.200 1.045 112.024 = 103.25% 98.80%
108.500 100% Rodline S.S. Power = 102.27% 99.00%
100% Rodline APRM Flux Increase = 8.13% 7.90%
100% Rodline Peak Power = 110.40% 106.90%
DS5A Extrapolated Margin 7.60% 11.10%
Step 6.2.15A GETARS Data Page 073 Step 7.2.4.2 WT FACTOR WI* FACTOR 108.50 1.045 113.383 = 104.50% 100.00%
108.500 100% Rodline S.S. Power = 103.15% 100.00%
100% Rodline APRM Flux Increase = 8.55% 8.29%
100% Rodline Peak Power = 111.70% 108.29%
DS5A Extrapolated Margin 6.30% 9.71%
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Page 90 of 132' Supplemental Final Startup Esport Procedure Number: N2-SUT-22-6 Pressure Regulator Corrected Recorded Data Data 6.2.22A .
GETARS Data Page.078 Step 7.2.4.2 WT FACTOR WT* FACTOR 108.40 1.045 113.278 = 104.40% 90.91%
108.500 100% Rodline S.S. Power = 103.08% 99.90%
100% Rodline APRM Flux Increase = 12.51% 12.10% -
100% Rodline Peak Power = 115.59% 112.00%
DS5A Extrapolated Margin 2.41% 6.0G%
Step 6.2.29A GETARS Data Pages 082/083
. Step 7.2.4.2 WT FACTOR WT* FACTOR 108.00 1.045 112.860 = 104.02% 99.54%
108.500 100% Rodline S.S. Power = 102.81% 99.70% ..
100% Rodline APRM Flux Increase = 8.34% ;B.10%
100% Rodline Peak Power = 111.15% 107.80%
DSSA Extrapolated Margin 6.85% 10.20%
Step 6.2.33 OD-3 (02-29-88 0255)
_ WT. FACTOR WI* FACTOR 107.300 1.045 112.129 = 103.34% 98.89%
108.500 NWT RATED MWT % POWER '
3260.060 3323.000 98.11%
% Power Rodline = .3+.7*%WT = 95.86% 98.87%
Step 6.2.7B GETARS Data Page 087 Step 7.2.4.2 WT FACTOR WT* FACTOR 108.800 1.045 113.696 = 104.79% 100.28%
108.500 100% Rodline S.S. Power = 103.35% 100.20%
100% Rodline APRM Flux Increase = 7.82% 7.60%
100% Rooline Peak Power = 111.18% 107.80%
DSSA Extrapolated Margin 6.82% 10.20%
Step 6.2.15B CETARS Data Page 092 Step 7.2.4.2 WT FACTOR WT* FACTOR 110.00 1.045 114.950 = 105.94% 101.38%
108.500 ,
100.97% MB 100% Rodline S.S. Power = 104.16%
100% Rodline APRM Flux Increase = 10.85% 10.52%
100% Rodline Peak Power = 115.01% 111.49%
DSSA Extrapolated Margin 2.99% 6.51%
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Page 91 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-22-6 Pressure Regulator Corrected Recorded Data Data-Step 4.3.5 OD-3 (02/29/88 0436)
WT FACTOR WT* FACTOR 107.58 1.045 112.421 = 103.61% 99.15%
.108.500 MWT RATED MWT % POWER 3260.130 3323.000 98.11%
% Power Rodline = .3+.7*%WT =
95.69%. 98.69 Step 6.3.1 OD-3 (02-29-88 0617)
WT FACTOR WI* FACTOR 104.410 1.045 109.108 .. 100.56% 96.23% -
108.500 MWT RATED MWT % POWER 3242.720 3323.000 97.58%
% Power Rodline = .3+.7*%WT = .97.20% 100.23%
Step 6.3.7A GETARS Data Page 192 Step 7.3.4.2 WT FACTOR WI* FACTOR 105.800 1.045 110.561 , 101,90% 97.51%
108.500 100% Rodline S.S. Power = 101.33% 98.26%
100% Rodline APRM Flux Increase = 6.58% 6.39%
100% Rodline Peak Power = 107.91% 104.64%
DS8A Extrapolated Margin 10.09% 13.35%
Step 6.3.14 OD-3 (02-29-88 1014)
WT FACTOR WT* FACTOR 104.220 1.045 108.910 = 100.38% 96.06%
108.500 MWT RATED MWT % POWER 3197.630 3323.000 96.23%
% Power Rodline " .3+.7*%WT = 95.97% 98.96%
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l Page 92 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-22-6 Pressure Regulator Corrected Recorded ,
Data Data Step 6.3.15A GETARS Data Page'204 Step 7.3.4.2 WT FACTOR WT* FACTOR 105.20 1.045 109.934 = 101.32% 96.96% .
108.500 '
100% Rodline S.S. Power = 100.93% 97.87%
100% Rodline APRM Flux Increase = 10.84% 10.51%
100% Rodline Peak Power = 111.76%. 108.38%
DS8A Extrapolated Margin 6.24% 9.62%
Step 6.3.22A 'GETARS Data Pa5e 208 Step 7.3.4.2 ,Et FACTOR WI* FACTOR ,
105.600 1.045 110.352 = 101.71% 97.33%
108.500
'100% Rodline S.S. Power = 101.19% 98.13%
100% Rodline APRM Flux Increase- 9.79% 9.50%
100% Rodline Peak Power = 110.99% 7107.63%
DS8A Extrapolated Margin 7.01% 10.37%
Step 6.3.29A' GETARS Data Page 222 Step 7.3.4.2 WT FACTOR WT* FACTOR 105.600 1.045 110.352 = 101.71% 97.33%
108.500 100% Rodline S.S. Power = 101.19% 98.13%
100% Rodline APRM Fluz Increase = 7.09% 6.90%
100% Rodline Peak Power = 108.28% 105.03%
DS8A Extrapolated Margin 9.72% 12.97%
Step 6.3.33 OD-3 (02/29/88 1130)
WT FACTOR WT* FACTOR 103.590 1.045 108.252 = 99.77% 95.47%
108.500 MWT RATED MWT % POWER 3158.190 3323.000 95.04%
% Power Rodline = .3+.7*%WT = 95.19% 98.15% ,
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Page 93 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-22-6 Pressure Regulator-Corrected Recorded Data Data !
Ster 6.3.7B GETARS Data Page 235 Step 7.3.4.2 WT FACTOR WT* FACTOR 104.400 1.045 _109.098 = 100.55% 96.22%
108.500 100% Rodline S.S. Power = 100,39% 97.35%
100% Rodline APRM Fluz Increase = 7.98% 7.74%
100% Rodline Peak Power = 108.37% 105.10%
DS8B Extrapolated Margin 9.63% 12.91%
Step 6.3.15B GETARS Data Page 245 Step 7.3.4.2 WT FACTOR WT* FACTOR 104.400 1.045 109.098 = 100.55% 96.22% ~
108.500 100% Rodline S.S. Power = 100.39% 97.35%
100% Rodline APRM Fluz Increaso= 7.35% 7.13%
100% Rodline Peak Power = 107.74% 104.48%
DS8B Extrapolated Margin 10.26% 13.52%
CONCLUSION: CORE FLOW DATA ALSO RECORDED ON PROCESS COMPUTER OD-3 EDITS AND GETARS HISTOGRAM ON M4IN TUREINE CONTROL VALVE INCREMENTAL REGULATION TEST. THESE DATA SHALL BE CORRECTED WITH A FACTOR OF 1.045 FOR FUTURE REFERENCES.
EXTRAPOLATED NEUTRON FLUX MARGIN TO REACTOR SCRAM WERE LESS THAN REQUIRED 7.5% IN SEVEN DIFFERENT TESTS. THE AMOUNT OF CORE FLOW DURING THESE TESTS ivERE BETWEEN 101.3% TO 105.9% RATED WHICH CAN BE ACC3PTED AS IS PER ATTACHMENT 1. THE DIRECTION FROM THE LEAD STD&A ENGINEER IS "D0 NOT PERFORM TESTING WHILE CORE FLOW IS HIGHER THAN 108.5 MLB/HR." THE ACCEPTANCE CRITERIA 0F THIS TEST IS NOT L1PACTED BY THE INCREASED CORE FLOW EVENT.
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Page 96 of 132 L Supplemental Final Startup Report Procedure Number: N2-SUT-23-6 Feedwater Systems Corrected ' Recorded Data Data Step 4.3.1/4.3.6 OD-3 (03-04-88. 0239)
WT FACTOR WT* FACTOR 107.030 1.045 111.846 = 103.08% 98.65%
108.500 MWT RATED MWT % POWER 2401.470 3323.000 72.27%
% Power Rodline = .3+.7*%Wr = 70.74% 72.96%
Step 4.10.7/4.10.2-WT FACTOR WT* FACTOR
-107.110 1.045 111.930 = 103.16% 98.72% -
108.500 MWT RATED MWT % POWER 3298.500 3323.000- 99.26%
% Power Rodline = .3+.7*%WT = 97.11% 100.16 Step 4.11.7/4.11.2 WI FACTOR WT* FACTOR 104.300 1.045 108.993 = 100.45% 96.13%
108.500 MWT RATED MWT % POWER 3195.250 3323.000 96.16%
% Power Rodline = .3+.7*%WI = 95.85% 98.83%
Step 4.12.7/4.12.2 WT FACTOR WT* FACTOR 105.700 1.045 110.457 = 100.80% 97.42%
108.500 )
l MWT RATED MWT % POWER 3258.090 3323.000 98.05% ,
% Power '
Rodline = .3+.7*%WT = 96.83 99.8 % .
