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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989 Suppl 15 to Startup Rept for Period 890501-0801 ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989 Suppl 14 to Startup Rept for Period 890201-0501 ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988 Suppl 12 to Startup Rept for Period Aug-Nov 1988 SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988 Suppl 11 to Startup Rept for May-Aug 1988 ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures 1994-07-31
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D5931988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 10, Level/ Power Control ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D5621988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 7, Emergency Depressurization ML20151D6971988-06-20020 June 1988 Rev 9 to Procedure 29.023.01, Reactor Pressure Vessel Control Emergency Procedure. W/One Oversize Encl ML20151D6281988-06-10010 June 1988 Rev 1 to Procedure 3.04, Developing Written Tests ML20151D6481988-06-10010 June 1988 Rev 1 to Procedure 5.01, Counseling Trainees & Providing Remedial Training Plan ML20151D6791988-06-10010 June 1988 Rev 2 to Procedure 8.01, Simulator Exam Evaluation ML20151D6581988-06-10010 June 1988 Rev 0 to Procedure 5.02, Formulating Tests from Question & Answer Banks & Administering Tests ML20151D5821988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 9, Reactor Pressure Vessel Flooding ML20151D4981988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 5, Radioactive Release Control ML20151D5691988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 8, Steam Cooling ML20151D6041988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 12, Figure ML20151D5481988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 6, Alternate Level Control ML20151D4471988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 3, Primary Containment Control ML20151D4251988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 2, Reactor Pressure Vessel Control ML20151D5971988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 11, Primary Containment Flooding ML20151D4901988-05-11011 May 1988 Rev 0 to Plant Specific Technical Guideline 4, Secondary Containment Control ML20196A9081988-01-25025 January 1988 Rev 3 to 80A8614, Inservice Insp Program Plan,Core Spray Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing ML20196A9601988-01-25025 January 1988 Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1 ML20196A9911988-01-25025 January 1988 Rev 3 to 80A8621, Inservice Insp Program Plan,Containment Penetration Flued Heads,Shoreham Nuclear Power Plant Unit 1 ML20196A9471988-01-25025 January 1988 Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1 1994-07-31
[Table view] |
Text
Submittcd t SP Numbar 29.023.03 (Section hard)
App oved. Revision: C (Plant Manager)
Effective Date CONTAINMENT CONTROL EMERCENCY PROCEDURE i I+.bi a
1.0 PURPOSE The purpose of this procedure is to control primary containmest temperatures, pressure and level. This procedure will be performed concurrently with the procedure from which it was entered.
2.0 ENTRY CONDITIONS The entry conditions for this procedure are any of the following:
Paragraph 2.1 Suppression Pool Temperature Above 90*F 3.1 2.2 Drywell Temperature Above 135*F -3.2 2.3 Drywell Pressure Above 1.69 psig 3.3 2.4 Suppression Pool Level Above 26' 8" 3.4 2.5 Suppression Pool Level Below 26' 0" 3.4 NOTE Enter the paragraphs of this procedure as required by the entry condition. The paragraphs can and should be performed concurrently with each other as the entry conditions dictate.
3.0 OPERATOR ACTIONS 3.1 Monitor and control suppression pool temperature.
3.1.1 Attempt to close any stuck open SRV per SP23.116.01.
CAUTION If continuous LPCI is required to assure adequate core cooling, do not divert RRR pumps from the LPCI mode.
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' 7//c[f/ G107230262 810720 PDR ADOCK 05000322 A PDR
3.1.2- Operato cvailabli cupproscion pool cocling par
'SP 23.121.91 wh:n cupressien pool tetpsratura exceeds 90'F.
3.1.3 If suppression-pool temperature reaches 110*F, scram the reactor per SP 29 919 91, Emergency Shutdown.
CAUTION Cooldown rates above'199'F/HR may be required to accomplish this step.
CAUTION Do not depressurize the RPV below 100 psig (HPCI low pressure isolation setpoint) unless motor driven pumps
- sufficient to maintain RPV water level are running and available for injection.
CAUTION Observe NPSH requirements. for pumps taking a suction from the suppression pool.
1 SUPPRESSION POOL PUMPS MAXIMUM TEMPERATURE MINIMUM LEVEL HPCI (Later) (Later)
RHR (Later) (Later)
CS (Later) (Later)
RCIC- (Later) (Later) i 3.1.4- If suppression pool temperature cannot be maintained below the heat capacity temperature limit, maintain RPV pressure below the limit of Figure 1.
3.1.5 If suppression pool temperature and RPV pressure cannot be restored or maintained below the heat capacity temperature limit, proceed to SP29.023.05 (Rapid RPV Depressurization).
i SP 29.023.03 Rev. C
/ / Page 2
-u
. . - _ . .- ..- . . - . _ =. -. . . .
3.2 Monitor cnd control drywell tamparcture.
3.2.1- Operate available drywell cooling when drywell temperature exceeds 135*F.
CAUTION DO NOT DIVERT RHR PUMPS FROM THE LPCI HDDE UNLESS ADEQUATE C0RE COOLING IS ASSURED.
