|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 1999-08-04
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 ML20137P8441997-02-14014 February 1997 Rev 5 to Authorization of Changes,Test & Experiments (10CFR50.59 & 72.48 Reviews) ML20140G9351997-02-14014 February 1997 Rev 13 to ISTs IT 585, Leakage Reduction & Preventive Maint Program Test of Post-Accident Containment Atmospheric Sampling Sys (Refueling) ML20140G8921997-02-14014 February 1997 Rev 7 to ISTs IT 215, SI Valves (Cold Shutdown) ML20140G9401997-02-0707 February 1997 Rev 21 to TS Tests TS 10A, Containment Airlock Door Seal Testing ML20138K2991997-01-31031 January 1997 Rev 46 to OP 4D,Part 1, Draining RCS to CVCS Hut W/O Entering Reduced Inventory ML20138K2031997-01-31031 January 1997 Rev 6 to IT 380, Purge Valve Air Sys Check Valve (Quarterly) for Unit 1 ML20138K2551997-01-31031 January 1997 Rev 2 to IT 530B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) for Unit 1 ML20138K2411997-01-31031 January 1997 Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1 ML20138K3231997-01-31031 January 1997 Rev 9 to RP 6A, SG Crevice Flush (Vacuum Mode) ML20137P8551997-01-31031 January 1997 Brine Tank Standpipe Mod ML20138K3071997-01-31031 January 1997 Rev 38 to OP 9C, Containment Venting & Purging ML20138K2901997-01-31031 January 1997 Rev 2 to IT 535A, Leakage Reduction & Preventive Maint Program Test of Train a HHSI & RHR Sys (Refueling) Unit 2 ML20138K2641997-01-31031 January 1997 Rev 12 to IT 535, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 2 ML20138K4991997-01-31031 January 1997 Rev 9 to Ort 4, Main Turbine Mechanical Overspeed Trip Device for Unit 2 ML20138K3181997-01-31031 January 1997 Rev 33 to RP 1B, Recovery from Refueling ML20138K3031997-01-31031 January 1997 Rev 1 to OP 4D,Part 5, Draining RCS to CVCS Hut W/O Entering Reduced Inventory & W/O SG Tubes ML20138K2251997-01-31031 January 1997 Rev 7 to IT 385, Purge Valve Air Sys Check Valve (Quarterly) for Unit 2 ML20138K4791997-01-31031 January 1997 Rev 15 to Ort 67, Component Cooling Water to & from Excess Letdown Heat Exchanger-Refueling Shutdown for Unit 1 ML20138K4701997-01-31031 January 1997 Rev 17 to Ort 59, Train Spray Sys CIV Leakage Test for Unit 1 ML20138K5041997-01-31031 January 1997 Rev 7 to Ort 50, PRT to Gas Analyzer Sample Line for Unit 2 ML20138K5161997-01-31031 January 1997 Rev 18 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 2 ML20138K4751997-01-31031 January 1997 Rev 19 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 1 ML20138K5231997-01-31031 January 1997 Rev 7 to Ort 71, Electrical Penetration Leak Test for Unit 2 ML20138K7311997-01-31031 January 1997 Rev 9 to TS 80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175A,B) & EDG Day Tanks (T-31A,B & T-176A,B)(Quarterly) ML20138K7171997-01-31031 January 1997 Rev 6 to TS 37, Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Yrs) for Unit 1 ML20138K3121997-01-31031 January 1997 Rev 43 to RP 1A, Preparation for Refueling 1998-09-30
[Table view] |
Text
. .- .. . - . -. ._ - - - . - . - . - . _.
. -.. NUCLEAR POWER BUSINESS UNIT PC 77 PART 1
.Y- OPERATIONS PERIODIC CHECKS MINOR
' g' Revision 9
' January 25,1997 REFUELINGINTERVAL AUTOMATIC FIRE
' PROTECTION SYSTEM VALVE TRIP-TEST AND L ALARM VERIFICATION TEST UNIT 1 4
1 DATE RECORD l DSS PROCEDURE VERFED CURRWr AND CHECKED FOR TT.MPORARY CHANGES IF FELD j OPS-OFFICE i i BY: DATE:
CFPS !