Am
1 l
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I Page 97 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-23-6 Feedwater Systems corrected Recorded Data Data Step 4.13.3/4.13.9 WT FACTOR WT* FACTOR 107.620 1.045- l 112.463 = 103.65% 99.19%
108.500 MWT RATED MWT % POWER-3291.440 3323.000 99.05%
% Power Rodline = .3+.7*%WT = 96.58% 99.6?%
Step 4.1.4 Data Sheet 1A Page 71 WT FACTOR WT* FACTOR .
2/11/88 75.600 1.045 79.002 .. 72.81% 69.68%
108.500 2/15/88 89.40 1.045 93.423 = 86.10% 82.40%
108.500 RETEST 1 48.10 1.045 50.265 = 46.33% 44.33%
3/03/88 108.500 j Step 4.2.4 Data Sheet 1B Page 73 WT FACTOR WT* FACTOR 2/22/88 56.030 1.045 58.551 = $3.96% 51.64%
108.500 Step 4.3.4 Data Sheet 13 Page 121 WT FACTOR WI* FACTOR 107.900 1.045 112.756 = 103.92% 99.45%
108.500 Step 6.3.3 Data Sheet 14 Page 124 WT FACTOR WT* FACTOR Step 4.3.6 107.900 1.045 112.756 = 103.92% 99.45%
108.500 Step 6.3.3 106.90 1.045 111.711 = 102.96% 98.53%
108.500 )
21 km 95 i
p , 1 Page 98 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-23-6 Feedwater Systems Corrected Recorded Data Data Step 4.4.5 Data Sheet 16A Page-128 WT FACTOR WT* FACTOR 82.000- 1.045 85.690 = 78.98% 75.58%
108.500 Step 4.5.5 Data Sheet 16B Page 130 WT FACTOR WT* FACTOR 86.000- 1.045 89.870 = 82.83% 79.26%
108.500 Step 4.6.5 Data Sheet 16C Page 132 WT FACTOR WT* FACTOR .
82.500 1.045 86.213. = 79.46%' 76.04%
108.500 Step 4.10.5 Data Sheet 21A Page 152 WT FACTOR WT* FACTOR 107.300 1.045 112.129 = 103.34% 98.89%
108.500 Step 4.11.5 Data Sheet 21B Page 154 WT FACTOR Wr* FACTOR 102.000 1.045 106.590 , 98.24% 94.01%
108.500 Step 4.12.5 Data Sheet 21C Page 156 WT FACTOR WT* FACTOR 105.100 1.045 109.829 = 101.23% 96.87%
108.500 Step 4.10.8 Data Sheet 22A Page 158 WT FACTOR WT* FACTOR 107.000 1.045 111.815 = 103.06% 98.62%
109.500 Step 4.11.8 Data Sheet 22B Page 159 WT FACTOR WT* FACTOR 104.100 1.045 108.784 = 100.26% 95.94% I 108.500 mm Am,
Page 99 of 132 Supplemental Finni Startup Report Procedure Number: N2-SUT-23-6 Feedwater Systems Corrected Recorded Data Data Step 4.12.8 Data Sheet 22C, Page 160 WT FACTOR WT* FACTOR
'104.000 1.045 108.680 = 100.17% 95.85%
108.500 Step 4.13.7 Data Sheet 24 Page 164 WT. FACTOR WT* FACTOR 103.500 1.045 108.158 = 99.68% 95.39%.
108.500 Step 4.13.9- Data Sheet 25. Page 166 Before WT FACTOR ~ WT* FACTOR ,
Pump 108.000 1.045 112.860 = 104.02% 99.54% !
108.500 Trip Step 6.13.3 After WT FACTOR WT* FACTOR Pump 30.000 1.045 31.350 = 28.89% 27.65%
Trip 108.500 Step 7.13.2 Data Sheet 26, Page 167 ,
Before WT FACTOR WT* FACTOR Pump 107.800 1.045 112.651 = 103.83% 99.35%
Trip 108.500 -
Step 7.13.2 Data Sheet 26. Page 167 After WT FACTOR WT* FACTOR Pump 30.800 1.045 32.186 = 29.66% 28.39%
Trip 108.500 CONCLUSION: THE PLANT CONDITION AT STEP 2.10.2/4.11.2/4.12.2 AND 4.13.2 HAD HIGHER CORE FLOW THAN TC-6 TEST WINDOW. THE MAI CORRECTED CORE FLOW WAS 104.02%, THIS CONDITION CAN BE ACCEPTED PER ATTACHMENT 1.
CORE FLOW DATA WAS NOT USED ON ANALYSIS STEPS FOR EVALUATION OF THE ACCEPTANCE CRITERIA.
ANY CORE FLOW DATA IN THIS PROCEDURE SHALL BE CORRECTED WITH A H FACTOR OF 1.045 FOR FUTURE USE.
Yh ff y I,Jo/er M.C i140 6 Perfordbd by Verifiep/by I
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-Pa8e 100 of 132 Supplemental Final Startup Report Procedure Number:- N2-SUT-24-6 Turbine Vkive Surveillance Test Condition 6.
Corrected Recorded Data Data Step 6.1.1 OD-3 Dated 02/13/88 0237 WT FACTOR WT* FACTOR. PCT WT 72.580 1.045 75.846 = 69.90% 66.89%
108.500 MWT RATED MWT % POWER 2501.380 3323.000 75.27%
Rodline = 95.37% 97.98%
Step 6.1.1 OD-3 Dated 02/13/88 0229 WT FACTOR WT* FACTOR PCT WT 72.420 1.045 75.679 =- 69.75% 66.75%
108.500 .
. MWT RATED hVI % POWER 2505.590 3323.000 75.40%
Rodline = 95.66% 98.28%.
Step 6.1.1 P-1 Dated 02/13/88 0230 WT FACTOR WT* FACTOR PCT WT 72.190 1.045 75.439 = 69.53% 66.53%
108.500 ,
MWT' RATED MWT % POWER 2505.000 3323.000 75.38%
Rodline = 95.82% 98.45%
Step 4.2.5 OD-3 Dated 02/13/88 1906 WT FACTOR WT* FACTOR PCT WT 90.390 1.045 94.458 = 87.06% 83.31%
108.500 MWT RATED MWI % POWER 2856.440 3323.000 85.96%
Rodline = 94.52% 97.33%
Step 6.2.1 P-1 Dated 02/13/88 1959 WT FACTOR WT* FACTOR PCT WT 90.120 1.045 94.175 = 86.80% 83.06% 1-108.500 MWT RATED MWT % POWER j 2850.000 3323.000 85.77%
Rodline = 94.50% 97.30%
M
.. 4 l
Page 101 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-24-6 Turbine Valve Surveillance Test Condition 6.
1 Corrected Recorded i Data Data Step 6.2.1 OD-3 Dated 02/13/88 2010 ,
WT FACTOR WT* FACTOR -PCT WT l 89.840 1.045 93.883 = 86.53% 82.80% a 108.500 1 MWT RATED MWT- % POWER 2847.530 3323.000 85.69%
Rodline = 94.61% 97.42%
. Step 4.2.5 OD-3 Dated 02/23/88 0359 RETEST 1-WT FACTOR WT* FACTOR PCT WT 87.970 1.045 91.929 = 84.73% 81.08%
108.500 .
MWT RATED MWT % POWER 2902.340 3323.000 87.34%
Rodline. = 97.80% 100.68%
Step 6.2.1 OD-3 Dated 02/23/88 0446 RETEST 1 WT FACTOR WT* FACTOR PCT WT 88.710 1.045 92.702 = 85.44% 81.76%
108.500 MWT RATED MWT % POWER 2913.030 3323.000 87.66%
Rodline = 97.61% 100.49%
Step 6.2.1 P-1 Dated 02/23/88 0447 RETEST 1 WT FACTOR WT* FACTOR PCT WT 89.300 1.045 93.319 = 86.01% 82.30%
108.500 MWT RATED MWT % POWER 2915.000 3323.000 87.72%
Rodline = 97.25% 100.12%
i Step 6.2.1 OD-3 Dated 02/23/88 2028 RETEST 2 WT FACTOR WT* FACTOR PCT WT l 84.960 1.045 88.783 = 81.83% 78.30% 1.1 108.500
'e MWT RATED MWT % POWER 2923.560 3323.000 87.98%
Rodline = 100.80% 103.73% !
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Page 102 of 132 I Supplemental Final Startup Report Procedure Number: N2-SUT-24-6 Turbine Valve Surveillance Test Condition 6.
