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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F1041999-10-14014 October 1999 Proposed Tech Specs Pages,Revising TS Sections 2.2 & 3.0/4.0,necessary to Support Mod P000224 Which Will Install New Power Range Neutron Monitoring Sys & Incorporate long- Term thermal-hydraulic Stability Solution Hardware ML20212H5681999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS to Clarify Several Administrative Requirements,Delete Redundant Requirements & Correct Typos ML20216J3471999-09-27027 September 1999 Corrected Tech Specs Page,Modifying Appearance of TS Page 3/4 4-8 as Typo Identified in Section 3.4.3.1 ML20196F5551999-06-22022 June 1999 Proposed Tech Specs Pages to Delete Surveillance Requirement 4.4.1.1.2 & Associated TS Administrative Controls Section 6.9.1.9.h,removing Recirculation Sys MG Set Stop ML20195H0651999-06-0909 June 1999 Revised Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS Units 1 & 2,in Order to Clarify That Requirements for Reactor Enclosure Secondary Containment Apply to Extended Area Encompassing Both Reactor Enclosure & Refueling Area ML20195E7611999-06-0707 June 1999 Proposed Tech Specs Table 3.6.3-1 & Associated Notations, Reflecting Permanently Deactivated Instrument Reference Leg Isolation Valve HV-61-102 ML20195G0481999-06-0707 June 1999 Proposed Tech Specs Section 3/4.4.3, RCS Leakage,Leakage Detection Systems, Clarifying Action Statement Re Inoperative Reactor Coolant Leakage Detection Systems ML20195B8431999-05-26026 May 1999 Proposed Tech Specs Section 4.1.3.5.b,removing & Relocating Control Rod Scram Accumulators Alarm Instrumentation to UFSAR & TS Section 3.1.3.5,allowing Alternate Method for Determining Whether Control Rod Drive Pump Is Operating ML20207L6591999-03-11011 March 1999 Proposed Tech Specs Section 2.1, Safety Limits, Revising MCPR Safety Limit ML20199G2021999-01-12012 January 1999 Proposed Tech Specs Section 3/4.4.2 & TS Bases Sections B 3/4.4.2,B 3/4.5.1 & B 3/4.5.2 to Increase Allowable as-found Main Steam SRV Code Safety Function Lift Setpoint Tolerance from +1% to +3% ML20199A7271999-01-0404 January 1999 Proposed Tech Specs Revising Administrative Section of TS Re Controlled Access to High Radiation Areas & Rept Dates for Annual Ore Rept & Annual Rer Rept ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20155H6401998-10-30030 October 1998 Proposed Tech Specs Pages Revising TS SRs 4.8.4.3.b.1, 4.8.4.3.b.2 & 4.8.4.3.b.3 in Order to Reflect Relay Setpoint Calculation Methodology ML20154Q8941998-10-15015 October 1998 Proposed Tech Specs Re Addition of Special Test Exception for IST & Hydrostatic Testing ML20154L3971998-10-13013 October 1998 Revised Tech Spec Bases Pages,Clarifying Thermal Overload Operation for Motor Operated Valves with Maintained Contact Control Switches ML20151Z4721998-09-14014 September 1998 Proposed Tech Specs Revising Table 4.4.6.1.3-1,re Withdrawal Schedule for Reactor Pressure Vessel Matl Surveillance Program Capsules ML20151V0951998-09-0404 September 1998 Proposed Tech Specs Ensuring Fidelity Between TS Pages & 970324 Submittal ML20236M1221998-07-0202 July 1998 Proposed Tech Specs Change Request 96-06-0,modifying FOL Page 8 ML20217K5291998-04-24024 April 1998 Proposed Tech Specs Page 6-18a Revising MCPR Safety Limit for Lgs,Unit 1,cycle 8 ML20202G7871998-02-0909 February 1998 Proposed TS Section 2.1, Safety Limits, Revising MCPR Safety Limit.Nonproprietary Supporting Info Encl ML20199G7771998-01-27027 January 1998 Proposed Tech Specs Pages,Removing Maximum Isolation Time for HPCI Turbine Exhaust Containment Isolation Valve HV-055-1(2)F072 from TS ML20198M7861998-01-12012 January 1998 Proposed Tech Specs Table 4.4.6.1.3-1 Re Surveillance Specimen