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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] Category:TEST REPORT
MONTHYEARML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 JAFP-95-0291, Ja FitzPatrick Cycle 12 Startup Testing Rept1995-06-23023 June 1995 Ja FitzPatrick Cycle 12 Startup Testing Rept ML20081H0141995-03-21021 March 1995 Four Yr Performance Testing Rept (Per 10CFR55.54(b)) ML20065G6941990-10-0909 October 1990 Reactor Containment Bldg Integrated Leakage Rate Test JAFP-90-0697, Cycle 10 Startup Testing Rept1990-09-17017 September 1990 Cycle 10 Startup Testing Rept JAFP-89-0140, Cycle 9 Startup Testing Rept1989-02-21021 February 1989 Cycle 9 Startup Testing Rept JAFP-87-0534, Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test1987-04-30030 April 1987 Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test ML20155G4391986-04-25025 April 1986 Ja Fitzpatrick Nuclear Power Plant Reactor Pressure Vessel Surveillance Matls Testing & Fracture Toughness Analysis JAFP-85-0682, Cycle 7 Startup Test Rept1985-08-21021 August 1985 Cycle 7 Startup Test Rept ML20137F7931985-05-31031 May 1985 Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C Periodic Tests for May 1983 - May 1985, Ja Fitzpatrick Nuclear Power Plant ML20106F4301984-09-30030 September 1984 Recirculation Sys Welds - Sept 1984 Outage ML20082M7801983-11-18018 November 1983 Cycle 6 Startup Test Rept ML20054J1921982-05-31031 May 1982 Voltage Profile Test Rept ML20052H9581982-05-0707 May 1982 Cycle 5 Startup Test Rept. ML20079F7831981-12-0707 December 1981 Certification Test Rept for Mechanical Snubber PSA-3,Serial Number 8383 ML20079F8021981-12-0707 December 1981 Certification Test Rept for Mechanical Snubber PSA-3,Serial Number 8387 ML19340B6291980-11-0707 November 1980 Cycle 4 Startup Test Rept. ML19241B2891979-04-18018 April 1979 Cycle III Startup Test Rept ML19308A2881979-03-0606 March 1979 Reactor Containment Bldg Integrated Leak Rate Test Type a, B & C.Periodic Tests for Jan 1976 to Nov 1978. ML20063A9921976-12-0202 December 1976 Design Verification Test Summary,Model 7567F ML20081B9691974-03-20020 March 1974 Integrated Leak Rate Test:Computer Program for Primary Containment ML20116N6801972-07-19019 July 1972 Seismic Analysis of 3-Inch,20-Inch & 24-Inch Butterfly Valve Assemblies for S&W,Agent for Pasny 1999-03-21
[Table view] |
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. . Page 1 of 2 CYCLE 6 START-UP TEST REPORT Cyclo 6 operations commenced September 2,1983 ending a 90 day refueling cutage. The start-up physics test program was conducted from September 1,1983 through November 5, 1983 utilizing Reactor Analyst Procedure 7.1.17 titled Refuel Start-up Program, Revision 6.
CORE LOADING AND VERIFICATION
- Two hundred new fuel assemblies designated LY4857-LY5056 were loaded during the refueling outage. Three hundred and sixty irradiated fuel assemblies designated LJB, LJM, LJX, and LJZ 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 ur'ng an underwater T.V. camera io 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, was satisfactorily completed on 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 (Sees.)
46 .338 .325 .
38 .923 .736 24 1.992 1.476 04 3.554 2.586 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 MARGIN TEST
" Criticality" was achieved on September 2, 1983, on the 11th rud of rod sequence control system group number 2, notch position 14, with reactor temp-erature at 145"F and a period of 213 seconds. The shutdown margin was calcu-lated to be 1.0% AK exceeding the technical specification of 0.38% AK + R. By referencing the cycle management report provided by the vendor, the moderator temperature ccefficient-was determined to be - 2.21 x 10-5 p "F, the period correction factor 3 x '10-4 AK, and the value of R (maximum decrease in shutdown margin) = 0.0. ,
REACTIVITY ANOMALY J A comparison of the expected and actual _ control rod density was performed at 100% core thermal power and 96.7% ratort core flow. The actual control rod inventory was 268 notches inserted, and the predicted inventory was 360 notches inserted. The +' 1% AK reactivity boundaries were 53 (-1% AK) and 653 (+ 1% AK) notches inserte6.'
B312060274 031118 PDR ADOCK 05000333 P PDR
{ -. -
Page 2 of 2
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POWER DISTRIBUTION MEASUREMENTS b Core power-dist'ribution was' monitored throughout the start-up using the process computer. During the ascension' to full power, six LPRM calibrations were performed at 26%, 35%, 57%, 64%, 90%,.and.100% core thermal power. Reactor core thermal limits were maintaiaed within technical specifications.
-TIP REPRODUCIBILITY-t A traveling incore probe reproducibility test was performed at 100% power, c and the total uncertainty.was calculated to be 3.09%,, well below.the 8.7%
assumed by the vendor.
