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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/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals 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 ML20203H2501997-12-31031 December 1997 Rev 19 to Odcm ML20211P9471997-10-15015 October 1997 Revised MSRV Tailpipe Temp Action Plan ML20203H2701997-04-30030 April 1997 Rev 18 to Odcm ML20113E0491996-06-28028 June 1996 Technical Basis & Description of Approach for Review Method Selection ML20100L9131995-11-30030 November 1995 Rev 17 to LGS Units 1 & 2 Odcm ML20094B5391995-10-24024 October 1995 Scenario Manual for Limerick Generating Station Emergency Preparedness Annual Exercise (Radiological Scenario) ML20094B5041995-10-24024 October 1995 Scenario Manual for Limerick Generating Station Emergency Preparedness Annual Exercise (General Scenario) ML20100L9051995-05-0808 May 1995 Rev 16 to LGS Units 1 & 2 Odcm ML20100L9001995-01-19019 January 1995 Rev 1 to RW-C-100, Solid Radwaste Sys Pcp ML20080N1461994-12-31031 December 1994 Rev 15 to LGS Units 1 & 2 Odcm ML20073S9471994-06-21021 June 1994 Non-proprietary Revised Emergency Response Procedures, Including Revs 43 & 44 to Index,Rev 10 to ERP-300 & Rev 9 to & ERP-500 ML20080N1401994-06-0909 June 1994 Rev 14 to LGS Units 1 & 2 Odcm ML20080N1291994-06-0606 June 1994 Rev 13 to LGS Units 1 & 2 Odcm ML20080N1171994-04-30030 April 1994 Rev 12 to LGS Units 1 & 2 Odcm ML20056G0981992-12-28028 December 1992 Rev 0 to Procedure RW-C-100, Solid Radwaste Sys Pcp. Procedure Supersedes RW-800 at LGS & RW-120 & RW-121 at PBAPS ML20098D9641992-05-20020 May 1992 Rev 57 to Limerick Generating Station Off-Normal (on) (Bases) Procedures Index,Reflecting Rev 0 to ON-123 Bases, Mispositioned Control Rod ML20098D9501992-05-18018 May 1992 Rev 0 to Off-Normal (on) Procedure ON-123 Bases, Mispositioned Control Rod ML20098D9451992-05-18018 May 1992 Rev 0 to Off-Normal (on) Procedure ON-123, Mispositioned Control Rod ML20113G9421992-05-0101 May 1992 Rev 2 to Spec ML-008, Limerick Generating Station,Units 1 & 2 First Ten Yr Interval Pump & Valve IST Program ML20094S5671992-04-0303 April 1992 Rev 54 to Operational Transient Procedures Index ML20094S5881992-04-0303 April 1992 Rev 54 to Operational Transient Bases Procedures Index ML20094S5931992-04-0101 April 1992 Rev 9 to OT-100 Reactor Low Level ML20094S5751992-04-0101 April 1992 Rev 9 to OT-100 Bases, Reactor Low Level - Bases ML20091N2791991-10-0404 October 1991 Inservice Insp Program, First 10-Yr Interval ML20065S1171990-12-0606 December 1990 Procedures Index to Rev 2 to ON-120 Bases, Fuel Handling Problems ML20065S1151990-12-0606 December 1990 Rev 2 to ON-120 Bases, Fuel Handling Problems ML20065M6731990-11-26026 November 1990 Rev 19 to Limerick Generating Station Trip Bases Procedures Index ML20059E6501990-04-0303 April 1990 Rev 8 to Odcm ML20246E1601989-07-27027 July 1989 Samda Estimate Process & Cost Estimate Breakdown ML20246K5581989-03-0303 March 1989 Rev 8 to Solid Radwaste Sys Process Control Program ML20206M1671988-11-18018 November 1988 Rev 0 to Pump & Valve Inservice Testing (IST) Program,First 10 Yr Interval ML20205K8301988-08-31031 August 1988 Rev 1 to, Limerick Generating Station Unit 2 Reactor Pressure Vessel Preservice Insp Exam Plan ML20154B9361988-08-29029 August 1988 Rev 0 to Readiness Verification Program (Rvp) Description ML20150C9531988-07-0606 July 1988 Rev 1 to Program for Independent Design & Const Assessment of Limerick - Unit 2 ML20155A0081988-05-27027 May 1988 Rev 0 to Program for Independent Design & Const Assessment ML20151W2701988-04-26026 April 1988 Rev 5 to 8031-P-505, Preservice Insp Exam Plan for Nuclear Piping Sys ML20150E7971988-03-30030 March 1988 Rev 5 to Offsite Dose Calculation Manual ML20151W3551987-11-19019 November 1987 Suppl 2 to Rev 2 to UT-AUSTENITIC-M, Suppl for Manual Ultrasonic Exam of Dissimilar Metal Welds ML20151W3501987-11-18018 November 1987 Suppl 2 to Rev 1 to UT-AUSTENITIC-A, Suppl for Automatic Ultrasonic Exam of Dissimilar