Program Evaluation for Limerick Generating Station, Unit 1 ML20203H2501997-12-31031 December 1997 Rev 19 to Odcm ML20198N8061997-12-31031 December 1997 NPDES Permit PA-0052221 Study Plan for Fecal Coliform Bacteria in Pont Pleasant Water Diversion Sys During May- Sept 1998 ML20199H5971997-11-18018 November 1997 Proposed Tech Specs Re Affected Unit 1 FOL Page 8 ML20212D1851997-10-24024 October 1997 Proposed Tech Specs Revising Section 3/4.1.3.6 to Exempt Control Rod 50-27 from Coupling Test for Remainder for Cycle 7 at LGS Unit 1,provided Certain Conditions Are Met ML20211P9471997-10-15015 October 1997 Revised MSRV Tailpipe Temp Action Plan ML20216H1101997-09-0808 September 1997 Proposed Tech Specs,Supplementing Change Request 96-06-0 by Adding Three Addl TS Pages Containing Typos Discovered Since 970225 Submittal ML20210T9231997-09-0202 September 1997 Proposed Tech Specs,Revising TS Section 4.0.5 & Bases Sections B 4.0.5 & B 3/4.4.8 Re SRs Associated W/Isi & IST of ASME Code Class 1,2 & 3 Components ML20141K9461997-05-27027 May 1997 PECO Nuclear Limerick Generating Station Unit 2 Startup Test Rept Cycle 5 ML20203H2701997-04-30030 April 1997 Rev 18 to Odcm ML20138A2311997-04-21021 April 1997 Proposed Tech Specs,Providing New Pp B 3/4 8-2a to Accomodate Overflow of Text from TS Bases Pp B 3/4 8-2 ML20137X8101997-04-0909 April 1997 Proposed Tech Specs Re Battery Specific Gravity Changes ML20137G6751997-03-24024 March 1997 Proposed Tech Specs Deleting Drywell & Suppression Chamber Purge Sys Operational Time Limit & Add SR to Ensure Purge Sys Large Supply & Exhaust Valves Are Closed as Required ML20135D0961997-02-25025 February 1997 Proposed Tech Specs Changing Corporate Name from PA Electric Co to PECO Energy Co & Removing Obsolete Info & Correcting Typos ML20133L2141997-01-15015 January 1997 Proposed Tech Specs Pp 3/4 5-5 mark-up Rev for Unit 1 Revising TS by Eliminating in-situ Functional Testing of ADS Valves Requirement as Part of start-up Testing Activities ML20135F0961996-12-0606 December 1996 Proposed Tech Specs 2.1 Re Safety Limits ML20135A4491996-11-25025 November 1996 Proposed Tech Specs Change Request 96-22-0,revising TS SR 4.8.1.1.2.e.2 & Supporting TS Bases Section 3/4.8,to Clarify Requirements Associated W/Single Load Rejection Testing of EDGs ML20134L7571996-11-0505 November 1996 Proposed Tech Specs Revising Same Pp Contained in TS Change Request 95-14-0 Re Adoption of Performance Based 10CFR50, App J,Option B Testing ML20128N7761996-09-27027 September 1996 Proposed Tech Specs 3/4.6.5 Re Secondary Containment & 4.6.5.1.1 Re Surveillance Requirements ML20116L2701996-08-0808 August 1996 Proposed Tech Specs,Revising TS Sections 3/4.3.1,3/4.3.2, 3/4.3.3 & Associated TS Bases Sections 3/4.3.1 & 3/4.3.2 to Eliminate Selected Response Time Testing Requirements ML20116H6511996-08-0505 August 1996 Proposed Tech Specs Section 2.1, Safety Limits, to Revise Min Critical Power Ratio Safety Limit ML20116E6191996-08-0101 August 1996 Proposed Tech Specs 3/4.4.6 Re Addition of Two Hydroset Curves,Effective for 6.5 & 8.5 Efpy,To Existing Ptol Curves ML20113E0491996-06-28028 June 1996 Technical Basis & Description of Approach for Review Method Selection ML20115A9111996-06-28028 June 1996 Proposed Tech Specs,Performing Containment leakage-rate Testing Per 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B ML20117H2621996-05-20020 May 1996 Proposed Tech Specs Sections 3/4.4.9.2,3/4.9.11.1,3/4.9.11.2 & Associated TS Bases 3/4.4.9 & 3/4.9.11 to More Clearly Described RHR Sys Shutdown Cooling Mode Operation ML20112C1691996-05-17017 May 1996 Startup Rept Cycle 7 ML20117D7801996-05-0303 May 1996 Proposed Tech Specs,Revising TS SRs to Change Surveillance Test Frequency for Performing Flow Testing of SGTS & RERS from Monthly to Quarterly ML20107M5141996-04-25025 April 1996 Proposed Tech Specs 3/4.3.7.7 Re Relocation of Traversing in-core Probe LCO ML20101L9211996-03-29029 March 1996 Proposed Tech Specs,Revising TS SR 4.5.1.d.2.b to Delete Requirement to Perform Functional Testing of ADS Valves as Part of start-up Testing Activities 1999-09-27