CORE' POWER SYP94ETRY
. Core power symmetry was checked at 30%, 50%, 75%, and 100% power. The maximum difference in power level of symmetrically located fuel. bundles was found to be less than 10%.
LPRM RESPONSE TEST Nine LPRMs were replaced during the refueling outage, and a test to verify that the LPRMs are connected to the correct flux amplifier was performed using RAP 7.3.8. The LPRMs responded satisfactorily to control rod movement.
CORE FLOW EVALUATION Two core flow evaluations were performed at 100% thermal power. The value
' for total core flop provided by the instrumentation was found to agree within 1%
with the,value calcrlated by the jet pump calibration program.
PROCESS COMPUTER CHECKOUT 1The vendor supplied, and came to the site, to load the data classes for
- cycle 6. ; Tests were performed to ensure the data classes were loaded properly.
Core performance calculations were made using the BUCLE program at 35%, 50%,
75%, and 100% core thermal power. In each case, the location and the value 4 calculated for MFLCPR, MFLPD, and MAPRAT. agreed very closely.
r 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 pressura set-point for each pressure regulator is less than 1.0.
i
' DETERMINATION OF RATED DRIVE FLOW In conjunction with the core flow e si .ar data was obtained to deter-(
mine rated drive flow. The result was taj 3p? ,to be 33.51 x 106 lb/hr.
l TIP AXIAL ALIGNMENT t
L A test to verify the proper alignment of the traveling incore probe system was performed, and the results showed the axial alignment to be satisfactory.
l
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--- -- LJM LJM LJM LJM LJM KIN LJM LJM LJM LJM 52 525 475 558 588 585 TJ9 565 598 535 563 -
LJM LJX LJI LJI LJI LT4 LT4 LJX LJI LJI LJI LJM 58 - -
497 881 946 954 986 906 951 957 977 948 974 494 - --
! LJB LJM LJE LJE LJI LT4 LJN LT4 LJI LJI LT4 LJN LT4 LJE LJK LJE LJN LJ8 48 388 514 895 888 885 984 549 f45 953 882 876 545 915 928 979 916 524 338 l - LJB LJI LJK LT4 LJE LT5 LJZ LT4 LJZ LT4 LTS LJZ LT5 LJZ LY4 LJI LY4 LJI LJI LJB- ---
i 46 336 897 924 977 939 913 953 884 942 897 801 912 012 029 974 983 878 921 985 327 l LJ8.LJE LJM LY4 LJI LT4 LJM LT4 LJM LT4 LJM LJM. LY4 LJM.LT4 Lcs LT4 LJI LT5 LJM LJI LJB ,,, -
i -. 4 4 - --- 316-961-577-989-913-992-564-998-556 908 522 543 888 578 882-559 868 993 839-552-978-344 ,------- -
1 LJM LJE LT5 LJE LT4 LJZ LT4 LJZ.LT4 LJZ LT4 LYS LJZ'LT4 LJZ LT4 LJZ LY4 LJI LT4 LJK LJM
! <2 557 888 SZZ 989 985 955 963 948 886 041 863 954 845 901 828 978 858 955 914 969 949 601
! - LJI LT4 LJI LT4.LJM LT4 LJN LT4 LJM LT4-LJM LJM LY4 LJM LY4 LJM LY4- LJM'LT4 .LJI-LY4- LJI-------
, 48 988 999 899 999 471 865 581 988 538 987 469 451 914 547 944 689 948 467 889 877 862 917 LJM LJK LJK LT4 LJZ LT4 LJI LY4 LJZ LT4 LJK LT4 LYS LJI LT5 LJZ LT5 LJE LY4 LJZ LT5 LJI LJI LJM
, ~38 492-935-892-913 807-893-879-864-849-978-938-993 933 928 836-834 837 886 996 832-835-981-919 533 i LJM LJK LJI LT5 LJM LT5 LJN LT4 LJN LJK LJM LT4 LJM LJM LT4 LJM LJE LJN LT5 LJM LT5 LJM LT4 LJK LJI LJM
. 36 554 956 923 997 528 992 569 847 479 991 476 987 456 459 983 59Z.876 452 S48 526 998 598 937 958 9'S 546
! LJM LJI.LY4 LJZ LY4 LJZ LT4.LJZ LJI-LJM LT4 LJI-LYS LT4 LJI.LT5 LJM LJI LJZ LT4 LUI LY4-LJZ LY4 LJE LJn