Corrected Recorded Data Data Step 6.2.1 P-1 Dated 02/23/88 2032 RETEST 2 WT FACTOR WT* FACTOR PCT WI 85.120 1.045 ~ 88.950 = 81.98% 78.45%
108.500 MWT RATED MWT % POWER 2932.000 3323.000 88.23%
Rodline = 100.97% 103.91%
Step 6.3.1 P-1 Dated 02/24/88 0150 WT FACTOR WI* FACTOR PCT WT 100.080 1.045 104.584 = 96.39% 92.24%
108.500 MWT RATED MWT % POWER 3161.000 3323.000 95.12%
Rodline = 97.59% 100.59%
Step 6.2.1 OD-3 Dated 02/24/88 0211
108.500 MWT RATED MWT % POWER 3159.220 3323.000 95.07%
Rodline = 98.15% 101.15%
WT* FACTOR PCT WT WT DATA SH. PAGE FACTOR (MLB/HR) (%) (MLB/HR) 1 24 1.045 76.076 70.12% 72.800 2 26 1.045 75.846 69.90% 72.580 10 35 1.045 94.750 87.33% 90.670 11 37 1.045 94.175 86.80% 90.120 10 35 RETEST 1 1.045 92.692 85.43% 88.700 11 35 RETEST 1 1.045 92.702 85.44% 88.710 10 35 RETEST 2 1.045 88.512 81.58% 84.700 11 35 RETEST 2 1.045 88.783 81.83% 84.960 19 46 1.045 105.127 96.89% 100.600 20 48 1.045 103.643 95.52% 99.180 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS. THE _
CORE FLOW AND RECIRC LOOP FLOW DATA IN ThE PROCEDURE SHALL APPLY TeBr Par i ihkACORRECTIONFACTOROF1.0 0710 b Performed by Yerified/by '/
.nu
Page 103 of 132 Supplemental Final Startup Report
. Procedure Number: N2-SUT-25-6 Full Reactor Isolation ,
I Corrected Recorded 1 Data Data Step 4.1.3 OD-3 (02-15 1348)
WT FACTOP. WI* FACTOR PCT WT M1b/Hr M1b/HL-102.540 3 . t,is 5 107.154 = 98.76% 94.51% i 108.500 MWT RATED MWT % POWER 3168.060 3323.000 95 34%
Rodline = 96.17% 99.15% !
Step No. Doc. Type Date Parameter Unit 4.1.1 P-1 02-15-88 WT M1b/He 107.03 102.42 4.1.2 Data Sheet 1 02-15-88 WT dib/He 105.55 101.00 .
4.1.3 P-1 02-15-88 WI M1b/He 107.15 102.54 4.1.2 GETARS P599 02-15-88 LP-A-FLO M1b/Hr 53.22 50.9291 4.1.2 GETARS P599 02-15-88 LP-B-FLO M1b/Hr 53.98 51.6527 4.1.2 GETARS P599 02-15-88 WT M1b/He 106.97 102.3654 CONCLUSION: CORE FLOW DATA WAS NOT USED FOR DATA ANALYSIS OR EVALUATION OF THE ACCEPTANCE CRITERIA THEREFORE THE ONLY IMPACT TO THIS TEST BY THE INCREASED CORE FLOW DATA CORRECTION AS NOTED IN ABOVE.
AF / .
/ / # f Verifled %y Performe~d by /
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Page 104 of 132 Supplemental Final Startop Report Procedure Number: N2-SUT-27-6 Generator Load Rejection Corrected _ Recorded Data Data Step 4.1.4.3/6.1.1 OD-3 Dated 03/05/88 1049 j
WT FACTOR WT* FACTOR PCT WT .l 106.560 1.045 111.355 = 102.63% 98.21%
108.500 MWT RATED MWT % POWER 3310.310 3323.000 99.62% j Rodline = 97.82% 100,88%
Step 6.1.1 P-1 03/05/88 1058 SEQ. 7 WT FACTOR WT* FACTOR PCT WT l
107.730 1.045 112.578 = 103.76% 99.29%
108.500 --
MWT RATED MWT % POWER 3304.000 3323.000- 99.43%
Rodline = 96.88% 99.92%
DOC. TYPE PAGE STEP NO. FACTOR WT* FACTOR % RATED 'WT DS 1 24 4.1.2 1.045 111.919 103.15% 107.100 DS 2 32 6.1.1 1.045 111.355 102.63% 106.560 GETARS WT 849 4.1.2 1.045 111.954 103.18% 107.133 GETARS-JP-A-FLO 849 4.1.2 1.045 56.471 52.05% 54.040 GETARS JP-B-FLO 849 4.1.2 1.045 55.751 51.38% 53.350 GETARS WT 755 7.1.16 1.045 112.696 103.87% 107.843 GETARS JP-A-FLO 755 7.1.16 1.045 57.863 53.33% 55.371 GETARS JP-B-FLO 755' 7.1.16 1.045 55.115 50.80% 52.742 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS AS CORE FLOW DATA WAS NOT USED ON ANALYSIS STEPS. 103.76% RATED CORE FLOW CAN BE ACCEPTED PER ATTACHMENT 1.
ALL THE CORE FLOW OR JET PUMP LOOP FLOW DATA OR PLOT IN THE APPENDIX II 0F THE TEST PROCEDURE SHALL BE CORRECTED BY A FACTOR OF 1.045 BEFORE ANY APPLICATION.
W/ N '
/l C Y Performefd by verified gy e
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i Page 105 of 132 3 i
~
Supplemental Final Startup Report f Procedure Number: N2-SUT-29-6 Recirculation Testing Corrected Recorded Data Data The Test Data Evaluation are as follows:
Step 4.1.3 Data Sheet 1 '
A Jet Pump Loop Flow (M1b/He) 40.34 38.60
, B Jet Pump Loop Flow (M1b/Hr) 39.66 37.95 Total Core Flow (M1b/Hr) 79.94 76.50 Step 6.1.1/4.1.2 WT FACTOR WT* FACTOR PCT WT 48.980 1.045 51.184 = 47.17% 45.14%
108.500 ..
MWT RATED MWI % POWER -
2007.660 3323.000 60.42%
Rodline = 95.87% 98.08%
Step 7.2.7/6.1.7/7.1.5 GETARS P415 WT FACTOR WT* FACTOR PCT WT 53.000 1.045 55.385 = 51.05% 48.85%
108.500 100% Rodline S.S. Power = 65.73% 63.00%
100% Rodline APRM Flux Increase = 15.77% 15.24%
100% Rodline Peak Power = 81.50% 78.21%
Extrapolated APRM Trip Margin = 36.50% DS3 39.79% ,
GETARS Min Ht Flux Margin = 15.40% 15.40% j P416 Extrapolated Margin = 14.334% DS3 14.90%
1 Step 6.1.9/7.1.5 P375 I Extrapolated APRM Trip Margin 14.69% DS3 14.80%
Step 6.1.17/7.1.5 P325 Min Ht Flux Mergin = 15.25% 15.25% ;
Extrapolated Margin = 14.93% DS3 15.10%
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Page~106 of 132 4
. Supplemental Final Startup Report I Procedure Number: N2-SUT-29-6 Recirculation Testing Corrected ' Recorded 1
. Data Data P271 Min Ht Flux Margin = 15.6?% 15.6?%
Extrapolated Margin
= 15.62*(100/95.867)'-1.7 = 14.54% DS3 15.11%
P280 WT FACTOR WT* FACTOR PCT WT l 52.700 1.045 55.072 = 50.76% 48.57%
1 108.500 100% Rodline S.S. Power = 65.53% 62.80%
100%.Rodline APRM Flux Increase = 13.85% 13.40%
100% Rodline Peak Power = 79.38% 76.20%
Extrapolated APRM Trip Margin = 38.62% DS3 41.80%
Step 6.1.23/6.1.22 WT FACTOR WT* FACTOR PCT W 70.510. 1.045 73.683 = 67.91% 64.99%
108.500 MWT RATED MWT % POWER 2476.840 3323.000 74.54%
Rodline = 96.13% 98.74%
Step 6.1.29 +5% FCV A GETARS P080 WT FACTOR WT* FACTOR 70.51 1.045 73.683 = 67.91% 64.99%
108.500 100% Rodline S.S. Power = 77.54% 75.50%
100% Rodline APEN Flux Increase = 12.47% 12.00%
100% Rodline Peak Power = 90.00% 87.50%
Extrapolated APRM Trip Margin = 28.00% DS3 30.50%
Min Ht Flux Margin = 16.20% 16.20%
P081 Extrapolated Margin = 15.15% DS3 15.80%
Min Ht Flux Margin = 15.80% 15.80%
Extrapolated Margin = 15.49% DS3 15.70%
i As
Page 107 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-6 Recirculation Testing Corrected Recorded Data Data Step 6.1.39 +5% FCV B P132 WT FACTOR WT* FACTOR 70.51 1.045 73.683 = 67.91% 64.99%
108.500 100% Rodline S.S. Power =l 77.54% 75.50%
100% Rodline APRM Fluz Increase = 12.10% 11.60%
100% Rodline Peak Power = 89.63% 87.10%
Extrapolated APRM Trip Margin = 28.37% DS3 30.90%
r Min Ht Flux Margin = 16.00% 16.00%
P133 Extrapolated Margin = 14.96% DS3 15.60%
Step 6.1.39 -5 FCV B P144 ,
Min Ht Fluz Margin = 16.00% 16.00%
P145 Extrapolated Margin = 15.69% DS3 15.90%
Step 6.1.45 WT FACTOR WT* FACTOR PCT WT 106.170 1.045 110.948 = 102.26% 97.85%
108.500 MWT RATED MWT % POWER 3225.160 3323.000 97.06%
Rodline = 95.55% 98.54% .