[Table view] Category:TEST REPORT
MONTHYEARML20141K9461997-05-27027 May 1997 PECO Nuclear Limerick Generating Station Unit 2 Startup Test Rept Cycle 5 ML20112C1691996-05-17017 May 1996 Startup Rept Cycle 7 ML20083P1361995-05-18018 May 1995 PECO Energy Co Limerick Generating Station Unit 2 Startup Rept Cycle 4 ML20044H1921993-04-26026 April 1993 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20115A5461992-09-30030 September 1992 Rev 0 to Limerick Generating Station,Unit 1 Startup Rept, Cycle 5 ML20082M9491991-08-0101 August 1991 Startup Rept,Cycle 2 ML20066G5251990-11-30030 November 1990 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20246A9001989-06-30030 June 1989 Startup Rept,Cycle 3 ML20236V6241987-11-30030 November 1987 Rev 0 to Limerick Generating Station Unit 1 Startup Rept Cycle 2 ML20236S0981987-08-13013 August 1987 Reactor Containment Bldg Integrated Leakage Rate Test Final Rept ML20155A3431986-03-31031 March 1986 Rev 2 to Rept of Initial Plant Startup ML20198H8201985-12-31031 December 1985 Rev 1 to Rept of Initial Plant Startup ML20132H0021985-09-30030 September 1985 Rept of Initial Plant Startup,Dec 1984 ML20093H8291984-09-25025 September 1984 Rev 0 to Scram Discharge Vol Contaminated Piping Insp ML20093H7591984-09-15015 September 1984 Rev 0 to RHR Loop D Contaminated Piping Insp ML20093H7381984-09-15015 September 1984 Rev 0 to RHR Loop C Contaminated Piping Insp ML20093H7101984-09-15015 September 1984 Rev 0 to RHR Loop B Contaminated Piping Insp ML20093H6981984-09-15015 September 1984 Rev 0 to RHR Loop a Contaminated Piping Insp ML20093H8041984-09-0909 September 1984 Rev 0 to Core Spray Loop B Contaminated Piping Insp ML20093H8161984-09-0909 September 1984 Rev 0 to Safeguard Piping Fill Sys Contaminated Piping Insp ML20093H7851984-09-0909 September 1984 Rev 0 to Core Spray Loop a Contaminated Piping Insp ML20100G0571984-08-31031 August 1984 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20095A5961984-05-15015 May 1984 Test Rept on Electrical Separation Verification Testing on Terminal Blocks & Panel Meters for Limerick Generating Station Units 1 & 2 ML20090K6441984-04-20020 April 1984 Test Rept on Electrical Raceway Separation Verification Testing for Philadelphia Electric Co,Limerick Generating Station Units 1 & 2 ML20086P0641983-12-0101 December 1983 Section 5.0, Startup Addenda, to Monthly Project Status Rept ML20077N0711983-09-0101 September 1983 Nuclear Qualification Test Rept ML20077N0811983-09-0101 September 1983 Summary of Generic Qualification of Solenoid Valves ML20077N0511983-06-27027 June 1983 Static Load Test Program on 18-Inch Butterfly Valve Assembly W/Limitorque Operator ML20028B4241982-09-0101 September 1982 Design Verification Test Rept,Internal Panel Control Wiring Separation Criteria. ML20077N0961982-06-24024 June 1982 Hydrodynamic Vibration Testing (New Loads) ML20077N0901980-08-28028 August 1980 Rev 1 to Qualification of EA180 Series Limit Switches for Use in Nuclear Power Plants in Compliance W/Ieee Stds 323-1974,382-1972 & 344-1975 1997-05-27
[Table view] |
Text
'i ST-1-052-702-1, Rnv. 0 1 -'. 3843070090 Paga 1 of 9 E s c], f y,' ,
E PHILADELPHIA ELECTRIC COMPANY LIMERICK. GENERATING STATION -
SURVEILLANCE TEST
@T-1-052-702 "B" CORE SPRAY LOOP CONTAMINATED PIPING INSPECTION 9 Cot Freq.: 18 Months -OR- Initiating Events: 1. Reason Tabl be Sch.-Spec.:6.8.4.a i FSAR 6.2.8.1.b 2. MRF No.
