JAFP-85-0682, Cycle 7 Startup Test Rept
| ML20135H545 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/21/1985 |
| From: | Radford Converse POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JAFP-85-0682, JAFP-85-682, NUDOCS 8509230752 | |
| Download: ML20135H545 (5) | |
Text
.. .
Page 1 of 3 CYCLE 7 START-UP TEST REPORT Cycle 7 operations commenced June 1, 1985 ending a 105 day refueling outage. The start-up physics test program was conducted from May 28, 1985 through August 8, 1985 utilizing Reactor Analyst Procedure 7.1.17 titled Refuel Start-Up Program, Revision 7.
CORE LOADING AND VERIFICATION One hundred and ninety-six new fuel assemblies designated LYA001-LYA196 were loaded during the refueling outage. Three hundred and sixty-four irradiated fuel assemblies were shuffled to new locations. The final loading map is attached as Figure 1.
Core verification was performed in accordance with RAP 7.2.4 using an underwater T.V. camera to verify proper fuel assembly location, orientation, and seating.
CONTROL ROD DRIVE TESTS Prior to start-up, surveillance test F-ST-23B, Control Rod Coupling Integrity Test and F-ST-20K, CRD Exercise / Venting Timing Test, were satisfactorily completed for all 137 control rods.
Prior to reaching 40% rated core thermal power, control rod scram time testing was conducted. The results are tabulated below.
Notch Technical Specification Average of Observed Limit (Secs.) 137 Rods (Secs.)
46 .338 .312 38 .923 .726 24 1.992 1.466 04 3.554 2.585 The average of the scram insertion times for the three fastest operable control rods for all groups of four control rods in a two by two array were less than the maximum times allowed by the Technical Specifications.
SHUTDOWN MARCIN TEST Criticality was achieved on May 28, 1985 by performing the insequence critical shutdown margin test which demonstrated a shutdown margin of
.81 % AK. By referencing the cycle management report, the moderator temperature correction factor was determined to be .0015 AK, the reactor period correction factor .0004 AK, and the R value .0006 AK.
8509230752 OW ADOCK O5000333 PDR PDR P
fh
\\\
Page 2 of 3 REACTIVITY ANOMALY A comparison of the expected and actual control rod density was performed at 100% core thermal power and 96.7% rated core flow. The actual control rod inventory was 396 notches inserted, and the predicted inventory was 420 notches inserted. The + 1% AK reactivity boundaries were 120 (-1% AK) and 720 (+1% AK) notches inserted.
POWER DISTRIBUTION MEASUREMENTS Core power distribution was monitored throughout the start-up using the process computer. During the ascension to full power, LPRM calibrations were performed at 50%, 75% and 100% core thermal power. Reactor core thermal limits were maintained within Technical Specifications.
CORE POWER SYMMETRY Core power symmetry was checked at 50%, 75%, and 100% power. The maximum difference in power level of symmetrically located fuel bundles was found to be less than 10%.
LPRM RESFONSE TEST During scram time testing, when control rod insertions and withdrawals were made, an LPRM response test was conducted on all 124 LPRMs which verified that each detector is connected to the appropriate flux amplifier. Five LPRMs were replaced during the refuel outage.
CORE FLOW EVALUATION Two core flow evaluations were performed at 100% thermal power. The value for total core flow provided by the instrumentation was found to agree within 2% with the value calculated by the jet pump calibration program.
PROCESS COMPUTER CHECKOUT The process computer databank for Cycle 7 operation was installed and satisfactorily checked out over the period of time from May 31, 1985 until June 3, 1985. This work was performed by site personnel with the assistance of Mr. Tim Leong of the General Electric Nuc1 car Data Banks group from San Jose, California. Core performance calculations were made using the off-line Backup Core Limits Evaluation program at 50%, 75% and 100% core thermal power. In each case, the location and the value calculated for MFLCPR, MFLPD, and MAPRAT agreed very closely with the plant process computer calculations.
PRESSURE REGULATOR TEST The pressure regulator test, RAP 7.3.18 verified that the decay ratio of the reactor pressure transient caused by a 10 psi change in the pressure set-point for each pressure regulator is less than 1.0
o' '
.o Page 3 of 3 DETERMINATION OF RATED DRIVE FLOW In conjunction with the core flow evaluation, data was obtained t 6
determine rated drive flow. The result was calculated to be 33.03 x 10 lb/hr.
TIP AXIAL ALIGKMENT A test to verify the proper alignment of the traveling incore probe system was performed and adjustments were mada as necessary.
TIP UNCERTAINTY TEST The standard deviation was calculated for symmetrically located TIP strings, and found to be 3.2%, well below the 8.7% value assumed in the Licensing Topical Report.
E6-41 !