Step 6.1.51 -5% FCV A P669 Min Ht Fluz Margin = 12.40% 12.40%
Extrapolated Margin = 12 12% DS3 12.30%
Step 6.1.53 +5 FCV A P680 WT FACTOR WT* FACTOR PCT WT 106.170 1.045 110.948 = 102.26% 97.85%
108.500 100% Rodline S.S. Power = 101.58% 98.50%
100% Rodline APRM Flux Increase = 3.53% 3.37%
100% Rodline Peak Power = 105.11% 101.87% -
Extrapolated APRM Trip Margin = 12.89% DS3 16.12%
en P679 Min Ht Flux Margin = 12.86% 12.86%
Extrapolated Margin = 11.90% DS3 12.53%
Am
_____._.._._____.m_ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _
~3.-
o-Page 108 of 132 Supplemental Final Startup. Report 4 Procedure Number: N2-SUT-29-6 Recirculation Testing i Corrected Recorded Data Data Step 6.1.61 -5% FCV A P957 Min Ht Flux Margin = 12.10% 12.10%
P145 Extrapolated Margin = 11.83% DS3 12.00%
Step 6.1.63 +5% FCV A' P971 WT FACTOR WT* FACTOR 106.17 1.045 110.948 = 102.26% 97.85%
108.500 100% Rodline S.S. Power = 101.58% 98.50%
100% Rodline APRM Flux Increase = 4.07% 3.90% .
100% Rodline Peak Power = 105.65% 102.40%
Extrapolated APRM Trip Margin = 12.35% DS3 15.60%
P970 Min Ht Fluz Margin. = 12.25% 12.30%
Extrapolated Margin = 11.34% .DS3 11.94%
Step 4.2 3 Data Sheet 4 A Jet Pump Loop Flow (M1b/He) 30.93 29.60 B Jet Pump Loop Flow (M1b/Hr) 30.41 29.10 Total Core Flow (M1b/He) 61.24 58.60 Step 6.2.1.1 WT FACTOR WT* FACTOR PCT WT 55.350 1.045 57.841 = 53.31% 51.01%
108.500 MWT RATED MWT % POWER 2086.280 3323.000 62.78%
Rodline = 93.27% 95.55%
Step 6.2.1.2 -3% Flow Step P131 l
l Nt Flux = 63.70% 63.70%
Min Ht Flux Margin = 17.50% 17.50%
Extrapolated Margin = 16.90% DS6 17.11%
L Am l- -
Page 109 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-6 Recirculation Testing Corrected Recorded Data Data Step 6.2.1.2_ +3% Flow Step P482 W FACTOR WT* FACTOR PCT WT 55.350 1.045 57.841 = 53.31% 51.01%
108.500 Step 7.2.1.5.4 100% Rodline S.S. Power = 67.3?% 68.30%
- 100% Rodline APRM Flux Increases 15.22% 14.67%
100% Rodline Peak Power = 82.53% 82.97%
Extrapolated APRM Trip Margin = 35.47% DS6 35.03%
P178 Ht Flux = 0.655 *0.979 65.10% 65.10%
Min Ht Flux Margin
= Ind Marg +(1-GAF)*Ht Flux = 18.50% 18.50%
Extrapolated Margin = 16.43% DS6 17.12% .
Step 6.2.2.1.1/6.2.1.7 WT FACTOR WT* FACTOR 106.99 1.045 111.805 = 103.05% 98.61%
108.500 MWT RATED MWT % POWER 3256.840 3323.000 98.01%
Rodline = 95.96% 98.97%
Step 6.2.2.1.2 -3% Flow Step P641 Min Ht Flux Margin = 11.80% 11.80%
Extrapolated Margin = 11.56% DS6 11.80%
Step 6.2.2.1.2 +3% Flow Step P740 WT FACTOR WT* FACTOR 109.10 1.045 114.010 ,' 105.08% 100.55%
108.500 100% Rodline S.S. Power = 103.55% 0.00%
7.2.1.5.5 100% Rodline APRM Flux Increase. 11.70% 11.17%
100% Rodline Peak Power = 115.26% 109.00%
Extrapolated APRM Trip Margin = 2.74% DS6 9.00% _
P648 Min Ht Flux Margin = 10.30% 10.30% 1B Extrapolated Margin = 9.60% DS6 10.30%
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Page 110 of 132 Supplemental Final Startup Report
-Procedure Number: N2-SUT-29-6 Recirculation Testing.
Corrected Recorded Data Data.
' Step 4.3.4 ' Data Sheet 8 Date A Jet Pump Loop Flow (M1b/Hr) 2/13/88 39.29 37.60 B Jet Pump Loop Flow (M1b/He) 2/13/88 38.04 36.40 Total Core Flow (M1b/Hr) 2/13/88 .77.12 73.80 A Jet Pump Loop Flow (M1b/Hr) 3/03/88 56.64 54.20 B Jet Pump Loop Flow (M1b/Hr) 3/03/88 54.44 52.10 Total Core Flow (M1b/Hr) 3/03/88 110.87 106.10 Step 6.3.1.1/4.3.3 .
Corrected Core Flow is greater WT FACTOR WT* FACTOR than 74 (+0,-2) M1b/He, this is an.
arbitrary selected range for test condition.
74.37 1.045 77.717 = 71.63% 68.54'a 108.500 MWT. RATED MWT % POWER 2526.750 3323.000. 76.038 Rodline = 95.00% 97.51% ,
Step 6.3.1.2 - 7 -8% Flux Step P866 Min Ht Flux Margin = 17.30% 17.30%
Extrapolated Margin = 16.85% DS10 17.10%
Step 6.3.1.2 - 7 +8% Flux Step P945/946 WT FACTOR WT* FACTOR 78.00 1.045 81.510 = 75.12% 71.89%
108.500 100% Rodline S.S. Power = 82.59% 80.00%
100% Rodline APRM Flux Increase = 4.33% 4.15%
100% Rodline Peak Power = 86.92% 84.15%
Extrapolated APRM Trip Margin = 31.08% DS10 33.85%
Min Ht Flux Margin = 16.20% 16.20%
Extrapolated Margin = 14.82% DS10 15.52%
L Am m
t
Page 111 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-6 Recirculation Testing Corrected Recorded Data Data ,
The Test Data Evaluation are as follows:
Step 6.3.1.11.3 +8% Flux Step P263 W FACTOR W* FACTOR 82.68 1.045 86.401 = 79.63% 76.20%
108.500-100% Rodline'S.S. Power = 85.74% 88.00%
100% Rodline APRM Flux Increase = 5.04% 4.87%
100% Rodline Peak Power = 90.78% 92.87%
Extrapolated APRM Trip Margin = 27.22% DS12 25.13%
Min Ht Fluz Margin = 17.70% 17.70%
Extrapolated Margin = 16.19% DS12 16.96% ,
Step 6.3.1.11.7 -8%- Flux Step P926 Min Ht Flux Margin = 19.10% 19.10%
P926 Extrapolated Margin = 18.60% DS12 18.86%
Step 6.3.2.1.1/6.3.1.13 WT FACTOR WT* FACTOR 107.46 1.045 112 296 = 1,03.50% 99.04%
108.500 WI RATED MWT % POWER 3214.780 3323.000 96.74%
Rodline = 94.43% 97.40%
l Step 6.3.2.1.3 -5% Flux Step P337 Min Ht Fluz Margin = 11.75% 11.75%
Extrapolated Margin = 11.42% 11.60%
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J Page 112 of 132 Supplemental Final Startup Report t
Procedure Number: N2-SUT-29-6 Recirculation Testing Corrected Recorded Data Data-
~ Step 6.3.2.1.5 +5% Flux Step P349 WT FACTOR WT* FACTOR !
102.50 1.045 107'113 =
98.72% 94.47%
108.500-100% Rodline S.S. Power = 99.10% 96.13%
100% Rodline APRM Flux Increase = 4.63% 4.42%
100% Rodline Peak Power = 103.74% 100.55%
Extrapolated APRM Trip Margin = 14.26% 17.45%
P350 Min Ht Flux Margin = 11.75% 11.75%
Extrapolated Margin = 10.66% 11.23%
Step 6.3.2.4.3 -5% Flux Step P358 ,
Min Ht Flux Margin = 11.50% 11.50%
Extrapolated Margin = 11.18% DS12 11.35%
Step 6.3.2.4.7 +5% Flux Step P367 WT FACTOR WT* FACTOR 104.25 1.045 108.941 = 100.41% 96.08%
108.500 100% Rodline S.S. Power = 100.28% 97.26%
100% Rodline APRM Flux Increase = 3.27% 3.12%
100% Rodline Peak Power = 103.55% 100.38% .
