|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20078A3771994-05-12012 May 1994 Vols 1 & 2 of Vogtle Electric Generating Plant Unit 1 Readiness Review Module 4 Mechanical Equipment & Piping Program ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20035F5601993-04-0505 April 1993 Rev 5 to Inservice Insp Plan (ISI-P-014) for Vogtle Electric Generating Plant,Unit 2 ML20035F0721993-03-22022 March 1993 Rev 7 to Inservice Test Program (ISI-P-008) for Vogtle Electric Generating Plant,Unit 1 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program ML20092G7441992-02-20020 February 1992 Undated Draft Site Safety Manual. Supporting Documentation Encl ML20094K1721991-12-31031 December 1991 Draft, ODCM for Vogtle Electric Generating Plant ML20086Q7231991-12-0404 December 1991 Rev 7 to Procedure 91202-C, Activation & Operation of Operations Support Ctr ML20129J2961991-09-13013 September 1991 Rev 3 to Procedure 23985-1, RCS Temporary Water Level Sys ML20091L7891991-07-0303 July 1991 Rev 5 to Procedure 29537-C, Outage Scheduling ML20079G4971991-06-10010 June 1991 Rev 5 to ISI-P-006, Inservice Insp Program for Vogtle Unit 1 ML20079G5071991-06-10010 June 1991 Rev 4 to ISI-P-014, Inservice Insp Program for Vogtle Unit 2 ML20091L7991991-04-22022 April 1991 Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to Ts ML20091L7771991-04-17017 April 1991 Rev 21 to Procedure 10000-C, Conduct of Operations ML20129H6151991-03-20020 March 1991 Rev 7 to Procedure 10004-C, Shift Relief. Supporting Documentation Encl ML20129J0311990-09-18018 September 1990 Rev 4 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program ML20043B6321990-05-22022 May 1990 Rev 5 to ISI-P-008, Inservice Testing Program ML20043B6381990-05-22022 May 1990 Rev 2 to ISI-P-016, Inservice Testing Program ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events ML20113G6141990-05-15015 May 1990 Rev 0 to VEGP-22981-C, Calcon Pneumatic Temp Sensor Calibr 1TSH-19110-1TSH-19119,1TSH-19146,1TSH-19153,2TSH-19110- 2TSH-19119,2TSH-19146 & 2TSH-19153. Supporting Documentation Encl ML20034C1061990-04-26026 April 1990 Rev 4 to Inservice Insp Program First 10-Yr Interval ML20129H9081990-04-16016 April 1990 Rev 3 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20113G3421990-04-0404 April 1990 Procedure T-ENG-90-016, DG1A J.W. Temp Monitoring & Recording ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20092F9691990-03-28028 March 1990 Rev 0 to T-ENG-90-15, Unit One Train a DCP 88-V1N0070 Sequencer Functional Test. Supporting Documentation Encl ML20092F8621990-03-28028 March 1990 Rev 1 to Procedure T-ENG-90-11, A-Train Undervoltage Test ML20092F7521990-03-27027 March 1990 Rev 20 to 13145-1, Diesel Generators ML20092F8741990-03-26026 March 1990 Rev 3 to Procedure VEGP 00053-C, B-Train Undervoltage Test ML20092F8481990-03-25025 March 1990 Rev 2 to Generator & Engine Control Panel Functional Test Procedure 27563-C, Power & Signal Removal/Replacement Data Sheet ML20092H0391990-03-23023 March 1990 Rev 16 to VEGP-10000-C, Conduct of Operations ML20092F5271990-03-21021 March 1990 Data Sheet 1 to Rev 12 to VEGP-10006-C, Reactor Trip Rept. Supporting Documentation Encl ML20092F7341990-03-19019 March 1990 Rev 16 to Procedure 25717-C, Torquing Electrical Type Connections ML20092G9111990-03-16016 March 1990 Abnormal Operating Procedure to Rev 7 to VEGP-18028-C, Loss of Instrument Air ML20092F6901990-03-16016 March 1990 Rev 7 to Procedure 18019-C, Abnormal Operating Procedure, Loss of Rhr ML20092F6361990-03-12012 March 1990 Temporary Change Notice to Rev 14 to Procedure 12007-C, Refueling Entry 1998-05-25
[Table view] |
Text
f h.
Georgia r
o VOGTLE ELECTRIC GEN 6 '-
p.o p, g V'3 pct TRAINING LESSON PLAN TITLE:
GAS GUERATION NUMBER:
5173 % w_o PROGRAM-REVISION-
- o ucease oet m w." L.