! FSAR 6.2.8.3
@ESTL RESULTS:
A. All Asterisked (*) Steps Completed SATISFACTORILY.
Performed'By: (Sign /Date). A 9f(ffd -
Performed By: (Sign /Date)
Informed Test Complete:(ACO or CO) (Sign /Date) 8.t), ho[ / -
1-9-8A (Time) te4*o Reviewed By:(SSVN or STA) (Sign /Date) P! 7dMf' D. One or More Asterisked (*) Steps Test Results UNSATISFACTORY.
Performed By: (Sign /Date)
Informed of Test Results: (CO or ACO)(Sign /Date)
(Time) J Shift Supervision: (Sign /Date)
Corrective Action: MRF No.:
i Initiated By: (Sign /Date)
IMMEDIATELY NOTIFY SENIOR PLANT STAFF MEMBER Person Notified: (Name)
Date/ Time Notified: (Date/ Time)
Notified By: (Sign)
ADDITIONAL' ACTION / TEST COMMENTS: ,
If any entry is made in Additional Action / Test Comments Section, person making initial entry sign here ,
(Sign /Date) j f h
//
e410160388 R41012 PDR ADOCK 05000352 A PDR
3843070090 ST-1-052-702-1, R2v. 0
, Paga 2 of 9 KSK/RSE:cjf 1.0 PURPOSE To inspect and measure any leakage from Core Spray System components that are directly associated with system piping that could carry contaminated water during a serious accident or transient. This procedure will be implemented while the system is at operating pressure with the pump (s) running.
2.0 REFERENCES
2.1 8031-M-52, Core Spray 2.2 NUREG 0737 i
3.0 TEST EQUIPMENT 3.1 Graduated Cylinder (s) 3.2 One-liter bottle (s) 3.3 Funnels 3.4 Stopwatch 3.5 Inspection mirror with handle 4.0 PRECAUTIONS & LIMITATIONS 4.1 If a procedural step cannot be completed, make a comment in the Additional Action / Test Comments section of the Data Sheet. I 4.2 Signoff steps marked "SO" in the left-hand margin of the body of the procedure require a signoff on the Data Sheet or Procedure Cover Sheet.
4.3 Leak Rates of greater than 5 drops per min. (.25 cc/ min) shall be quantified. Put "< .25 cc/ min" on the Data Sheet, Attachment A, in the space provide'd for components with leak rates less than or equal to 5 drops per min..
- ' '3843070090 sT-1-oS2-702-1, R2v. o Paga 3 of 9 KSK/RSE:cjf 4.4 Data' Sheet steps marked (*) are specific Tech. Spec.
requirements which will fail the test if not completed satsifactorily.
- 4.5 If any component is found to be exhibiting excessive-leakage notify EGVN immediately.
5.0 PREREQUISITES 5.1- Request RWP & HP assistance when required.
5.2 Inspector is familiar with the system layout and location.
5.3 Copy of the last test's Data Sheet is available for comparison.
5.4 Care Spray Loop must' be running for Surveillance Test ST-6-052-232-1 or per operating procedure SS2.9.A for the inspection.
5.5 Coordinate with operator running the system to allow pump run durations to be extended for the inspection.
6.o PROCEDURE IT IS THE RESPONSIBILITY OF THE PERSON OR PERSONS PERFORMING
- THIS TEST TO ENSURE ALL BLANKS AND DATA SHEETS ARE CORRECTLY AND COMPLETELY FILLED IN.
6.1 Preparation SO 6.1.1 Verify all prerequisites are satisfied.
6.1.2 Record appropriate information for each piece
- i. of measurement and test equipment used with a PECo number on the Data Sheet.
6.2 Shift Permission to Test
+
SO .6.2.1 Obtain Shift Supervision's (SSVN's) permission to start test.
50 6.2.2 Obtain Control Room Operator's permiss' ion to '
4 start test.
i i
)
3843070090 3,_l-os2-vo2-1, Rev. o Pcga 4 of 9 KSK/RSEscjf 6.3 Core Spray Loop "B" Contaminated Piping Inspection.