! 34 537 998 894 8Z8 C61 993 857 947 931 584 859 937 916 957 966 819 591 988 913 935 996 948 85Z 949 915 542 1 LJM LJK LJM LT5 LJM LT4 LJM LT4 LJN LT5 LJM LT4 LJM LJM LT5 LJM LT4 LJM LY5 LJM LY4 LJM LT5 LJM LJK LJM '1 1 - 32 484 918-558 005 602-932-579-933-518 983-578 934-591 582-841 593 883 -599 949- 697-942 57Z 843- 562 98 7 573 $q LJM LJI LY4 LJZ LT4 LJZ LY5 LJI LT4-LJI LT4 LJE LJZ LJZ LJ7 LT4 LJK LT5 LJK LT4 LJZ LT4 LJZ LT5 Lo. .m c:
39 593 887 892 533 969 926 821 995 994 941 910 998 919 991 956 97Z 968 998 966 947 818 899 916 951 92Z 511 pj 1
i LJM LT5 LJE LY4 LJM.LT4 LJM LT4.LJM LT4 LJM LJZ LJM LJM LJZ-LJM LY4 LJN LY4 LJM LY4 LJM LT4 LJI LT4 LJM '
Z8 489 924 893 936 551 946 462 984 469 997 495 943 516 4?9 986 555 999 463 980 458 941 566 878 903 964 19 3 LJM LY4 LJE LY5 LJM LT4 LJM LT5 LJM LT5 LJM LJZ LJA LJM LJZ LJM LY4 LJM LY4 LJM LV5 LJM LY4 LJK LY5 LJN 26 698 968.933.917 4S5-988-453-938 474 911 58Z 933 548 588 -838 698-981 464 888 466 -838 481-90Z 998-95Z 519 i LJM LJE LT5 LJZ LT4 LJZ LT5 LJI LT4 LJK LT4 LJZ LJZ LJZ LJZ LT4 LJK LT4 LJI LY5 LJZ LY4 LJZ LT4 LJI LJM
- 24 571 875 029 921 985 935 944 929 971'874 956 931 #46 588 917 918 948 993 991 845 SeZ 926 051.931 962 505 LJM LJI LJM LT5 LJM-LT4-LJN LT4.LJM LY4 LJM LY4 LJM LJM LT4.LJM LT4 LJM LT4 LJN LT4 LJM.LT4-LJN LJI LJN 4
22 483 975 532 984 567 976 541 962 491 953 549 958 594 589 938 517 891 498 943 527 991 498 896 479 912 482 LJM LJI LYS LJI LT5 LJZ LT4 LJI LJE LJN LT4 LJI LY5 Lf4 LJE LT4 LJM LJK LJZ LY4 LJZ LT4 LJZ LT4'LJI LJM 29 598 963 047 999 S42 937-954-997-959 686-921.942 826 924-999 885 4C6 998 844 912-836 887-905 895-898 596 LJM LJE LJK LT5 LJM LT4 LJM LT4 LJM LJK LJM LT5 LJM LJN LT4 LJN LJE LJM LT5 LJM LT5 LJM LT4 LJI LJI LJM 18 496 873 936 999 477 966 569 961 455 918 488 831 473 465 899 597 973 469 929 488 s19 487 982 994 976 529 LJN LJK LJI LY4 LJZ LT5 LJI-LY4 LJZ LT5 LJI-LT4 LT4 LJE LT4 LJZ LT4 LJI LY4 LJZ-LT4 LJI LJI-LJM ----
16 603 965 93Z 877 984 814 871 939 S15 S23 958 881 869 952 929 924 866 884 927 #99 872 902 987 586 '
LJI LT4 LJI LT4 LJM LY4 LJM LT4 LJN LT5 LJM LJM LTS LJM LY4 LJM LY5 LJM LT5 LJK LT4 LJE
- 14 - - - -972 959 964 952-472-965-478 975 544 953 454 461 925 512 995 534-928 457 958 986 875 904 - --
1 LJM LJK LT5 LJE LT4 LJZ LY4 LJZ LT4 LJZ LY4 LT4 LJZ LY4 LJZ LT4 LJZ LY4 LJI LY4 LJI LJM j 12 566 967 918 969 936 911 979 SZZ 879 948 871 911 954 917 925 928 814 868 894 922 982 515 LJB LJE LJM LT4 LJI LT5 LJM LT4 LJM LT4 LJM LJM LYS LJN LT4 LJM LT5 LJI LT5 LJM LJI LJB 18 296 934 583 967 878 S34 587 986 531 958 576 553 856 595,LJZ 858 538 948 951 855 518 898 375
. LJB LJI LJI LY4 LJI LT4 LJZ LY5 LJZ LY4 LT4 LJZ LY4 LT4 LJI LT4 LJE LJI LJB J sg 389 868 971 874 992 873 839 827 Sit 973 923 823 919 827 925 907 928 891 896 346 j LJB LJN LJI LJI LJE LT5 LJM LT5 LJI LJI LT4 LJM.LT5 LJI LJI LJI LJN LJB i 96 368 574 872 883 978 93Z 589 896 935 941 898 536 946 889 944 938 523 345 LJM LJI LJI LJI LJI LYS LY4 LJI LJI LJI LJI LJM S4 618 985 878 984 927 815 916 869 945 925 943 575 LJM LJM LJN LJM LJM LJM LJM LJN LJM LJM 82 605 684 561 544 513 528 521 507 568 588 1 3 5 7 9 11 13 15 17_ 19 21 23 25 27. 19 31 33 35 37 39 41 43 45 47 49 51
_ _ _ _ _ _ _