AUTHOR:
RICHARD D. BRIGDON DATE:
l'535 APPROVED:
MM DATE:
g-////f
REFERENCES:
t.
NUREG 0737. ITEN II.B.4
- 2..
MCD TRAINING, VEGP FSAR, CHAPTER 13; ITEM 13.2.1.1.6
'5,
MITIGATING CORE DAMAGE, " GAS GENERATION," GENERAL PHYSICS CORPORATION INSTRUCTOR GUIDELINES:
to_ we-u.i cr;-oo-c.-oo i HANDOUT: " GAS GENERATION,"-et-Elb 086 W a.cosE % =s(34teer' **** LLST 0+
8 L.e -TP-3Wo7-00 -C. S&-5F-486-4 col FRESSURE VS. CONCENTRATION FOR H IGNITION IN 2
PRESSURE VESSEL
'., TP=089=2'odi TMI-2 REACTOR BUILDING PRESSURE SPIKE SE-TP-066=S M EFFECTS OF H IGNITION ON TMI-2 S/G PRESSURE S&-WP-066-4cor CALCULATED V 0F H BUBBLE IN TMI-2 HEAD VS.
y r
TIME
- 45-486-604 E MATultTAL BALANCE SUMNARY 2
. mum 1
(
Lc-'9-36 c7-co-c
" ?,'_
^*f 1.
PURPOSE STATEMENT:
THIS LESSON WILL PROVIDE THE STUDENT WITH AN UNDERSTANDING OF HOW HYDROGEN CAN BE PRODUCED INSIDE CONTAINMENT DURING AN ACCIDENT, THE HAZARDS ASSOCIATED WITH HIGH HYDROGEN CONCENTRATIONS, AND THE MEANS AVAILABLE FOR DISPOSAL OF HYDROGEN AND OTHER NON-CONDENSIBLE GASSES.
II.
LIST OF OBJECTIVES:
Ta runi n al Obiactive i.
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2 v..ki4-- atj--.4 --
1.
List the sources of Hydrogen and Oxygen within the primary systems and containment.
2.
State the hasardous concentration ranges of explosive and flasmable mixtures of Hydrogen and Oxygen.
~
..s..
3 Describe the means available to measure the containment hydrogen concentration and to control it.
4.
Explain the techniques for venting-and disposing of non-condensible gasses.
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LESSON OUTLINE:
NOTES I.
INTRODUCTION A.
Topic of most concern at TMI was H bubble formed in W-TE~ h
the reactor vessel.
cG3thcm L5 1.
Fears of explosion were unfounded due to lack of 0 in RCS.
2 2.
H Prevents accumulation of 0
B.
Amount of H, produced was sufficient to cause legitimate
-02 "2 000 i concerns ab5ut core cooling and flammability in the T9-oo T containment atmosphere.
1.
An ignition occurred about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> into accident.
9R=TF=089=2-TP-cos 2.
Equipment may have been damaged but no harm to CTB.
II.
SOURCES OF HYDROGEN A.
Radiolysis of Water gpyc g g 1.
2H O p 2H2+02 2
n 2.
Yield dependent upon:
a.
Energy absorbed Boiling increases radiolysis by 30 times I
b.
Nature of radiation 1)
Co-60 gamma
.45 molecules /100 av of emergy absorsed 2) 4 1.1 molecules /100 ev absorbed c.
Temperature - radiolysis stopped by adding H2 C.~
to residence ties l
3.
74 "
1 ppe; therefore radiolysis not b.
H f*** **di*1I*i" *** i"*i *ifi"*"t 2
3
(
B.
Zirconium-Water Reaction l
l 1.
Above 1600'F Zire alloys react with water to form H2 + Zr02 a.
Zr + 2H 0 -> Zr02 + 2H2 2
f p
3 E
co -cP. %.c 7 -ce -C.
.R-ee-ee.
' lli.
LESSON OUTLINE:
NOTES b.
Reaction rate increases with temp. and very rapid above 2700*F (self-sustaining at approx.
2300*F) 2.
Reaction could result in chemical-induced explosion.
3.
Violence of the reaction dependent upon:
a.
Rate of cladding melt b.
Size of melted particles c.
Ratio of amount of cladding to amount of water.
4.
Result of large LOCA a.
Start and self sustain at 2200*F b.
Accelerate rapidly to 3000*F 1)'
Clad melt occurs 2)
Stops if heat source removed when in contact with liquid water.