- i. _ . _ . _ _ _ _ _ _ _ _
!I-SER/ISRBB FUEL SERIAL NUMBERS
_ _ _ _ _ ncygg_t_ Q_
i il
!" LJX LJZ LJX LJZ LJX LJX LJZ LJX LJZ LJX 4:
i S2 __ _ . _ . . . __. _ . _ - _ _ 913 040 989 055 939 983 050 914 028 993 - - - - - - -A LJX LY4'LY4 LY4 LYA LY4 LY4 LYA LYS LY4 LY4 LJX
- 50 953 865 945 884 127 900 944 152 012 876 940 882
_ _ ._ . .__ .LJZ LJZ LJX LY4 LYA LY4 LYA LY4. LYA.LYA LY4 LYA LY5 LYA LY4 LJX LJZ LJZ- ----
-48 041 012 988 963 120 993 064 886 144 146 901 075 033 079 970 917 012 045 5 LJX LY4 LYS LY4 LYA LY4 LYA LY4 LYA LJ4 LY4 LYA LYS LYA LY4 LYA LY4 LY4 LY4 LJZ 3
- 46
..._ _ 998 M 8 013 992 162 905 040 934 180 907.983.187 041 186 955 179 860 974 888 056 'f LJZ LY4 LYA LY4 LYA LY4 LYA LJZ LYA LJX LYA LYA LJX LYA LJZ LYA LY4 LYA LY4 LYA LY4 LJZ
'44 026 960 118 987 104 977 115 010 036 991 150 089 876 028 001 098 870 145 914 054 899 018i
- _ LJZ LY5 LYS LYA LJX LYA LY4 LYA LY4 LYA LJX LJX LYA LY4 LYA LY5 LYA LJX LYA LY4 LY4 LJZ d
'42 038 007 021 006 881 013 897 143 984 183 924 921 184 915 090 001 185 974 068 947 937 016 3 40 LJX LY4 LYA LJX LYA LY4 LYA LJX LYA LY4 LYA LYA LYS LYA LJX LYA LY5 LYA LJX LYA LY5 LJX d "
4
. 895 913 164 956 157 978 174 906 173 864 072 066 037 069 957 011 036 012 926 110 035 916 LJX LYS LYA LY4 LYA LY4 LJX LY4 LY4 LYS LYA LJZ LJZ LYA LY4 LY5 LYS LJX LY5 LYA LY4 LYA LYS LJX 38 893 002 170 990 177 933 961 863 989 016 181 053 029 172 957 039 054 978 049 153 862 052 000 903
' _ LJX LY4 LYA LY4 LYA LY4 LYA LY4 LYA LJX LYA LJX LYA.LYA LJX LYA LJX LYA LY4 LYA LY4 LYA LY4 LY 36 899 893 117 909 189 930 042 946 048 946 041 888 178 191 979 195 948 158 941 160 878 002 889 091 996 877, LJZ LY4 LY4 LYA LJZ LYA LJX LY5 LJX LY5 LY4 LYA LJX LJX LYA LYS LY4 LJX LY4 LJX LYA LJZ LYA LY4 '.f5 LJX 234 003 892 904 176 043 039 887 022 990 024 859 182 885 920 165 010 964 915 969 922 019 006 171 980 051 996 l LJX LY5 LYA LY4 LYA LY4 LYA LY4 LYA LY5 LYA LJX LYA LYA LJX' LYA LY4 LYA LY4 LYA LY4 LYA LY4 LYA LYS LJX 32 879 005 102 910 107 894 194 997 196 003 148 954 155 114 977 053 883 109 999 005 949 126 972 135 043 886
_LJZ.LYA LY4 LYA LJX LYA LY4 LYA LJX LYA LJX LY4 LY4 LY4 LY4 LJX LYA LJX LYA LYS LYA LJX LYA LY4.LYA LJZ.
30 007 159 932 188 931 190 867 099 955 141 910 906 998 882 951 911 142 919 021 040 088 980 168 942 166 032 LJX LY4 LYA LY4 LYA LJX LYA LJZ LYA LJX LYA LY4 LJX LJX LY4 LYA LJX LYA LJZ LYA LJX LYA LYS LYA LY4 LJX Z8 892 857 151 994 051 880 106 020 101 923 034 861 897.905.948 192 950 193 052 167 949 169 008 045.935 981 LJX LY4 LYA LY4 LYA LJX LYA LJX LYA LJX LYA LYS LJX LJX LY4 LYA LJX LYA LJZ LYA LJX LYA LY4 LYA LY4 LJX 26 932 954 043 971 103 967 062 999 061936 085 042 868 896 887 004 994 015 005 017 982 009 903 C25 912 902
.LJZ LYA LY4 LYA LJX LYA LY4 LYA LJX LYA LJX LYS LY4 LY4 LY4 LJX LYA LJX LYA LYS LYA LJX LYA LY4 LYA LJZ-24 004 056 976 175 959 014 961 092 965 136 975 015 986 858 916 912 134 987 116 029 008 900 122 991 095 009 LJX LY5 LYA LY4 LYA LY5 LYA LY5 LYA LY4 LYA LJX LYA LYA LJX LYA LY4 LYA LY4 LYA LY4 LYA LY4 LYA LY4 LJX.