- o. 1 -3.2.2 If DRYWELL TEMPERATURE approaches 296*F,
' SHUTDOWN the Reactor Recirculation Pumps and Drywell Fans and initiate Drywell Sprays CAUTION Do not depressurize the RPV below 199 psig unless motor driven pumps suf ficient to maintain RPV water level are rr.nning and available for injection.
CAUTION Cooldown rates above 199"F/HR may be required to
' accomplish this step.
3.2'.3' - If DRYWELL TEMPERATURE reaches the RPV Saturation Limit, 71gure 2, enter SP29 923 95 (Rapid RPV Depressurization).
3.2.4 . If drywell temperature cannot be maintained below 296*F, proceed to SP23.023.05 (Rapid RPV Depressurization).
3.3 MONITOR AND CONTROL primary containment pressure with the following systems as required:
3.3.1 IF PRIMARY CONTAINMENT PRESSURE REACHES 1.69 psig Tperate THE POST LOCA HYDROGEN RECOMBINATION SYSTEM per SP23.402.01.
3.3.2 Operate the.MSIV Leakage Control System per SP23.496 91.
' CAUTION ELEVATED SUPPRESSION CHAMBER PRESSURE HAY TRIP THE RCIC
. TURBINE ON HICH EXHAUST PRESSURE, 25 psig.
SP 29.023.03 Rev. C
/ / Page 3
- -w - - g 5- ,,9., aq,,p .... ,, y,, ,._,.,gy,~ , ,, ., ,,,,p,,, ,,,_-g, , ,, , , , , , , ,, , ,, ,,_q_, ,_, , ,,,,_ _
3.3.3 VENT th2 primary centninment through tha RBSVS systen per SP23.418 91 only when the drywell temperature is below 212*F. ' ENSURE Rad / Chem samples and analyzes primary containment atmosphere prior to venting.
CAUTION DO NOT DIVERT RHR PUMPS FROM THE LPCI HODE UNLESS ADEQUATE CORE COOLING IS ASSURED.
3.3.4 INITIATE suppression pool sprays before the Suppression Chamb:r pressure reaches the suppression pool spray ,
limit, Fig. 3.
3.3.5 If Suppr'ession Chamber pressure approaches the Pressure Suppression Limit, Fig. 4 SHUTDOWN the Reactor Recirculation Pumps and the Drywell Fans and INITIATE Drywell Sprays as necessary to maintain Suppression Chamber pressure below the curve.
3.3.6 If Suppression Chamber pressure cannot be maintained below the presure suppression limit Fig. 4, ENTER SP 29.923 95 (Rapid RPV Depressurization).
9.4 . MONITOR and CONTROL suppression pool water level 3.4.1 MAINTAIN suppression pool water level between 26'9" and 26'8". ENSURE Rad / Chem samples and analyzes suppression pool water prior to lowering of Suppression Pool Level.
CAUTION Do not depressurize the RPV below 199 psig unless motor driven pumps sufficient to maintain RPV water level are l
runnning and available for injection.
i l~
i I CAUTION Cooldown rates above 199'F/HR may be required to accomplish the following steps.
P S? 29.023.03 Rev. C
/ / Page 4 '
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- - - . - . _ _ .. - . - = -_ .
3.4.2 If.cupprocsien' pool w: tee 1sval is lara than 26'9" and isval ccn be maintain;d abova tha heat cep: city laval limit, Fig. 5, initiate suppressioa pool makeup per SP (later).
3.4.3 If suppression pool cannot be maintained above the heat capacity level limit, Fig. 5, proceed to SP 29.923 95 (Rapid RPV Depressurization).
CAUTION.
If_ high suppression pool level (26'8") exists or' low condensate storage tant level (3'4") exists, VERIFY / MANUALLY transfer RCIC and HPCI suctions from the CST tank to the Suppression pool.
3.4.4 IJ[ the Suppression Pool water level is above 26'8" and adequate core cooling is assured, TERMINATE injection
-into'the reactor vessel from sources external to the primary containment.
3.4.5' If suppression pool water level cannot be maintained below the suppression pool load limit, maintain RPV pressure below the limit' of Figure 6.
CAUTION
" > Observe NPSH requirements for pumps taking a suction fr m the Suppression Fool.
, SUPriESSION POOL PUMPS MAXIMUM TEMPERATURE MINIMUM LEVEL
[ HFCI (Later) (Later)
CS (Later) (Later)
RHR (Later) (Later)
RCIC (Later) (Later)
!. 3.4.6 ~ If suppression pool water level and RPV pressure cannot be restored or maintained below the suppression pool load limit, proceed to SP 29 923.95, rapid RPV l _
depressurization.
v
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! SP 29.023.03 Rev. C
/ / Page 5
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3.4.7 Whsn primary centninment watar 1sval rsschas intsr isst terminate injection into the RPV from sources external to the primary containment irrespective of whether adequate core cooling is assured.
49 REFERENCES 4.1 SP 23.116 91 Main and Auxiliary Steam 4.2 SP 23.121.91 Residual Heat Removal (RHR) System 4.3 SP 29 919 91 Emergency Shutdown 4.4. SP 29.923 95 Rapid RPV Depressurization 4.5 SP 23.492 91 Primary Containment Post LOCA Hydrogen Recombination 4.6 SP 23.418.91 HVAC Reactor Building f .
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SP 29.023.03 Rev. C
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