Extrapolated APRM Trip Margin = 14.45% DS12 17.62%
Min Ht Flux Margin = 11.25% 11.25%
Extrapolated Margin = 10.21% DS12 10.76%
Step 6.3.3.1 WT FACTOR WT* FACTOR 106.48 1.045 111.272 = 102.55% 98.14%
108.500 MWT RATED MWT % POWER 3215.000 3323.000 96.75%
Rodline = 95.05% 98.03%
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Page 113 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-29-6 Recirculation Testing Corrected Recorded Data Data Step 6.3.3.1/7.3.3.2 - 5 -8% Flux Step P394 Min Ht Flux Margin = 13.25% 13.25%
~ Extrapolated Margin = 12.92% 13.12%
P395 Min Ht Flux Margin = 19.25% 19.25%
Extrapolated Margin = 18.77% 19.06%
Step 6.4.1 WT CORR FACTOR CORRECTED WT % RATED 107.886- 1.045 112.84 103.91%
Data Sheet 13 (DS13)
RECORDED CORRECTED FCV POS %
WT -1.045*WT "A" "B" 56.900 59.461 18.70 21.60 63.900 66.776 24.06 26.95 75.770 79.180 34.26 37.17 87.380 91.312 45.47 47.90 {
99.093- 103.552 61.46 63.32 ,
107.886 112.741 78.79 77.78 B35-K649 K652 RECORDED RECORDED RECORDED CORRECTED RECORDED CORRECTED RECORDED CORRECTED .
I WD WD A B VDC 1.055*VDC A 1.055*A B 1.055*B l 48.56 48.46 3.90 4.115 3.90 4.115 3.89 4.104 4.54 56.00 55.95 4.49 4.737 4.790 4.50 4.748 69.37 69.15 5.55 5.855 5.59 5.897 5.58 5.887 81.31 81.17 6.51 6.868 6.53 6.889 6.53 6.889 92.75 92.81 7.437 7.846 7.46 7.870 7.45 7.860 i 101.35 100.52 8.063 8.506 8.05 8.493 8.00 8.440 l 1
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l Supplemental Final Startup Report Procedure Number: .N2-SUT-29-6 Recirculation Testing CONCLUSION: DUE TO INCREASED' CORE FLOW EVENTS, IN A FEW CASES PLANT INITIAL TEST CONDITIONS WERE OUT OF THE SPECIFIED RANGE, HOWEVER, ALL THE SPECIFIED RANGES. WERE SELECTED BY THE PROCEDURE WRITER AND WERE NOT A REQUIREMENT OF ' THE TEST SPECIFICATION OR FSAR CHAPTER '
- 14. WR145900 WAS COMPLETED TO RECALIBRATES.~THE INSTRUMENT R35-K652A/B. WR145841 WAS COMPLETED TO ~ RECALIBRATES THE INSTRUMENT B35-K649. SECTION 7 AND 8 0F THE TEST PROCEDURE.ARE EVALUATED . BASED ON. INCREASED : CORE FLOW CONDITION. ALL -THE REQUIREMENTS ARE MET EXCEPT THE FOLLOWIMG:
THE' MAX. CORRECTED CORE FLOW DATA IN THIS PROCEDURE IS 103.9%
RATED. THE APRM TRIP MARGIN FOR THE FLOW UPSTEP AT NEAR RATED WAS ONLY 2.7%.
. ALL' THE CORE FLOW AND JET PUMP LOOP FLOW DATA IN THE PROCEDURE SHALL BE CORRECTED WITH A FACTOR OF 1.045 BEFORE ANY APPLICATION.
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Page 115 of 132 Supplemental Final Startup Report l
Procedure Number: N2-SUT-30-6 Reactor Recirculation System Corrected ' Recorded Data Data Paga 14 Step 7.1.2 The estimated core flow shortfall Corrected data meets <5% requirement. = 2.50% 6.33%
Page 16
. Step 7.2.5 Evaluate the heat flux trip margin See Data Sheet 11 Page 117.
Step 7.2.6 Verify simulated heat flux trip margin See Data Sheet 11 is > 5%. Page 117 Step 7.2.8 APRM trip margin analysis: .
Stsp.7.2.8.1 Extrapolate Core Power (100% loadline)= 61.5?% 60.16% .
Step 7.2.8.2 Extrapolated APRM change = 17.47% 26.87%
Page 17 Step 7.2.8.3 Extrapolated APRM margin to scram = 39.01% 40.97%
Step 7.2.9 Verify APRM trip margin is > 7.5% 39.01% 40.97%
Page 18 Section 8 All criteria are satisfied with increased core flow condition. ,
Page 21 See attached corrected Fig. 1.
CORRECTED DATA RECORDED DATA AVG FCV POS WT PCT WT WT PCT WT 13.232 50.97 46.98% 48.776 44.955%
18.2335 56.93 52.47% 54.476 50.208%
39.7175 84.52 77.90% 80.880 74.544%
81.9745 114.91 105.91% 109.961 101.347%
Corrected Recorded Data Sheet Page No. Parameter Data Data I 1 26 A LP FLOW 29.05 27.80 B LP FLOW 28.01 26.80 27 CORE FLOW 56.43 54.00 2 29 A LP FLOW 25.08 24.00 B LP FLOW 25.81 24.70 ,7 CORE FLOW 50.62 48.44 28.95 27.70 'E 3 31 A LP FLOW B LP FLOW 27.90 26.70 CORE FLOW 56.49 54.06 a.k
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Page 116 of 132 j' Supplemental Final Startup Report Procedure Number: N2-SUT-30-6 Reactor Recirculation System Corrected Recorded Data Sheet Page No. Parameter Data Data i
4 33 A LP FLOW 42.95 41.1 B LP FLOW 41.59 39.8 ,
CORE FLOW 83.64 80.04 5 35 A LP FLOW 57.09- 54.631 B LP FLOW 57.82 55.33 CORE FLOW 113.43 108.55 l 36 CORE FLOW SHORTFALL % 2.50% 6.33%
(%) (%)
CFP FCV AVE 9 81.97 108.62% 82 108.20%
M1b/Hr 117.86 117.397 CFA M1b/Hr 114.91 109.961 105.91% 101.35%
6 37 The Reactor Recire pump eff. was performed at 104.5% .
rated core flow condition.
7 40 A LP FLOW 57.06 54.'60 B LP FLOW 55.91 53.50 41 CORE FLOW 112.13 107.30 8 44 A LP FLOW 57.51 55.03 B LP FLOW 56.07 53.65 CORE FLOW 112.83 107.97.
9 46 A LP FLOW 73.38 70.22 B LP FLOW 16.41 15.70 CORE FLOW 57.48 55.00 11 50 PRE-TRIP TOTAL CORE FLOW 112.77 107.91 POST TRIP TOTAL CORE FLOW 112.60 107.75 POST RESTART CORE FLOW 48.70 46.60 PEAK FLUK MARGIN PUMP TRIP 11.39% 11.66%
HEAT FLUX MARGIN PUMP RESTART 14.66% 15.24%
APRM MARGIN 39.01% 40.97%
Step 6.2.1. OD-3 Dated 0301 1038 WT FACTOR WT* FACTOR 107.97 1.045 112.829 = 103.99% 99.51%
108.500 MWT RATED MWT % POWER 3295.970 3323.000 99.19%
Rodline = 96.49% 99.53%
Step 6.2.3 GETARS Data Page 539 ,
Heat Flux Margin = 11.60% 11.60% 'E Extrapolated Heat Flux Margin = 11.39% 11.60%
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Page 117 of 132 Supplemental Final Startup Report 1
Procedure Number: N2-SUT-30-6 Reactor Recirculation System ]
Corrected Recorded Data Data step 6.2.23/6.2.25 OD-3 Dated 030188 1718 j
WT FACTOR WT* FACTOR 50.39 1.045 52.658 = 48.53% 46.44%
108.500 MWT RATED MWT % POWER 1790.090- 3323.000 53.87%
Rodline = 84.21% 86.20%
GETARS Data Page-818 Heat Fluz Margin = 19.63% 19.63%
Extrapolated Heat Flux Margin = 14.66% 15.24%
Step 6.2.25 B Pump Restart GETARS Data Page 582 WT FACTOR WT* FACTOR 46.750 1.045 48.854 = 45.03% 43.09%
108.500 100% Rodline S.S. Power = 61.52% 60.20%
100% Rodline APRM Flux Increase = 17.47% 16.90%
100% Rodline Peak Power = 78.99% 77.00%
Extrapolated Margin = 39.01% 41.00%
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E' I i j Page 118 of 132 Supplemental Final Startup Report-j Procedure Number: N2-SUT-30-6 Reactor Recirculation System Ref. Corrected Recorded Step No. Data Type Date Time Parameter Data Data 6.1.1.2 P-1 02/21/88 2122 WT 50.54 48.36 )
OD-3 02/21/88 2124 WT 50.62 48.44 GETARS 02/21/88 0610 JP-A-FLO 29.03 27.78 P850 JP-B-FLO 28.04 26.83 WT 56.84 54.39 6.1.2.2 P-1 02/21/88 1843 WT' 56.45 54.02 OD-3 02/21/88 1859 WT 56.49 54.06 V-MEAN 02/21/88 1848 JP-A-FLO 28.99 27.74 P868 JP-B-FLO 27.93 26.73 WT $6.70 54.25
-6.1.3.2 P-1 02/22/88 1200 WT 84.25 80.62 OD-3 02/22/88 1236 WT 83.64 80.04 V-MEAN 02/22/88 1112 JP-A-FLO 42.90 41.06 P119 JP-B-FLO 41.62 39.82 -
6.1.4.2 P-1 02/26/88 0022 VT 113.93 109.02 OD-3 02/26/88 0036 WT 83.64 80.04 V-MEAN 02/26/88 0025 JP-A-FLO 42.90 41.06 P770 JP-B-FLO 41.62 39.82 WT 84.17 80.55 4.2.7 HISTO 03/01/88 0848 JP-A-FLO 57.06 54.60 P636 JP-B-FLO 55.89 53.48 WT 112.16 107.33 6.2.1 P-1 03/01/88 1029 WT 112.70 107.85 OD-3 03/01/88 1038 WT 112.83 107.97 6.2.4 Y-MEAN 03/01/88 1037 JP-A-FLO 57.51 55.03 P670 JP-B-FLO 56.07 53.65 WT 112.77 107.91 6.2.6 P-1 03/01/88 1122 WT 57.48 55.00 OD-3 03/01/88 1142 WT 57.48 55.00 6.2.7 V-MEAN 03/01/88 1114 JP-A-FLO 73.38 70.22 P682 JP-B-FLO 16.41 15.70 WT 57.83 55.34 6.2.10 V-MEAN 03/01/88 1231 JP-A-FLO 73.34 70.18 P729 JP-B-FLO 16.14 15.44 WT 58.28 55.78 6.2.12 V-MEAN 03/01/88 1250 JP-A-FLO 66.69 63.82 P742 JP-B-FLO 13.76 13.16 WT 53.87 51.55 6.2.14 V-MEAN 03/01/88 1328 JP-A-FLO 60.43 57.83 P024 JP-B-FLO 11.19 10.71 WT 49.92 47.77 6.2.16 V-MEAN 03/01/88 1403 JP-A-FLO 53.59 51.28 _,
P029 JP-B-FLO 7.56 7.23 WT 46.58 44.57
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Page 119 of 132 Supplemental' Final Startup Report Procedure Number: N2-SUT-30-6 Reactor Recirculation System Ref. Corrected Recorded Step No. Data Type Date Time Parameter DataL Data 6.2.18 V-NEAN 03/01/88 1426 JP-A-FLO 46.75 44.74 P034 JP-B-FLO 3.23 3.09 WT 43.90 42.01 6.2.20 V-MEAN 03/01/88 1530 JP-A-FLO 39.33 37.64 P096 JP-B-FLO 0.67 0.65 l WT 38.92 37.24
- 6.2.26 V-NEAN 03/01/88 1729 JP-A-FLO 25.93 24.81 P024 JP-B-FLO 26.85 25.70 WT 52.66 50.40 6.2.25- P-1 03/01/88 1723 WT 52.82 50.55 P-1. 03/01/88 1946 WT 52.68 50.41 MAX TESTED CORE FLOW = 114.91 MLB/HR= 105.91%
Second Order Fit for FCV POS Versus Core Flow, 100%
Load Line Valve Pos % (Valve Pos)2 Core Flow
% %"2 % Regression Output:
3.50 12.25 44.8 Constant 39.5172253.