\
1.0' PURPOSE This test will verify that all automatic fire suppression system alarms operate satisfactorily and 2
that all Unit I deluge valves function properly.
2.0 REFERENCES
t
] IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures PMT/QC
- reviews.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Persons conducting this test should be extremely cautious when working around energized .
electrical equipment and moving parts of valves to avoid personal injury.
l t
3.2 Persons using the heat device should be aware of areas wetted by system actuation or drainage.
3.3 Manually-operated isolation valves should always be operated relatively slowly to ;
j minimize the probability of creating a water hammer.
1 3.4 These fire protection systems utilize rate compensating heat detectors. The heat device . ;
should be quickly positioned on the side of the detector and held there consistently, but for l
no longer than sixty seconds.
i
! 3.5 Never use oil or grease on a deluge or dry-pipe valve clapper or seat ring; unless specified by manufacturer and never cleaa the seat ring with materials or instruments that would permanently mar the soft material.
3.6 It should never be necessary, while conducting this test, to open the air-tight compartment s
of the deluge valve enclosing box.
j Y 9 1 1
9702190073 970210 F Page 1 of 7 REFERENCE USE PDR ADOCK 05000301 P PDR g .
l
,3 NUCLEAR POWER BUSINESS UNIT PC 77 PART 1 l 4
OPERATIONS PERIODIC CHECKS MINOR l4' Revision 9
!V REFUELING INTERVAL AUTOMATIC FIRE January 25,1997 ,
PROTECTION SYSTEM VALVE TRIP-TEST AND ALARM VERIFICATION TEST
- UNIT 1 4.0 DISCUSSION 4.1 Post-maintenance or special surveillance testing may be conducted as required on only a
- portion of the checklist as directed by the coordinator fire protection and safety and the duty shift superintendent.
, 4.2 The Followinn Eauioment Will Be Reauired to Comolete This Test:
4.2.1 Heat device on detachable pole.
I 4.2.2 Heavy duty extension cord.
- 4.2.3 Set of wrenclr ,
4.2.4 FM radios.
4.2.5 50' length, 2M" utility hose and large bucket.
4.2.6 Strainer flushing connections (found in U2 Non-Nuclear Room)
. 5.0 INITIAL CONDITIONS l
Lake temperature is $45 F or service water system chlorination is in progress.
i 6.0 PROCEDURE Complete the following steps for each system. Initial or provide the requested information in the appropriate blanks. Record deficiencies or problems in the remarks section, along with any WO tag numbers.
! 6.1 Contact the duty shift superintendent and obtain permission to start this test:
DSS
. 6.2 Fully shut the appropriate isolation valve and fully open the main drain valve, using the fire l system test flow diffuser, direct water to a safe location where necessary.
6.3 Pull the manual trip handle on the side of the enclosing box and verify that the deluge i valve has tripped. Verify alarms at C01, C900 D400.
ICl38 1Cl39 l ICl37 1Cl34 1Cl35 ICl36 C-141 Hydrogen Lube Oil IX02 IX01 A$ IX01 B4 Wall Spray Seal Oil IX01 C4 Reservoir
- 1FP-3703 1FP-3700 1FP-3701 1FP-3702 FP-3709 1 FP-3704 ' - 1FP-3705 4- i I
- l
, . Page 2 of 7 REFERENCE USE e
- NUCLEAR POWER BUSINESS UNIT PC 77 PART 1 l* l OPERATIONS PERIODIC CHECKS MINOR '
'b REFUELING INTERVAL AUTOMATIC FIRE Revision 9 January 25,1997 :
. , PROTECTION SYSTEM VALVE TRIP-TEST AND !
