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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216J4111999-09-28028 September 1999 Proposed Tech Specs,Removing cycle-specific Min Critical Power Ratio Safety Limit Restriction ML20211G0501999-08-31031 August 1999 Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept ML20206R7931999-05-17017 May 1999 Revs Made to BSEP TS Bases Between 980605 & 990507,IAW TS 5.5.10.d ML20204D5241999-03-31031 March 1999 Rev 0 to Brunswick Steam Electric Plant,Unit 2 Simulator Certification Quadrennial Rept ML20204D4961999-03-31031 March 1999 Rev 0 to Brunswick Steam Electric Plant,Unit 1 Simulator Certification Rept ML20204G5991999-03-19019 March 1999 Proposed Tech Specs Re Balance of Plant/Emergency Bus AOT Extension ML20198K0411998-12-21021 December 1998 Rev 1 to Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20153D8791998-09-14014 September 1998 Proposed Tech Specs 3.8.1 & 3.8.7 Re Balance of Plant/ Emergency Bus Allowable Outage Time Extension ML20238F6671998-08-28028 August 1998 Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20237C0251998-08-17017 August 1998 Proposed Tech Specs 5.2.2.f Requiring Operations Manager or Assistant Operations Manager to Hold SRO License ML20237A5711998-07-16016 July 1998 Rev 10 to OENP-16.7, Administrative Control of Check Valve Disassembly Program ML20249B1161998-06-12012 June 1998 Proposed Tech Specs Page 3.3-56 for Issued Amends 203 & 233, Correcting Erroneous Inequality Sign for Allowable Value ML20249C0131998-06-11011 June 1998 Rev 0 to TR-ECCS-GEN-011, ECCS Suction Strainer Hydrodynamic Test Summary Rept ML20248A4681998-05-22022 May 1998 Proposed Tech Specs Pages to Rev E of Proposed License Amend for Conversion to Improved TS ML20247H9481998-05-15015 May 1998 Revised TS Pages for Administrative Rev to Proposed Surveillance Requirements 4.7.2.b.2 & 4.7.2.c,to State That Charcoal Absorber Samples Will Be Tested IAW Methodology Provided by ASTM D3803-1989 at 30 C ML20217J9171998-04-24024 April 1998 Proposed Rev D to Improved Ts,Incorporates New ITS 3.6.3.2, Containment Atmospheric Dilution Sys ML20217H3061998-04-16016 April 1998 Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports ML20216G7961998-04-0909 April 1998 Proposed Tech Specs,Revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements ML20217Q1041998-04-0303 April 1998 Proposed Tech Specs Pages to Modify TS 3.5.3.1 & Associated Bases Section 3/4.5.3.1,to Revise Specified Total Volume of Condensate Storage Tank from 150,000 Gallons to 228,200 Gallons ML20217F9101998-03-27027 March 1998 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20217D5451998-03-24024 March 1998 Proposed Tech Specs 3.0 & 4.0 Re Applicability & Surveillance Requirements ML20216J8571998-03-13013 March 1998 Proposed Rev C to Improved Ts,Incorporating NRC Comments on Improved TS Submittal Resulting from Internal Reviews ML20197A9371998-02-25025 February 1998 Rev 4 to 0AP-025, Bnp Integrated Scheduling ML20203H0481998-02-23023 February 1998 Proposed Tech Specs,Revising SLMCPR from 1.10 to 1.09 & Deleting Document Reference ML20203M4031998-02-18018 February 1998 Rev 0 to Pump & Valve IST Program Plan Third Interval for Cp&L,Units 1 & 2 ML20197A9281998-02-12012 February 1998 Rev 22 to 0A0P-13.0, Operation During Hurricane,Flood Conditions,Tornado or Earthquake ML20204A7551998-02-0202 February 1998 Rev 0 to ESR 97-00706, Benchmark of Dll Computer Program ML20199K7041998-01-27027 January 1998 Proposed Tech Specs 3/4.8 Re Electrical Power Sys ML20199A9291998-01-22022 January 1998 Core Shroud Insp Plan Unit 1 B112R1 Outage April 1998 ML20197B8741997-12-18018 December 1997 Proposed Tech Specs Pages Revising Proposed Amends in 971101 Request by Expanding Note in LCO 3.3.1.1,Table 3.3.1.1-1,to Allow 12 Hours to Adjust Allowable Value,Specified in COLR, After Sufficient Reduction in Feedwater Temperature ML20202D9151997-12-0202 December 