9.00 81.00 51.2 Std Err of Y Est 0.42033741 16.50 272.25 60.3 R Squared 0.99976545 ,
25.80 665.64 71.2 No. of Observations 8.0 33.70- 1135.69 79.5 Degrees of Freedom 5.0 46.00 2116.00 89.6 61.98 3841.52 100.0 % Coefficient (s) 1.401561 -0.0068136 86,00 7396.00 109.7 Std Err of Coef. 0.020772- 0.00022899 Indicated Calculated FCV POS Core Flow 81.9745 108.6227 %
117.5322 M1b/Hr 4
Page 120 of 132-Supplemental Final Startup Report Procedure Number: N2-SUT-30-6 Reactor Recirculation System FIGURE 1 DATA
_, Core Flow Predicted Core Flow FCV POS CORE FLOW DESIGN DATA (Based on FCV POS) Actual 0.0 39.51722 NA NA NA 3.50 44.33922 44.8 NA NA 4.0 45.01445 NA NA NA
'8.0 50.29364 NA NA NA 9.00- 51.57936 51.2 NA NA 12.0 55.35489 NA NA NA 13.232 56.86970 NA NA 46.98 16.0 60.19790 NA NA NA 16.50 60.78796 60.' NA NA.
18.234 62.80788 NA NA 52.47 20.0 64.82297 NA NA NA 24.0 69.23001 NA NA NA 25.80 71.14204 71.2 NA NA .
28.0 73.41901 NA NA NA 32.0 77.38997 NA NA NA 33.70 79.01160 79.5 FA NA R36. 0 - 81.14289 NA NA NA 39.718 84.43571 NA NA 77.89 40.0 84.67777 NA NA NA .
44.0 87.99462 NA ' NA - NA 46.00. 89.57128 89.6 NA NA 48.0 91.09342 NA NA NA 52.0 93.97419 NA NA NA ,
56.0 96.63692. NA NA NA 60.0 99.08162 NA NA NA 61.98 100.2110 100 NA NA 62.0 100.2222 NA NA NA 64.0 101.3082 NA NA NA 68.0 103.3168 NA NA NA i 70.0 104.2394 NA NA NA i 72.0 105.1074 NA NA NA q 76.0 106.6800 NA NA NA 80.0 108.0345 NA NA NA 81.975 108.6228 NA 108.6228 105.911 82.0 108.6299 NA NA NA 84.0 109.1709 NA NA NA i 86.00 109.6574 109.7 NA NA 88.0 110.0894 NA NA NA CONCLUSION: THE MAX. CORRECTED CORE FLOW RECORDED IN THIS PROCEDURE IS 114.91 MLB/HR. THIS IS EQUIVALENT TO 105.9% RATED CORE FLOW.
THIS CAN BE ACCEPTED AS PER ATTACHMENT 1. FIGURE 1 IS PLOTTED "J WITH 100% LOAD LINE DESIGN DATA AND SECOND ORDER DATA
'8 REGRESSION; THE CORRECTED CORE FLOW SHORTFALL IS 2.5%.
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Page 122 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-33-6 Reactor Recire. Piping Vibration Corrected Recorded Data Data Step 4.1.6 OD-3 (02-22-88 1235)
WT FACTOR WT* FACTOR M1b/Hr M1b/He 79.92 1.045 83.516 = 76.97% 73.66%
108.500 MWT RATED MWT % POWER 2732.940 3323.000 82.24%
Rodline = 98.05% 100.84%
Step 4.1.2 Step 4.1.1/4.1.2 Data Sheet 1 Page 29 Total Core Flow (M1b/Hr) = 84.01 80.39 PCT WT (%) = 77.43% 74.09%
Step 4.2.5 OD-3 (02-25-88 2246)
WT FACTOR WT* FACTOR M1b/Hr M1b/Hr 108.12 1.045 112.985 = 104.13% 99.65%
108.500 .
MWT RATED MWT % POWER 3299.780 3323.000 99.30%
Rodline = 96.51% 99.55%
Step 4.2.1 Data Sheet 2 Page 32 Total Core Flow (M1b/He) = 112.651 107.80 PCT WT (%) = 103.83% 99.35%
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p Page 123 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-33-6 Reactor Recire. Piping Vibration Corrected Recorded Data Data Step 4.3.5 OD-3 (03-01-88 0845)
WT FACTOR WT* FACTOR PCT WT M1b/He M1b/He 108.32 1.045 113.194 = 104.33% 99.83%
108.500
-MWT RATED MWT % POWER 3301.280 3323.000 99.35%
Rodline = 96.43%' 99.46%
Step 4.3.2 Data Sheet 3 Page 35 Total Core Flow (M1b/Hr) = 111.606 106.80 PCT WT (%) = 102.86% 98.43%
Step 4.4.5 OD-3 (03-05-88 1019)
WT FACTOR WT* FACTOR PCT WT M1b/Hr M1b/He 107.42 1.045 112.254 = 103.46% 99.00%
108.500 MWT RATED MWT % POWER i 3302.750 3323.000 99.39% l Rodline = % Power = 97.04% 100.09%
.3 + .7*%WT Step 4.4.2 Data Sheet 4 Page 38 Total Core Flow (M1b/Hr) = 110.77 106.00 PCT WT (%) = 102.09% 97.70%
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1 Page 124 of 132
. Supplemental Final Startup Report Procedure Number: N2-SUT-33-6 Reactor Recire. Piping Vibration Corrected Recorded Data Data -
Step 4.5.2 Data Sheet 5 Page 41 Total Core Flow (M1b/Hr) = 6.85 6.5556 PCT WT (%) = 6.31% 6.04%
Step 4.6.2. Data Sheet 5A Page 44 Total Core Flow (Mlb/He) = 34.80 33.30 PCT WT (%) = 32.07% 30.69%
CONCLUSION: THE TESTS FOR RECIRC. SYSTEM PIPING VIBRATION WERE MARGINALLY
, IMPROVED BECAUSE THE DATA WAS COLLECTED OVER A GREATER RANGE OF RECIRC. FLOW.
104.33% FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
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Page 125 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-74-6 Offgas System Corrected Recorded Data Data Step 6.1.1 Dated 3-3-88 Data Sheet 1 Page 17 Total Core Flow (M1b/Hr) = 110.39 105.64 PCT CORE FLOW = 101.75% 97.36%
Data Sheet 1 Page 17 Dated 2-26-88 Total Core Flow (M1b/Hr) = 113.91 109.00 PCT CORE FLOW = 104.98% 100.46%
CONCLUSION: 104.98% CORE FLOW CAN BE ACCEPTED AS IS PER ATTACHMENT 1.