ALARM VERIFICATION TEST
- UNIT 1 6.4 Remove the enclosing box cover and the hand-hole cover of the deluge valve. Ensure that the weight dropped, the clapper latch moved off the clapper and that the clapper swings freely.
6.5 Inspect and remove any foreign matter from the rubber clapper facing and clean the clapper seat-ring with bare fingers. Replace the rubber facing if deteriorated or damaged.
6.6 Clean any accumulation of sediment or foreign material fnm inside the deluge valve body.
6.7 Inspect the mating surfaces of the clapper and clapper latch, and remove any foreign material with bare fingers.
6.8 Manually raise and lower the weight on the guide rod to determine that there is no restriction in movement, and that the guide rod is relatively straight. If oxidation has occurred on the guide rod, remove it with a fine grain sand paper and apply a thin film of oil, making certain that the oil is not applied to and cannot spread to any other internal parts.
6.9 Reset the local C panel, reset the clapper into set position, pull out the reset handle, and raise the weight.
aCAUTION* THE TRANSFORMER AND WALL SPRAY DETECTORS SHOULD ONLY BE TESTED DURING REFUELING SHUTDOWN WHEN TRANSFORMERS ARE DEENERGIZED.
NOTE: Because of obstructions and extreme height, all of the wall spray dete.-tors may not be accessible. At a minimum the El 8' heat detectors shallbe tested All transformer, hydrogen seal oil and lube oil reservoir detectors shall be tested during the annualtest.
6.10 Independently check each heat detector actuation and Control Room actuation. Reput until all methods have been tested.
Cl41 1Cl38 1Cl39 1Cl37 1Cl34 1Cl35 ICl36 Wall Hydrogen Lube Oil IX02 IX01 A4 IX01 B4 IX01 C4 Spray Seal Oil Reservoir 1FP-3703 1FP-3700 1FP-3701 1FP-3702 FP-3709 1FP-3704 1FP-3703 Heat Detection Actuation Ctl Rm Actuation *'
Page 3 of 7 REFERENCE USE 9
,3 NUCLEAR POWER BUSINESS UNIT PC 77 PART 1 OPERATIONS PERIODIC CHECKS MINOR Revision 9
,b REFUELING INTERVAL AUTOMATIC FIRE January 25,1997 PROTECTION SYSTEM VALVE TRIP-TEST AND ALARM VERIFICATION TEST UNIT 1 6.11 Replace the hand hole cover and tighten fasteners.
aCAUTIONa ENSURE TRANSFORMER AREA IS CLEAR OF PEOPLE, ELECTRICAL EQUIPMENT IS COVERED OR REMOVED AND AREA IS SAFE FOR WATER FLOW.
NOTE: Steps 6.12 And 6.13 Do not applyfor the tube oil reservoir and hydrogen seal oil systems.
6.12 Close the main drain valve and open the isolation valve. Allow water to flow until clear but for no longer then 5 minutes. Observe nozzles for proper spray without obstructions or direct spray on bushing.
Cl41 1C138 1Cl39 ICl37 1Cl34 1Cl35 1Cl36 Wall Hydrogen Lube Oil IX02 IX01 A4 IX01 B& 1X01 C$ Spray Seal Oil Reservoir 1FP-3703 1FP-3700 1FP-3701 1FP-3702 FP-3709 1FP-3704 1FP-3705 Fire System Flush N/A N/A i
6.13 Fully close the isolation valve and open the main drain.
6.14 Reset the deluge valve, replace the enclosure box cover and flush the in line strainer.
6.15 Fully close the main drain valve and fully open and red-lock the isolation valve.
Wall Hydrogen Lube Oil
- IX02 IX01 A$ 1X01 B4 IX01 C$ Spray Seal Oil Reservoir IFP-3703 IFP-3700 IFP-3701 1FP-3702 FP-3709 IFP-3704 IFP-3705 FP-41 FP-44 FP-43 FP-42 FP-135 FP-60 FP-70 Red Lock No.
