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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20077P9291991-08-15015 August 1991 Final Rept, Verification of Fort St Vrain Activation Analysis ML20072V5031991-04-12012 April 1991 Summary of Existing & Planned Work for Activation Verification,910415 ML20029B6731991-03-0505 March 1991 Nonproprietary Estimated Blast Effect from Ft St Vrain Well 11 Analysis Methods Summary. ML20059L5921990-09-13013 September 1990 Determination of Upper Bounds on Radiation Exposure Rates at Refueling Floor Above Defueled Region W/Crd Orifice Assemblies Radiation Shielding Removed ML20042F9071990-05-0101 May 1990 Conceptual Plan & Cost Estimate for Early Dismantlement of Fort St Vrain Pcrv. ML19332E8181989-12-0101 December 1989 Rev a to Fort St Vrain Site-Specific Decommissioning Cost Estimate Basis for Preliminary Decommissioning Plan. ML19332C2831989-10-0909 October 1989 Fort St Vrain 3-D Neutron Source Analysis Using DIF3D. ML19332E8191989-08-31031 August 1989 Rev a to Fort St Vrain Activation Analysis. ML20245L4061989-08-31031 August 1989 Safety Analysis Rept for Reactor Defueling ML20246K1321989-07-31031 July 1989 Pcrv Tendon Surveillance Rept for Jul 1989.W/four Oversize Drawings ML20245J3261989-06-14014 June 1989 Rev B to Evaluation of Cable/Equipment Separation for Bearing Water Pumps P-2101-S,P-2102 (Train B),P-2102-S (Train B) & P-2107 (Train B) for App R Requirements ML20245C4581989-05-11011 May 1989 CRD Partial Scram Test Results & Max Daily Temp Rept, 890511-0531 ML19332E8211989-02-23023 February 1989 Fort St Vrain Plateout Analysis for Decommissioning Study. ML20206K1111988-11-21021 November 1988 Rev a to Engineering Evaluation of Interaction & Effects of Plant Protection Sys & Steam Line Rupture Detection/ Isolation Sys ML20154E0981988-08-31031 August 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20077B9091988-05-31031 May 1988 Vols I & II of Activation Analysis ML20154A5451988-04-28028 April 1988 Integrated Sys Study of CRD Mechanism Rod Position Instrumentation ML20154A5501988-04-28028 April 1988 Temp Prediction for CRD Mechanism Motors ML20235A5591988-01-31031 January 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20148G7941988-01-22022 January 1988 Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities ML20148G8511988-01-22022 January 1988 Helium Circulator Insp Schedule ML20195H8731988-01-14014 January 1988 Final Rept on Fort St Vrain 871002-03 Fire ML20236J2911987-10-30030 October 1987 Preliminary Rept on Impact of Fort St Vrain 871002 Fire ML20235H4731987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification for Returning to Power Operation ML20235K2721987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage Including Licensing Assessment ML20195G9681987-08-11011 August 1987 Analyses Re Fort St Vrain DBA-2 Core Damage Frequency ML20235W6091987-07-31031 July 1987 Pcrv Tendon Interim Surveillance Rept ML20234C1091987-06-25025 June 1987 Issue B to Effect of Firewater Cooldown Using EES Bundle on Steam Generator Structural Integrity ML20214Q9981987-05-31031 May 1987 Verification Rept for Buckle Computer Program ML20215J8711987-05-0404 May 1987 Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling ML20214P3381987-04-30030 April 1987 Rev 3 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 4, Exemptions & Mods ML20214P3141987-04-30030 April 1987 Rev 5 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 2, Electrical Reviews ML20214P3061987-04-30030 April 1987 Rev 7 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 1, Shutdown Model 1997-04-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
[Table view] |
Text
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l CONTROL. ROD-DRIVE PARTIAL SCRAM .1 TEST RESULTS AND MAXIMUM DAILY l
' TEMPERATURE REPORT:
i REPORT PERIOD:
'May 11, 1989 - May 31, 1989 l 1
1 l
~\
Prepared by: M M /,,, M k l
- l. Rob Ga#Ta 7 7 System Engineer i
Systems Engineering '
1.
Approved by: /4 i
Steve JoneV' Preventive Maintenance Supervisor Systems Engineering Public Service Company of Colorado Fort St. Vrain Unit No. 1 8906260193 890615 4 l' PDR ADOCK 05000267 R PDR ,
.. . -- _ .b
, Page 1 I. ABSTRACT This report summarizes the partial scram test results'and the
-maximum daily temperature of those control rods with motor temperatures above 215 degrees Fahrenheit. It is prepared to satisfy the Fort St. Vrain Interim Technical Specifict. tion Surveillance Requirement 4.1.1.A.I.a. ..The time period covered
.by this report is May 11, 1989, through May 31, 1989.