INCREASED CORE FLOW EVENT HAS NO IMPACT ON VALIDITY OF RESULTS.
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Page.126 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-77-6 BOP and Small Bore Piping Vibration corrected Recorded' Data Data Step 4.2.3 OD-3 Dated 02-12-88 1617 PCT WT WT FACTOR :WT* FACTOR 71.02 1.045 74.216 = 68.40% 65.46% 'l 108.500 '
MWT. RATED MWT % POWER 2458.780 3323.000 '73.99% '
Rodline = 95.01% 97.59%
Step 4.3.3 -OD-3 Dated 02-26-88 0918 I WT FACTOR WT* FACTOR --
107.77 1~045 112.620 = 103.80% 99.33%-
108.500 '
MWT RATED MWT % POWER 3289.220 3323.000 98.9R%
Rodline = 96.42% 99.45%.
Step 4.4.3/4.8.4 OD-3 Dated 02/15/88. 1311 WT FACTOR WT* FACTOR 103.28 1.045 107.928 95.19%
99.47%"
108.500 j MWT RATED MWT % POWER 3158.370 3323.000 95.05%
Rodline = 95.40% 98.36%
Step 4.6.4 OD-3 Dated 03-05-88 0148 WT FACTOR WT* FACTOR 107.62 1.045 112.A63 = 103.65% 99.19%
108.500 MWT RATED MWT % POWER 3291.440 3323.000 99.05%
Rodline = 96.5&% 99.62%
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Page 127 of 132 Supplemental, Final Startup Report Procedure Number: N2-SUT-77-6 BOP and Small Bore Piping' Vibration' )
Corrected Recorded -
Data Data Step 4.7.4' OD-3 Dated 03-05-88 1048
]
WT FACTOR WT* FACTOR 107.97 1.045 112.829 = 103.99% 99.51%
108.500.
NWT RATED MWT % POWER 3311.530 3323.000 99.65%
Rodline = 96.95% 100.00%
Data Sheet Page Factor Wt* Factor % Rated WT !
1A 22 1.045 74.202 68.39% 71.007 -
IB 27- 1.045 113.905 104.98% 109.000 1C 33 1.045 106.590 98.24% 102.000 1D .35 1.045 35.530 32.75% 34.000 1E 38 1.045 112.756 103.92% 107.900 1F 42 1.045 111.815 103.06% 107.000 1G -50 1.045 105.733 97.45% 101.180 CONCLUSION: INCREASED CORE FLOW HAS NO IMPACT ON VALIDITY OF RESULTS.
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no Page 128 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-79-6 Reactor Internals Vibration Measurement 100 Percent Load Line Corrected Recorded Data Data Step 4.1.1/6.1.1 OD-3 Dated 02-21-88 2124 WT FACTOR WT* FACTOR M1b/He M1b/Hr 48.44 1.045 50.620 = 46.65% 44.65%
108.500 MWT RATED MWT % POWER 1952.910 3323.000 58.77%
Rodline ~ = % Power = 93.79% 95.95%
.3 +. 7*%WT,,s Step 6.1.6 OD-3 Dated 02-21-88 1842 .
WT FACTOR WT* FACTOR .,
M1b/He M1b/He 53.98 1.045 56.409 = 51.99% 49.75%
108.500 MWT RATED MWT % POWER 2107.660 3323.000 63.43%
Rodline = % Power = 95.53% 97.84%
.3 + .7*%WT Step 6.1.11 OD-3 Dated 02/22/88 1235 WT FACTOR WT* FACTOR M1b/He M1b/He 80.20 1.045 83.809 = 77.24% 73.92%
108.500 MWT RATED MWT % POWER 2727.940 3323.000 82.09%
Rodline = % Power = 97.65% 100.43% j
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Pa8e 129 of 132 Supplemental Final Startup Report l
Procedure' Number: N2-SUT-79-6 Reactor Internals Vibration Measurement I 100 Percent Load Line
- , Corrected Recorded Data Data Step 6.1.16 OD-3 Dated 02-25-88 1926 WT FACTOR WI* FACTOR M1b/Hr M1b/Hr.
108.52 1.045 113.403 = 104.52% 100.02%
108.500 MWT RATED MWT % POWER 3309.440 3323.000 99.59%
Rodline = % Power = 96.54% 99.58%
.3 + .7*%WT Step 6.2.1 OD-3 Dated 03-01-88 0846 -
WT FACTOR WI* FACTOR PCT WT M1b/Hr M1b/He 106.99 1.045 111.805 = 103.05% 98.61%
108.500 MWT RATED MWT % POWER 3296.000 3323.000 99.19%
Rodline = % Power = 97.12% 100.16%
.3 + .7*tWI Step 6.2.7 OD-3 Dated 03-01-88 1142 WT. FACTOR WT* FACTOR M1b/He M1b/He 55.00 1.045 57.475 = 52.97% 50.69%
108.500 MWT RATED MWT % POWER 2150.220 3323.000 64.71%
Rodline = % Power = 96.46% 98.81%
.3 + .7*%WT
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, 28 m
-.y Page 130 of 132 Supplemental Final Startup Report Procedure Number: 'N2-SUT-79-6 Reactor Internals Vibration Measurement 100 Percent' Load Line Corrected Recorded
- Data Data Step 6.3.1' OD-3 Dated 03/05/88 1020 WT FACTOR WT* FACTOR M1b/Hr M1b/Hr
. 106.99 1.045 111.805 = 103.05% 98.61%
108.500 MWT RATED MWT % POWER 3306.220 3323.000 99.50%-
Rodline = % Power = 97.42% 100.47%
.3 + .7*%MT Step 6.3.7- OD-3 Dated 03-05-88 1217 -
WT FACTOR WT* FACTOR M1b/Hr M1b/He 21.09 1.045 22.039 = 20.31% 19.44%
108.500 MWT RATED MWT % POWER 521.550 3323.000 15.70%
Rodline = % Power = 35.49% 35.99%
.3 + .7*%MT ,
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Corrected Recorded Step No. Page- Doc. Type Parameter Data Data 4.1.4 17 DS1 JP-A-FLO 28.95 27.70 4.1.4 17 DS1 JP-B-FLO 28.01 26.80 4.1.4 18 DS1 WT 56.68 54.24 6.1.1/6.1.2 19 DS2 JP-A-FLO 25.12 24.04 6.1.1/6.1.2 19 DS2 JP-B-FLo 25.85 24.74 6.1.1/6.1.2 19 DS2 WT 50.77 48.581 6.1.7 20 DS3 JP-A-FLO 29.02 27.774 6.1.7 20 DS3 JP-B-FLO 27.93 26.732 6.1.7 20 DS3 WT 56.70 54.254 6.1.12 21 DS4 JP-A-FLO 42.95 41.10 6.1.12 21 DS4 JP-B-FLO 41.59 39.80 6.1.12 21 DS4 WT 84.17 80.55 6.1.17 22 DSS JP-A-FLO 56.64 54.20 1B i
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I E Page 131 of 132 Supplemental Final Startup Report Procedure Number: N2-SUT-79-6 Reactor Internals Vibration Measurement 100 Percent Load Line Corrected Recorded Step No. Page Doc. Type Parameter Data Data 6.1.17 22 DSS JP-B-FLO 58.00 55.5 6.1.17 22 DSS WT 113.87 108.97 4.2.3 23 DS6 JP-A-FLO 56.33 53.90 4.2.3 23 DS6 JP-B-FLO 57.37 54.90 4.2.3 24 DS6 WT 112.96 108.10 6.2.2 25 DS7 JP-A-FLO 56.53 54.10 6.2.2 25 DS7 JP-B-FLO 56.64 54.20 6.2.2 25 DS7 WT 112.44 107.60 6.2.8' ~26 DS8 JP-A-FLO 73.36 70.20 6.2.8 26 DS8 JP-B-FLO 16.41 15.70 6.2.8 26 DS8 WT 57.79 55.30 4.3.3 27 DS9 JP-A-FLO 56.43 54.00 4.3.3 27 DS9 JP-B-FLO 55.39 53.00 .
4.3.3 28 -DS9 WT 111.69 106.88 6.3.1/6.3.2 29 DS10 JP-A-FLO 56.39 53.96 6.3.1/6.3.2 29 DS10 JP-B-FLO 57.00 54.55 6.3.1/6.3.2 29 DS10 WT 113.07 108.20-6.3.8 30 DS11 JP-A-FLO 17.45 16.70 6.3.8 30 DS11 JP-B-FLO 4.49 4.30 6.3.8 30 DS11 WT 21.95 21.00 MAX CORE FLOW = 104.95% RATED CONCLUSION: GENE SAN JOSE SKALL USE THE CORRECTED DATA (FACTOR 1.045) FOR VIBRATION DATA ANALYSIS, SEE ATTACHMENT 1. MAX CORRECTED CORE FLOW DOCUMENTED IN THIS TEST = 104.95% RATED.