THE ACTUAL LEAKAGE RATE MEASUREMENT METBODS WILL BE LEFT TO THE DISCRETION OF THE INSPECTOR (s). THE ONLY GUIDELINES BEING THAT ALL DATA WILL BE A MEASURED QUANITY OF FLUID OVER TIME USING A STOPWATCH. DROPS PER MINUTE CAN BE USED AS A MEASUREMENT WHERE 2o DROPS
= 1CC. ALL RECORDED DATA SHALL BE IN CUBIC CENTIMETERS PER MINUTE. -
6.3.1 For all In Line components, within the boundries of Attachment B, that exhibit leakage, record on the Data Sheet their leakage rate and a description of the location of the leak. Pay particular attention to system components identified as having exhibited measurable leakage during the previous inspection.
6.3.2 From the leakage rate data on Attachment A, calculate the total system leakage rate and document the results on the Data Sheet section 6.3 6.4 Test Result Evaluation SO 6.4.1 Compare the leakage limit in 8.1 to the total system leakage rate. If the limit is exceeded N$
prepare a MRF to reduce the system leakage rate so that it is within the limit.
6.4.2 If any component's leakage rate has increased significantly since the last inspection prepare a MRF to repair the component.
6.4.3 If any component's leakage is a major portion of the overall system leakage limit prepare a MRF for its repair. i i
1
=
- m
- . - --w ,- - , , , ~ - - - - . ~ - - - - ~ , -m- - - - - - - e.-
3843070090 sT-1-os2-702-1, R2v. o
, Paga 5 of 9 KSK/RSE:cjf 7.0 - RETURN TO NORMAL SO 7.1 Inform SSVN and ACO test is complete 8.0 ACCEPTANCE CRITERIA 8.1 Loop "B" of the Core Spray System shall not exhibit a total leakage rate of greater than (Later)
AT TEST COMPLETION, ENSURE COVER SHEET IS CORRECTLY AND COMPLETELY FILLED IN.
4 9
e 4
- -- -, ,,,,---------,,---mr,---,,- ,,-- - - .. - , - - -------.--e----v-,- ---r, - - - - - .. --
a 3843070090 ST--s2-7g-ljsg;.0
'~
> KSK/RSE:cjf "B" CORE SPRAY LOOP CONTAMINATED PIPING INSPECTION DATA SHEET (1 of 3)
ACTION REQUIRED INITIALS 6.0 PROCEDURE 6.1 Preparation 6.1.1 All prerequisites satisfied NSX 6.1.2 Test Equipment INSTRUMENT MFR./MODEL SER. NO. CAL. DUE DATE sloo 14ald %Ior (Aler 53-0030 B/5/f8~
l '
6.2 Shift Permission to Test 6.2.1 SSVN permission obtained b$
6.2.2 ACO permission to test ((R ACO T+W/to:tMt Date Time 6.3 Core Spray System Contaiminated Piping Inspection 6.3.2 "B" Core Spray Loop Total Leakage Rate: I,trS cc/ min
.000816tt/ gal / min (1 cc/ min .000264 gal / min) ,
. - - . _, - - , . , - . -,-n en ,, -. ,,, , --p. . -- ,----n., . - - ,,,-
I 3843070090 ST-1-os2-702-1, Ray. o Pago 7 of 9 KSK/RSE:cjf "B" CORE SPRAY LOOP CONTAMINATED PIPING INSPECTION DATA SHEET (2 of 3) l ACTION REQUIRED INITIALS 6.4 Test Results Evaluation 6.4.1 The total Loop "B" Core Spray System .
Leakage is within Acceptable 6; ) $,Yta.f Limits. ,N / - ( * ) p 6.4.2 All individual Core Spray System Component Leakage Rates are within Acceptable Limits for both total leak rate and increase over previous leakage rate. XS N 7.0 RETURN TO NORMAL 7.1 CO/ACO informed of test completion k3(
IF ANY ENTRY IS MADE IN THIS SECTION, SIGN COVER SHEET IN APPROPRIATE SPACE.
ADDITIONAL ACTION / TEST COMMENTS h [ p11,coog ![>,,' a em M e "1 e.
ad 5.I narecss 6. 4.1 .
t, . 4. 1 nee nd anslicalle.
M t r;s ; d ,i I ' w t n er h e m . n e . M fa eha;>,ed w:1 ;,e usad tu ;d elo,n 1; :6 Jor Mora wt
! ST-1-052-702-1, Rev. 0 .-
P;.g3 8 of 9 .
TAS/RSEtcjf -
"B" CORE SPRAY LOOP CONTAIMINATED PIPING INSPECTION t DATA SHEET (3 of 3) 3843070090 i
ATTACHMENT A i
Inspector:
System Mode Date: ,
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