Page 4 of 7 REFERENCE USE
' NUCLEAR POWER BUSINESS UNIT PC 77 PART 1 OPERATIONS PERIODIC CHECKS hENOR Revision 9 h REFUELING INTERVAL AUTOMATIC FIRE January 25,1997
~
PROTECTION SYSTEM VALVE TRIP-TEST AND ALARM VERIFICATION TEST UNIT 1 l PMT
~
6.16 With the isolation valve fully open, record the pressure on the gauge. Fully open the main drain and again record the pressure, then fully shut the main drain. Ensure that the pressure is now greater than, or equal to, the original reading.
Hydrogen Lube Oil IX02 IX01 A$ IX01 B$ IX01 C$ Wall Spray Seal Oil Reservoir 1FP-3703 IFP-3700 1FP-3701 IFP-3702 FP-3709 IFP-3704 1FP-3705 Original Gauge Rdg.
? (psig)
Main Drain Open Rdg.
(psig)
- . Final Gauge Rdg.
- (psig) 6.17 Clear all test-related alarms on local panel C01, C900 and D400. I C-141 1Cl38 1Cl39 ICl37 ICl34 1Cl35 ICl36 Wall Hydrogen Lube Oil IX02 IX01 A$ IX01 B& IX01 C4 Spray Seal Oil Reservoir 1FP-3703 1FP-3700 1FP-3701 1FP-3702 FP-3709 1FP-3704 J FP-3705 Alarms Cir/
Conditions Normal 6.18 Second independent operator performs the following valve lineup verification:
Position Initials FP-41 IFP-3703 Isolation LO FP-44 1FP-3700 Isolation __LQ. _
FP-43 IFP-3701 Isolation . LO _
FP-42 IFP-3702 Isolation _LQ__
FP-135 FP-3709 Isoir. tion LO FP-60 IFP-3704 Isclation __LQ__.
FP-70 IFP-3705 Isootion LO ..
Remarks:
Page 5 of 7 REFERENCE USE
,'34 j ;! I i'l { !! ;!i i ;
- !. 4 -4i :: : ! ! . i;
- ;;(b
s UAPR ON NLRE AOF PU .
I T RTU E C R L 1
MEECL AE TA VTI I EI N OR R NI I
OG NP SO F
I S N PW CY AS T E EE TTEVR RR I
I OB O DU N MA L I S CI TVA C E N I g@on hs=
=$Ia "
EA U SL T HS J @ e TVE O ES .
E. ws5 C K
b - T M R A SNU
. Eg I
hwg I T PI T -
_ lN
- C
$e,
e gW od 3g 5s TE _
6 A
o e N o
f ' e D 7 k8g oErb 2O . N *9iw i%
c 4 s M
naRMP J
e I C v
8
y oiO7 EY 8 h*
2 n R. A P
,5 9 R 1
9 T
I 9
R .
7 E .
F E ~
R E
N C
E U
S
,E _
Eksm
- > O r. a5 mn ,
hbor e m ses s2 r r/HHHfHHH/HHHHA Ge 58
= - - JL
- s 5- =,.-ms D3$ $$
= . .,
xqg8:e sm an p L. o =-
J *
. .n 1 X O 2. ==-==
$ $ S m sego ;
y .
m n m r, g f ap o msSu us has H b 50 5641 k.bn l
- r b *3 '
/ l ,O m-56* exs-sut em-wu e as-un exs-uu exs-ssot o
. un e e o e e .
-s ~
/ n.o ui, ni, tu, i /
/
--=== IXol-C
/
/j ,, ,, 4
_ l .-s43e
- ts ni, nis tu, Qeg:3yg8.e
/ m i Y /
as-une e e e o e ye );
/j Nio His Rio EUs '8-5" o -
o d .
Q
- gr fr o
, , ,,,,,, exs-ssu e xs-sus e us-sna e ms-su s e xs-sso, -
. ns-3.no S
$ d 44dEE, E
z O l m
m
- _ - - - - - - - - . --