1997 Rev 11 to 0AOP-34.0, Chlorine Emergencies ML20198T2961997-11-24024 November 1997 Rev 0 to B2C13, Brunswick Unit 2,Cycle 13 Neutronics Startup Rept ML20199J5711997-11-14014 November 1997 Rev 3 to 0AP-025, Bnp Integrated Scheduling ML20198T3131997-11-0707 November 1997 BSEP Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20198P7091997-11-0606 November 1997 Proposed Tech Specs 3/4.7.2 & 3/4.3.5.5 Revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation ML20199A3011997-11-0606 November 1997 Proposed Tech Specs,Adding Footnote to SR 4.8.1.1.2.d to Allow Performance of SR 4.8.1.1.2.d.1,SR 4.8.1.1.2.d.4 & SR 4.8.1.1.2.d.5 in Operational Condition 1 Through 5 ML20198Q3011997-11-0404 November 1997 Proposed Tech Specs 3.0 & 4.0,revising Specific Terms in Proposed TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology ML20198P2681997-10-29029 October 1997 Proposed Tech Specs,Revising Description of Control Rod Assemblies ML20212F1991997-10-28028 October 1997 Proposed Tech Specs Revising Proposed SRs to Remove Allowable Humidity & Temperature Testing Ranges for Charcoal Adsorber ML20212F2241997-10-28028 October 1997 Proposed Tech Specs Revising Certain Instrumentation Allowable Values ML20199J5601997-10-13013 October 1997 Rev 2 to 0AP-022, Bnp Outage Risk Mgt ML20198P4841997-10-0808 October 1997 Rev 1 to BSEP Unit 2 Core Shroud Insp Plan Outage B213R1 ML20249C0041997-09-30030 September 1997 Rev 2 to TR-ECCS-GEN-01-NP, Hydrodynamic Inertial Mass Testing of ECCS Suction Strainers ML20249C0091997-09-30030 September 1997 Rev 1 to TR-ECCS-GEN-05-NP, Hydrodynamic Inertial Mass Testing of ECCS Suction Strainers Suppl 1 - Free Vibration Data Analysis ML20217E2791997-09-17017 September 1997 Tensil Testing & Charpy Impact Testing of Reactor Archive Matl ML20217Q5131997-08-27027 August 1997 Proposed Tech Specs,Revising Labels for Coordinates of TS Figures 3.4.6.1-1,3.4.6.1-2,3.4.6.1-3a & 3.4.6.1-3b as Pressure (Psig) & Temp (F) Rather than Pressure Limit in Rv Top Head (Psig) ML20210P4651997-08-22022 August 1997 Proposed Tech Specs,Incorporating Power up-rate Amend 183 Provided as Replacement & Addressing Administrative Error W/Typed Bases Page Submitted w/970115 Amend Request ML20210P3601997-08-22022 August 1997 Proposed Tech Specs Bases Pages Incorporating 961101 Power up-rate Amendments ML20196J0701997-07-25025 July 1997 Proposed Tech Specs Clarifying Use of NRC Staff Approved Alternatives to Recommendations of NRC GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping ML20149J3641997-07-18018 July 1997 Proposed Tech Specs 5.2.2.b & 5.4.2 Re Containment & RCS Design Features 1999-09-28
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20198K0411998-12-21021 December 1998 Rev 1 to Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20238F6671998-08-28028 August 1998 Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20237A5711998-07-16016 July 1998 Rev 10 to OENP-16.7, Administrative Control of Check Valve Disassembly Program ML20217H3061998-04-16016 April 1998 Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports ML20197A9371998-02-25025 February 1998 Rev 4 to 0AP-025, Bnp Integrated Scheduling ML20203M4031998-02-18018 February 1998 Rev 0 to Pump & Valve IST Program Plan Third Interval for Cp&L,Units 1 & 2 ML20197A9281998-02-12012 February 1998 Rev 22 to 0A0P-13.0, Operation During Hurricane,Flood Conditions,Tornado or Earthquake ML20204A7551998-02-0202 February 1998 Rev 0 to ESR 97-00706, Benchmark of Dll Computer Program ML20199A9291998-01-22022 January 1998 Core Shroud Insp Plan Unit 1 B112R1 Outage April 1998 ML20202D9151997-12-0202 December 1997 Rev 11 to 0AOP-34.0, Chlorine Emergencies ML20199J5711997-11-14014 November 1997 Rev 3 to 0AP-025, Bnp Integrated Scheduling ML20199J5601997-10-13013 October 1997 Rev 2 to 0AP-022, Bnp Outage Risk Mgt ML20198P4841997-10-0808 October 1997 Rev 1 to BSEP Unit 2 Core Shroud Insp Plan Outage