II. BACKGROUND Because proper operation of the Control. Rod Drive Mechanism-(CRDM). is critical for safe operation of the reactor; a series of qualification tests were conducted over a one year time span to demonstrate its capabili ty. The motor: temperature.
during 'these tests varied between 200 degrees Fahrenheit and 230 degrees Fahrenheit, and averag?d 215 degrees Fahrenheit.
A total of 130,000. jog cycles plus 1600 scrams was logged during the final design testing, which is many times- that expected 'over the normal life of a CRDM. The operating.
temperature of the CRDM is limited by the motor's Class H insulation which is de-rated to 272 degrees Fahrenheit to account for motor temperature rise, frictional torque increase, and winding life expectancy.
In order to monitor CRDM temperatures, Resistance Temperature Devices (RTD's) are mounted on the closure plate, orifice valve motor plate, and CRDM motor as shown on Figure 1. A11~
CRDM's installed in the Reactor are equipped with RTD's'.
Three recorders located in the control room record each of these temperatures for all 37 CRDM's. CRDM motor temperatures are alarmed at 212 degrees Fahrenheit and 247 degrees Fahrenheit.
CRDM motor temperatures are monitored at least once per 24' hours to verify that they are less than 250 degrees Fahrenheit, which is'a limiting condition for operation. If one or more CRDM motor temperature (s) is found to be greater than 215 degrees Fahrenheit during the daily surveillance, the motor temperature' of all CRDMs , exceeding 215 degrees Fahrenheit is recorded and a partial scram test is performed-on the CRDM wich the highest motor temperature once p1r 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. These surveillance ensure that' CRDM ' motor temper'itures exceeding 215 degrees Fahrenheit do not degrade the CRDM's reliability to perform its design function when required.
III.
SUMMARY
OF RESULTS l'
The previous months report identified Region 7 as.having a motor temperature in excess of 215 degrees Fahrenheit. The CRDM in Region 7 was replaced May 2, 1989, with a spare CRDM and has not exceeded 215 degrees Fahrenheit.
l
' * ^
, ., Page 2 During. the month . .of May,' Region L12 and Region 30 CRDM motor '!
temperatures . exceeded 215 . degrees Fahrenheit. .. The i temperatures were in excess of 215 degrees Fahrenheit for the.
period of May 11, 1989, through Mayu.31, 1989. On May '18,. l; 1989, . Region 30 CRDM exceeded .250 , degrees Fahrenheit. J Repositioning the: orifice valve brought the temperature below ,1 250 degrees Fahrenheit within 2' hours.
1 The partial . scram test results and' maximum daily temperature !
of those CRDMs with' motor -temperatures above 215 degrees-- l Fahrenheit are presented on' Table 1. 'The pertinent' parameters i are: reactor region l involved,' control rod position, maximum. .
l daily ' motor'. temperature, . extrapolated. scram times (actual ,1 value,and projected'value) and starting - acceleration.- .The '
control . rod position is presented because of its. relationship l to available starting torque which .affects -the starting- ;
acceleration and extrapolated . scram time. The extrapolated. ;
scram time is affected by control rod position because it is j calculated. using distance travelled versus time. Since the l
' j acceleration is slower at' lower control . rod positions, a j longer period of time is' required to reach steady state speed. j This longer acceleration period results in a decrease in- i distance travelled over a given period of time,'thereby.
indicating a longer extrapolated scram time. The extrapolated scram time calculated by the Back EMF program applies a correction fcctor to provide a projected full . length scram time. .i
~
The starting acceleration values presented are calculated by-the Back EMF program. These values reflect the CRDM's freedom of. rotation to accelerate to steady state speed and therefore 'j are considered to be valuable performance indicators. Two values'are presented: The actual acceleration measured during a scram from the indicated control-' rod position and ..the projected acceleration if the control rods were at the full.
out position (greater than 188 inches). If .the control . rod
~
position is greater than 188 inches, no data is presented for _ ,
a projected starting acceleration . since the actual and projected are the same. 'As indicated with scram times, the .i projected starting acceleration is more readily trended since ;
the value should be indepe'ndent of' control rod position.
i IV. CONCLUSIONS The performance of CRDMs with motor temperatures in excess of 215 degrees Fahrenheit did not show any significant trends. or '
degradation d>: ring this report period. Therefore, it.is 1 concluded that CRDM motor temperatures exceeding 215 ' degrees !
Fahrenheit did not degrade the~CRDM's capability to perform !
its design function when required.
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