22 871 004 161 956 016 047 086 011 073 953 018 984 074.139.945 149 891 147 981 020 895 046 918 029 896 884 LJZ LY5 LYS LYA LJZ LYA LJX LYS LJX LY4 LY4 LYA LJX LJX LYA LY4 LY5 LJX LY4 LJX LYA LJZ LYA LY4 LY4 LJZ 20 037 020 030 063 033 108 875 018 963 968 921 050 970 889 023 885 052 898 922 962 137 030 082 880 931 036
_.LJX LYS LYA LY4 LYA LYS LYA LY4 LYA LJX LYA LJX LYA LYA LJX LYA LJX LYA Lf5 LYA LY4 LYA LY5 LYA LY4 LJX-18 964 014 032 952 007 017 133 9E8 003 878 033 883 060 047 944 058 925 131 038 132 902 138 050 097 927 986 LJX LY4 LYA LY4 LYA LY4 LJX LY4 LY4 LY5 LYA LJZ LJZ LYA LY4 LYS LY4 LJX LY4 LYA LY4 LYA LY5 LJX 16 _ 933 966 083 959 078 962 934 871 967 026 067 039 027 024 924 055 911 890 943 105 875 038 019 908 LJX LY4 LYA LJX LYA LYS LYA LJX LYA LY4 LYA LYA LY4 LYA LJX LYA LY4 LYA LJX LYA LY4 LJX 14 872 877 070 873 001 023 057 927 044 939 121 065 866 087 869 125 929 128 976 140 872 938
_ _ _ _ LJZ LYS LY5 LYA LJX LYA LY4 LYA LYS LYA LJX.LJX LYA LY5 LYA LY4 LYA LJX.LYA LYS LY4.LJZ ,
12 '
021 009 044 031 985 035 973 163 032 037 971 891 076 046 112 923 026 943 030 045 982 051 LJZ LY4 LYA LYS LYA LY4 LYA LJZ LYA LJX LYA LYA LJX LYA LJZ LYA LY4 LYA LYS LYA LY4 LJZ 19 .. ___ 035 985 100 053 130 874 154 046 077.918 113 129 973 059 008 049 920 055 025 111 926 002 -. _
LJZ LY4 LY4 LYS LYA LY4 LYA LY4 LYA LYS LY4 LYA LY4 LYA LY4 LYA LYS LY4 LYS LJZ 08 031 950 873 034 156 936 027 958 119 031 890 084 938 071 868 096 048 925 056 017 LJZ LJZ LJX LY4 LYA LY4 LYA LY4 LYA LYA LY4 LYA LY4 LYA LY4 LJX LJZ LJZ _. _
f6_ ___ 048 019 972 97? 094 881 080 879 123 010 917 022 869 093 928 904 023 054 i
LJX LY4 LYS LY5 LYA LY4 LY4 LYA LY4 LY4 LY5 LJX 0 4___ _
935 965 006 027 081.975 995 124 919 898 028 941 _ _ . _ .
LJX LJZ LJX LJZ LJX LJX LJZ LJX LJZ LJX 02 870 022 969 011 992 907 014 894 025 951
~ ~
1 ~ ~ 3~ 5 7 9 11' ~ ~13 15 17 '19' 21 ~ 23 25 ~ 32 ~ 29~~ 31 33 35 37 39 4173~ 45 47 49 SI
?
. _ _ .d CYCLE 7 CORE LOADING MAP !
A, i
h l l:
, *y
- Jimei A. FitaPItrick Nuclerr Power PI:nt i PO. Ebu 41
- Lyccming. New York 13093 315 342.3840 Radford J. Converse
- b NewYorkPower 4# Authority
- August 21, 1985 JAFP 85-0682 Dr. Thomas E. Murley Regional Administrator United States Nuclear Regulatory Commissicn Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
Cycle 7 Start-Up Test Report
Dear Mr. Murley:
Enclosed you will find the Cycle 7 Start-Up Test Report for the James A.
FitzPatrick Nuclear Power Plant, DPR-59, Docket No. 50-333, which is submitted to you in accordance with Regulatory Guide 10.1 and Plant Technical Specifications paragraph 6.9.A.1.b.
We trust you will find this information satisfactory. However, should you desire additional information, please do not hesitate to contact us.
/
. aaau RADFORD J. CONVERSE RJCr :kjm Enclosure cc: J. C. Brons R. A. Burns L. Cuaquil T. Dougherty R. Taylor G. Rorke W. Fernandez D. Burch R. Chase H. Fish Document Control Center J. Gray l
i
,