B213R1 ML20196J5681997-07-17017 July 1997 1 to 2ASSD-05 Plant Operating Manual,Alternative Safe Shutdown Procedure Unit 2, Reactor Bldg North ML20148L7611997-06-12012 June 1997 Core Shroud Insp Plan Unit 2 B213R1 Outage,Sept 1997 ML20202D9331997-04-23023 April 1997 Rev 1 to 0FPP-038, Operation of SCBA Refill Sys ML20202D9371997-03-18018 March 1997 Rev 2 to Fire Protection Procedure OFPP-039, SCBA Use & Maint ML20115C6901996-06-30030 June 1996 Core Shroud Reinspection Plan for Unit 1 B111R1 Outage Oct 1996 ML20094E0861995-11-0202 November 1995 Core Shroud Reinspection Plan Unit 2 B2121R1 Outage for Feb 1996 ML20078P6731995-02-0909 February 1995 Core Shroud Reinsp Plan Unit 1 B110R1 Outage,Apr 1995 ML20079B0811994-12-14014 December 1994 Three-Yr Business Plan Performance Improvement Initiatives & Projects ML20073K8991994-10-0303 October 1994 Rev 47C to Plant Emergency Procedure (Pep) 0PEP-APPENDIX a, Emergency Response Resources ML20071P1491994-08-0202 August 1994 Three-Yr Business Plan Performance Improvement Initiatives & Projects ML20029E2471994-05-0404 May 1994 Three Yr Business Plan Performance Improvement Initiatives & Projects. ML20072M8571994-03-29029 March 1994 Rev 0 to Plan Mod 94-0077, Unit 2 Core Shroud Mod ML20217D4911993-07-30030 July 1993 Rev 0 to B-SP-93-06 Assessment Plan Outline, Program or Area:BNP-1 Startup & Power Ascension Readiness Assessment ML20045E0971993-05-16016 May 1993 Mod 91-038 to Field Rev 3 to Steam Leak Detection Sys Upgrade for Hpci,Rcic,Rwcu & RHR Procedure ML20044G6131993-05-11011 May 1993 Rev 5 to Design Guide DG-II.20, Design Guide for Civil/Structural Operability Reviews. ML20044C6191993-03-0101 March 1993 Rev 4 to Design Guide DG-II.20, Civil/Structural Operability Reviews. ML20116D2961992-08-31031 August 1992 Rev 2 to Nuclear Generation Group Manual 305-05, Prioritization Process ML20044G6141992-07-31031 July 1992 Rev 0 to 92C1737A, Recommended Operability Review Criteria for Piping Sys Subj to Level D Svc Loadings for Carolina Power & Light Nuclear Stations. ML20099G3101992-07-17017 July 1992 Rev 1 to Procedure WDP-002, Phase II Walkdown Procedure for Reactor Building Miscellaneous Steel & Drywell Platform Steel PM-91-038, Rev 0 to PM 91-038, Steam Leak Detection Sys Upgrade for Hpci,Rcic,Rwcu & Rhr1992-05-21021 May 1992 Rev 0 to PM 91-038, Steam Leak Detection Sys Upgrade for Hpci,Rcic,Rwcu & Rhr ML20056D6011991-11-19019 November 1991 Rev 2 to Performance Test Procedure 2-PT-24.6.4, SWS Hydraulic Performance Test for Bsep,Unit 2 ML20082H7521991-08-21021 August 1991 Rev 11 to ODCM ML20082H7501991-08-21021 August 1991 Rev 3 to Process Control Program ML20083A6541991-08-19019 August 1991 Rev 1 to Design Guide DG-VIII.50, Instrument Setpoints ML20056D6001991-01-25025 January 1991 Rev 1 to Performance Test Procedure 1-PT-24.6.4, SWS Hydraulic Performance Test for Bsep,Unit 1 ML20062C3931990-10-15015 October 1990 Rev 28 to Plant Emergency Procedure PEP-02.1, Initial Emergency Actions ML20062C3991990-10-11011 October 1990 Rev 5 to Plant Emergency Procedure PEP-02.6.10, Emergency Security Team Leader ML20081E7391990-04-20020 April 1990 Rev 6 to 25-2F, Operator Training Student Study Matl. Related Matl Encl ML20205S7011988-04-22022 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-LEP-02, Alternate Control Rod Insertion:LEP-02 ML20205K9071988-04-13013 April 1988 Rev 0 to Alternative Safe Shutdown Procedure ASSD-00, User Guide ML20205S7661988-04-0808 April 1988 Rev 5 to Emergency Operating Procedure EOP-01-UG, Users Guide ML20205S6891988-04-0808 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-EPP-2B, End Path Procedure 2B ML20205S6981988-04-0808 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-LEP-01, Alternate Coolant Injection ML20205S7091988-04-0808 April 1988 Rev 3 to Emergency Operating Procedure EOP-01-LEP-03, Alternate Boron Injection ML20205S7721988-04-0808 April 1988 Rev 6 to Emergency Operating Procedure EOP-01-ACCP, ATWS - Containment Control Procedure ML20205S7441988-04-0808 April 1988 Rev 3 to Emergency Operating Procedure EOP-01-SRP-NSW, Nuclear Svc Water Sys Recovery ML20205S7991988-04-0808 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-EPP-1M, End Path Procedure 1M 1998-08-28