.a c.
E, produced in proportion to amount of cladding material that has reached.
1) 8 scf per Ib. of Zr oxidized 2) 1.e., large amount of H, indicates large amount of clad failure d.
E, leaves reactor vessel through break and rises to CTMt done.
1)
Prevents 0, absorption in cloud due to t
conceEtration.
2 while rising Al@f C.
Ee0E
?-
1.
-Y 2EaA102
~
l 2.
NaOH provided by containment spray system actuation during LOCA Aluminum - components inside containment 3.
Corrected / minimized by minimizing aluminum components in containment.
o 4
awe s
=- u_a 111.
LESSON OUTLINE:
NOTES III. HYDROGEN COMBUSTION A.
Limits of Combustion (.d e T c G IE c-n u t * ~7_
1.
Flammable at 4 percent 2.
Lower limit for detonation is 19 percent B.
Pressure Increase from H Combustion 2
1.
Combustion of 4 to 9 percent concentrations produce pressure excursions dependent upon:
a.
Pre-combustion mixture temp.
b.
H2 " ""*""**"i "
c.
Yessel material, size, shape 4R-TP=08t=1
-t?--O o 2 d.
Ignition mechanism 2.
Between'8-10% - slow flame propagation (pressure
~
~
rises 8 times initial) 3.
Greater than 14-19 percent - detonation (pressure rise 17 times initial)
F IV.
H FRENOMENA AT THI-2 2
A.
28 psig pressure pulse on 3/28/79
-Sa-D-086-2 TP-oo3 1.
Reactor building temp. = 40'F 2.
No'similar imlientions at any other time.
3.
Figure 3 shows pulse as sa apparent decrease in 85 4 9-046-&
steam pressure.
'T1"- 0 0 9 4.
Figure 1 ure rise of 28 poi from 4R-fP-606=1-TP-oo 2.
B.
E 1/85 2
1.
.7%
contains 21% 0 82.6%
2 2.
Sample 2 - H = 1.7Z 2
= 16.5%
N = 81.8%
2 3.
Higher concentrations on 4/1/79 indicate earlier H burn.
2 5
e s.o-L.f-3G407 04'C, sa-u-ou lli.
LESSON OUTLINE:
NOTES V.
CONTADGENT CAPABILITY A.
Pk pressure of 28 peig.
B.
CTMT design pressure - 60 psig Therefore, no threat to integrity of oxidation of 29%
of Zr.
C.
Possibility of H buildup very low due to the numerous 2
ignition sources.
(Motors, valve operators, etc.)
D.
If 100% of Zr had reacted containment would have
- '"'-005 5 remained intact.
T'F-. %
CNME failure 150 to 190 psia due to tendon failure.
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LESSON OUTLINE:
NOTES i
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TRAINING MATERIAL ROUTING g,
TRAINING MATERIAL NUMBER REVI'ED MATERIAL
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REVISOR R M A
l y
REASON FOR REVISION:
)
MAJOR REVISION DUE TO ERRORS OR OMISSIONS.
REVISION DUE TO CHANGES IN EQUIPMENT.
j g REVISION DUE TO CHANGES IN PROCEDURES /0PERATING INSTRUCTIONS OR POLICT.
I DESIRE ADDITIONAL GRAPHICS / HANDOUTS FOR THIS TRAINING MATERIAL OTHER COMMITTMENTS: TES M NO DRAFING REQUEST FILLED OUT. TES NO W
DATE SUBMITTED FOR SUPERVISOR'S REVIEW '7/17-REVIEW SAT UNSAT W
APPROVAL SIGNA DATE
- DATE NEEDE FOR FROM TYF UG f/
M LIBRART CLERE:
b
~
DATE TO TTFING I
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DATE TO DRAFTING I/M
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DATE FROM TTFDG DATE FRON DRAFTING 8/#
5 CONFILID MATERTA12 TO INSTRUCTOR FOR RIV,I N.
DATE INSTEDCTOR 3371W: TTFING SAT UNSAT DRAFTING SAT UNSAT REWORE lETT
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.i=hCE ST c':;;,zx '(3 S
TTFING - SAT UNSAT g*
DRAFTING SAT UNSAT r
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REWORE: WRTT DATE NEEDED BY i
'SUPERVISOE SIGNATURE DATE LIBRARIAN RECEIFT FOR INCLUSION /0UTDATING OF FILES. DATE TILE WORE DONE DATE e
9
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