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l Page 132 of 132-Supplemental Final Startup Report Procedure Number: N2-SUT-20-W Steam Production Corrected ' Recorded Data Data
- S tep 6.'1'.1/6.1. 3 /6.1. 6 - Data Sheet 2' f Parameter Unit
, Core Flow ~ M1b/Hr 111.93 107.11 Core Flow % Rated 103.16% 98.72%'
' Step 7.1.1' Data Sheet 5 Parameter Unit Avg Core Flow M1b/He 112.03 107.21 Avg Core Flow % Rated 103.26% 98.81%
. Step 7.1.2.E '
Max Core Flow in N2-RPSP-1 M1b/Hr 113.24 108.36 Max Core Flow -% Rated 104.37% 99.87%-
Step 7.1'.1.4 of N2-RPSP-1: Core Flow is less_than or equal to 108.5 M1b/He UNSAT-Step 8.1.1 (Level'1 Criteria) The NSSS parameters ' as determined by. using -
normal operating ' procedures shall be within the appropriate -
license restrictions. UNSAT CONCLUSION: INCREASED CORE FLOW CENERATED A LEVEL 1. CRITERION VIOLATION BUT 104.37% OF RATED CORE FLOW CAN BE ACCEPTED PER ATTACHMENT 1.
' CORE. FLOW DATA IN THIS PROCEDURE SHALL BE CORRECTED WITH A FACTOR OF 1.045.
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ATTACHMENT 1, -
E ilNTERNAL CORRESPONDENCE
,e .. . .d '*'= MY11ATARA s g R u WlOMAWK-
, FRcM E. asternak/J. Conwayk -
DISTMCT . Nine Mile Point Nuciaar Station
.70 E. Abbott /J. W4lifa DATE September 23,1988 MLE C00E NMP38530 SUSJECT . Operation of NMP2 at Grastar Than Rated Core Flow !
Backsround on 9/15/88 it was determined that an arror anda during the startup test *
. program at Nina Mile Point Unit 2 resulted in improper calibration of the core flow instrumentation for that unit.: This resulted in tha plant be operated at cora flows as high as 104.5% of rated for aztended periods of time between 11/5/87 and 9/3/88. An evaluation of the impact of this condition has been performed. The results of this avaluation are provided below.
Event Analysis Improper calibration of the total core flow instrumentation did affect other instrumentation and calculations / evaluations important to plant safety. The
- affects are as_follows:
- 1. Core Flow Indication
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While operating at 100% of rated cora flow (i.e., 108.5 albs /hr.) actual core flow was approzinately 104.5% of rated (i.e.,113.38 albs /hr.). .I Steady state operation above 100% of rated cora flow is outside the currently approved design basis for NMP2, however,- an Increased Cora Flow (I.C.F.) analysis has been performed for NMP2 'which concludes that the plant can be safely operated at up to 105% of raced _ core flow without i requiring any changes to currant operating limits. Since resetor vessel internals vibration data was collected at flows near 104.5% of rated and previously evaluated as meeting applicable vibration critaria, it is '
concluded that the current design basis.can be revised to allow operation at up to 105% of rated core flow indefinitely (i.e., it is realized that
- regulatory review and concurrences would be required).
- 2. Fual Thermal Limits Evaluation .
1 The Maximum Ave.. age Planar Linear Hast Generation Rata (MAPGGE) and Linmar Haac Generation Rate (MGE) linics are not flow dependant. While the power shape calculated by the process computer may be slightly ]
affected, calculations of peak fuel bundle nodal powers used to compara t against these limits are not significantly affected by the flow measureaanc arror. The calculated critical bundle power will be lower than actual dua to the flow asasureaant arror and will result in a=1an1= tion of conservative Minimum Critical Power Ratio (MCPR) values.
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ATTACHMENT 1 E. Abbott /J. Willis
^
Page 2 September 23, 1988
- 3. Teawa=1 Specification Instrument Setpoints The setpoints for the APRM Flow Biased Thermal Trip as well as the R3M and APRM tod Block functions are affected by the calibration error. This'is
'due to the fact that rated loop drive flow was evaluated to be '
- approziastaly 44,100 gym vs. the correct value of approximately 41,800 syn. This results in implementation of trip setpoints lower than tech.
spec. requirements (i.e., which is allowed by tech. specs.) by a_ factor proportional to total drive flow in the flow biased regions. The nazimum setpoint implemented when clamping the flow biased setpoint is not affected by the calibration error. The APRM flow unit upscale Rod Block ~
setpoint (108% nominal-111% a n owable) is affected by the calibration in a nonconservative manner. This function would not have occurried until u 3.94% flow was reached. This situation does not compromise safety for the fonowing reasons:
- The ICF analysis provides an nuovable value for this function of 114%.
- The purpose of this function is to provida a block if the flow unit output fails upscala disabling the flow biased rod blocks. The setpoint j salaction for this function is somewhat arbitrary. The protective
, action would still have been provided if an upscala signal failure had ,
occurred. {
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- No credit is takan for this fasture in any FSAE Chaper 15 analysis. '
~4. Rasetor Yessel Internals Vibration i As previously discussed, incarnals vibration data was recorded and analyzed as part of the starrup test program while the reactor was operating at near 104.3% of rated flow. Startup test program acceptance critaria for anowable vibration levels were satisfied under these conditions. ,
- 5. Startup Test Program Easults There is some minor impact on the documentation for the majority of the startup tests conducted after the initial core flow instrumentation calibration. Only a few tests contain a=1a"1=tions or evaluations against acceptance critaria that are affected by the calibration arror. In no instance is it expected that the conclusions derived from the cast program are significantly affaccad.
- 6. Summary Conclusion Previous operation of NMP2 with total core flow in excess of 100% of rated did not adversely affect plant safety. In addition plant response to ,
transients and accidents analyzed in the FSAE would not have been 9 compromised.
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ATTACHMENT 1 ~
E. Abbott /J. Willis Page 3 September 23,1988 Correceive Actions The following corrective actions were completed prior to allowing plant operation in operational condition 1.
- Rarun jet pump calibration program using correct input data.
- Racalibrace jet pump loop flow summer cards.
- Racalibrate total drive flow summer cards.
Ravise jet only.
operation pump and APRM flow operability curves for single loop The following corrective actions were not judged to be restraints to antering operational condition 1 but were implemee e d as quickly as practical.
- Revise process computer jet pump flow constants. ~
- Ravise process computer WTC, WDC arrays.
- Adjust total drive flow limiter. '
The fonowing corrective actions win be completed prior to plant restart fonowing the fall outage which is currently scheduled to begin 10/1/88.
- Revise two loop operating map.
- Complace detailed evaluation and reem" 414= tion of affected startup test program results.
- Ravisa all APRM flow and jet pump operability curves for 'N2-OSP-LOG-0001.
- - Publish a permanent plant test procedure for core flow calibration with adequate controls to prevent future errors of a sf=41=* nature. This test will be performed during restart after the fall outage.
- Raview and upgrade as necessary procedural controls associated with offlina evaluation of fuel thermal limits via the Backup Core Limits Evaluation (B.U.C.L.E.) program.
LER 88-22 Considerations LER 88-22 reported a short tern excursion above 100% of rated core flow due to poor electrical contact between a summer card and its connector.
Actual flow for this event was deterniced to be 109.984 albs /hr. As a result of recent events we now know that the flow was actuany H4.933 '
albs /hr. or 105.9% of rated. The i= pact of the core flow calibration error on this previous excursion is as follows: es
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._ ._. ~. . m. ..- . . . ~ . . . . . . _ . . . . _ . . . . . _ . - _ - , _ m.
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- ATTAQOtENT 1
-1.' Abbott /J. Willis
?Fage 4 September 23, 1988
- 1. Core Flow Indication Indicatedcoreflowduringthisavantwasapproximataly106.5 albs /hr. vs. an actual value of 114.933 albs /hr. (98.2% vs. 105.9%).
The ICF analysis concludes that no operating linic ah====e 'are required for operation up to 105% flow. It is possible that's anzimisa change of '.01 to the MCPE operattag limit would have been appropriate when operating at 106% flow. This does not represent a safety concern, however, because as previously discussed the calibration arror caused the process computer to a=ta=1=ta erf.tical' bundle powers conservatively. In addition, the reactor core has always been operated to maintain significant margin between the operating MCPE and the MCPE limit (i.e., on tha order of .15 margin vs. 01).
- 2. . Fuel vh===1 Limits Evaluation h previous discussion on tharsal limits is still applicable. Aa
- additional margin of safety is provided by the fact that the reactor core is operated. to 'asintain margin to fuel *h==t limits.~
- 3. T=abia=1 Specification Instrument Setpoints h previous discussion is still applicable since this event provides no further impact to the drive flow signals that has not already been evaluated. -
- 4. Rasetor Yassal Internals Yibration/ N d4a-h conclusions of General Electric's previous evaluation on_this excursion are still applicable and ha-d'ar since that evaluation was based on data recorded at approziastaly 104.5% flow instand of 100%
flow. h ICF analysis on vessel internals and fuel assembly 1_a-dia!
was performed for 106% flow and therefore bounds this excursion.
- 5. Startup Test Program Easults h startup test program was c&alad-d prior to this azeursion.
- 6. Summary Conclusion h core flow excursion reported by LER 88-22 did not place the plant in a condition that compromised plant safety. Flant response to transients and accidents analyzed in the TSAR would have been acceptab?,a.
RJP/JTC/jaa ze: C. D. Terry
'W. C. Drews J. 5. Spadafore
- 1. C. Smith' E. E. Jenkins 8"
~ P. A. Mazzafarro '
W. A. Cook
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