[Table view] |
Text
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Core Shroud Reinspection Plan Unit 1 B110R1 Outage April,1995 ,
Prepared hv:
Vaughn Wagoner John Langdon Blane Wilton Itecommended by: ( dhi i bt Date: J/S,/9[
Approved by: i J. M Date:%/f/95' l
PR P
bC 0 000 56 PDR
l i
. i Core Shroud Reinspection Plan ,
Unit i B110R1 Outage i April,1995 l
EXECUTIVE
SUMMARY
The scope of reinspection fbr the Unit 1 Core Shroud is based on the results of previous inspections performed on both Unit 1 and Unit 2, ibliowup actions and commitments established from the last inspection in Engineering Evaluation 93-0536, and guidance on i shroud inspections contained in NRC Generic Letter 94-03. I The inspections perfbrmed in Unit I during the Summer and Fall of 1993 meet the current 'I requirements of NRC Generic Letter 94-03 for core shroud inspections, and meet the J requirement ofinspecting essentially 100% of accessible areas of the shroud circumferential !
welds. In addition, vertical welds and several attachment welds, and other parts of the core ,
support structure were examined during these inspections. Specific areas on several !
circumferential welds were marked, so that they could be re-examined to determine the ,
extent of crack growth during the last cycle. !
1 The reinspection scope is structured to meet the intent of NRC Generic Letter 94-03, and l fbcuses on three objectives: re-examination of selected areas to determine crack growth, ;
examination of some of the installed clamps to verify no inservice degradation, and utilization of specifically developed tooling to examine accessible portions of certain welds i that could nu be accessed before. Specifically, UT measurements will be repeated at j selected areas on 111 and 115. and VT measurements will be repeated on H5. Two of the !
12 clamps will be examined for degradation. CP&L is also developing UT techniques to i inspect the ID surface of the core support ring welds H6a and H6b and associated fillet !
welds. The automated UT scanner commonly being used for shroud inspections will not l work on the Brunswick shrouds, because ofinterference with the clamps. Specialized l tooling is under development to perform these inspections. .
Ultrasonic inspections will be conducted using " phased array" technology. This technology I allows electronic manipulation of the ultrasonic sound beam without hardware changes. It i has been successfully used Ihr a number of years both domestically and abroad. The equipment and procedures Ihr UT. as well as Ihr VT, will be qualified in accordance with ;
the guidelines of the BWRVIP. l l
An engineering evaluation of the results of the inspection will be performed, using the flaw .
evaluation guidance contained in the " Core Shroud Inspection and Evaluation Guidelines," j issued by the BWRVIP. CP&L is developing a contingency shroud repair plan.
CP&L is working closely with the BWRVIP to evaluate industry information and incorporate " lessons learned" into the overall inspection program. Inspection of areas Page 1 l
below the core support plate and other vessel attachments and internals will be perfbrmed consistent with the guidance provided by the BWRVIP.
UNIT 1 CORE SIIROUD REINSPECTION PLAN The scope of this reinspection plan meets the intent of requested licensee action item 3 of Generic 1.etter 94-03, fbr a reinspection of the shroud. This action item requires an inspection plan for all shroud welds or justification for not inspecting certain welds, and requires use of technology and industry experience to perfbrm inspections that will consistently detect IGSCC.
The reinspection plan fbr the core shroud fbcuses on reinspecting specific areas inspected last outage to determine crack growth rates, and to examine the inside areas of core support ring welds ll6a and ll6b. Visual inspections of the OD were conducted on these welds, since tooling did not exist at the time to examine the inside areas. The tooling commonly being used in industry, the General Electric Company "OD tracker," will not work on the BNP shroud due to interference from the installed clamps. Specialized tooling is being developed to inspect these welds.
Weld lil will be re-examined in 4 places ultrasonically, at the 30",140", 259", and 330" azimuths. This is a ring weld, with the "end grain" exposure and significant cold work. It was evaluated fbr one cycle, and must be reevaluated this outage. Other locations that were previously ultrasonically examined may be substituted, if required. Welds 112 and 113 will not be inspected because they have been structurally replaced by the clamps. Weld 114 will not be reinspected since only relatively minor axial cracking was seen at this weld, and areas on a similar weld (115) will be examined to determine crack growth. Two circumferential indications on weld 115 at 169" and 264" will be re-examined both visually and ultrasonically. This plate-to-plate weld area experiences harsher environment and more fluence than other welds. The data from this weld examination will be used to benchmark the GE PLEDGE Crack Growth Model for the Brunswick Plant and allow accurate prediction of crack growth rates. l Specialized tooling will be used to examine accessible portions of welds ll6a and il6b.
Access is limited to 6 areas between jet pump pairs fbr each of these welds. No further inspections of Weld 117, Weld 118, and areas below the core plate will be performed this outage because equipment and techniques are still being developed fbr these inspections. j Future inspection plans for these areas will be developed consistent with guidance provided by the llWRVIP. Portions of the OD of117 and 118 were examined last outage using enhanced VT, and no indications were found. j 1
The BWRVIP is currently developing guidance ihr qualification of the 119 shroud weld examinations. The 119 weld is located directly behind one of the vessel beltline welds that 1 will be examined this outage. Interrogation of the 119 weld will occur during the vessel beltline weld examination; however, since the BWRVIP has not completed development of Page 2
qualification criteria for the 119 weld inspection technique, the results of the H9 weld examinations can not be appropriately evaluated. CP&L will address the status of the core shroud 119 weld examination / evaluation in the post-outage inspection results submittal.
Two of the 12 repair clamps will be visually inspected to ensure no degradation during the last cycle of operation.
Details of the scope of inspection for each weld, and for the clamps, are summarized in Table 1.
INSPECTION SCOPE EXPANSION llased on the results of the Brunswick Plant Unit 1 Core Shroud Reinspection Plan, additional inspections of the core shroud (including repair clamps) may be necessary to support an engineering evaluation to demonstrate core shroud integrity. CP&L will address any scope expansion in our submittal of the inspection results to the NRC staff.
EVALUATION OF INSPECTION RESULTS An engineering evaluation will be perfbrmed on the inspection results, using the flaw evaluation guidance of the BWRVIP " Core Shroud Inspection and Evaluation Guidelines."
No significant changes from the last inspection results are expected. No repairs are anticipated ihr this outage. CP&L will submit the inspection results in accordance with the guidance of NRC Generic Letter 94-03.
l I
Page 3 )
I l
l 1
TAllLE 1 Unit 1 Outage - Core Shroud Reinspection Scope WELD PREVIOUS INSPECTION REINSPECTION COhlh1ENTS RESULTS h1ETilOD*
Ill VT of 100% of ID & OD. UT UT from OD 4 of 8 areas previously UT'ed.
App. 74% of OD cracked.
UT at 8 locations, <0.3" to 0.7" 112 VT of 100% of OD. App. N/A Replaced by clamps. See clamp inspection below.
62% cracked in ring. UT at 4 locations, <0.3" to 0.75" 113 VT of 100% of ID & OD. N/A Same as 112.
Near continuous cracking on ID in ring. UT at 11 locations. 0.95" to 1.71" II4 VT of 100% of ID & 45% of Nonc planned No circumferential indications identified last time, so sufficient OD (100% of accessible OD). structural margins exist. Any anticipated growth of axial Several small axial cracks. indications would not impact structural margins. 115 is a similar No circumferential cracks. weld, and is being inspected.
115 VT of 100% of ID & 45% of Partial VT plus UT VT of " punch marked" cracks for length on the ID. UT of 2 OD (100% of accessible OD). previous areas to determine crack growth.
Circumferential cracks passed screening criteria. UT at 2 locations, with depths <0.3" to 0.6" Page 4
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