Metal Welds ML20151W2831987-10-15015 October 1987 Rev 1 to Field Quality Procedure FQP-01, Procedure for Qualification & Certification of Insp & Testing Personnel in Accordance W/Asme/Ansi N45.2.6 - 1978 & Asme/Ansi NQA-1 ML20151W2971987-10-13013 October 1987 Rev 01 to Field Quality Procedure FQP-03, Procedure for Qualification & Certification of NDE Personnel in Accordance W/Asnt SNT-Tc-1A & Section XI ML20151W3451987-08-28028 August 1987 Suppl 1 to Rev 1 to UT-AUSTENITIC-A, Suppl for Ultrasonic Exam of Weld Overlayed Austenitic Piping ML20151W3391987-08-28028 August 1987 Rev 4 to UT-AUSTENITIC-A, Automatic Ultrasonic Exam of Similar & Dissimilar Metal Welds in Piping Sys ML20236Y2751987-08-28028 August 1987 Rev 1 to 8031-P-504, Preservice Insp Program ML20237J9901987-07-31031 July 1987 Rev 3 to First 10-yr Interval Augmented Inservice Insp Program ML20237J8401987-07-31031 July 1987 Rev 3 to First 10-yr Interval Inservice Insp Program ML20238C8121987-07-27027 July 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 5 to App 1 to EP-102, Unusual Event Notification Message & Rev 8 to EP-110, Personnel Assembly & Accountability. W/Revised Index ML20236A7231987-07-21021 July 1987 Rev 6 to 80A2972, Pump & Valve Inservice Testing Program Plan for Limerick Generating Station Unit 1 1998-11-16
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e oT-200 n^scs Rev-
- I I 3924020820 Page 1 of 4
- a. CAH/smk i
PHILADELPHIA ELECTRIC COMPANY LIHERICK GENLRATING STATION gg OT-100 REACTOR LOW LEVEL - BASES -l 5
1.0 ENTRY CONDITIONS 1.1 Unexpected / unexplained drop in RPV water level.
This procedure specifies actions to be.taken in response-to an ur. expected or unexplained decrease in reactor level.
Some typical events covered by this procedure are the trip of a RFP or condensate pump, and failure of the feedwater control system in the minimum flow direction. Entry into this procedure is inappropriate under shutdown conditions when reactor level is being manually controlled. Manual operation of the feedwater system while in a shutdown ..
condition will require the operator to routinely compensate for unexpected decreases in water level, and the majority of the steps in the procedure are applicable only to high power operation.
O 2.0 J,MMEDIATE OPERATOR ACTIONS 2.1 Reduce Reactor power per Reactor Maneuvering Shutdown Instructions until normal level is restored.
Reactor low level results from an imbalance.between The fastest way reactor feedwater input and reactor steam output.
to reduce steam output following a sudden decrease in feedwater flow, and thereby terminate the' reactor level decrease, is to reduce recire, flou.
2.2 IP a RTP controller malfunction exists, THEN take manual control of RPPs.
If a RFP controller has failed, transferring from the auto to manual control mode may restore sufficient feedwater flow. Transferring control from a RPP's controller to its motor speed changer may also prevent a low level scram if feed flow can be increased in time.
O 9204150174 920401 PDR ADOCK 05000352 L P PDR l.
I OT-100 BASES, Rev. 9 l Page 2 of 4
. Call /smk ;
(~ 1 r
1 1 JF 4 stam' condition occurs, tD m~
.4 enter T-101 AMD exit this procedure. ;
This step reminds-the operator that the 01 procedure should be exited and the RPV Control procedure must be entered on a Reactor Low Water Level scram.
3.0 FOLLOW-UP ACTIONS i 3.1- IP level drop was caused by RPP OR Condensate Pump trip, THEN determine cause of trip AND restart pump. ,
The operator should determine the cause of any pump trip which caused the level decrease. The pumps should be
-returned-to service as soon as possible to allow full power operation. ,
3.2 IP level drop was caused by RPP controller malfunction, THEN return RFP to its normal control mode after malfunction is cleared.
Since automatic'RPP control requires the least operator l
attention, efforts should be made to return to the automatic control mode as soon as possible.
3.3 IP level drop was caused by failure of feed flow / steam flow signal, '
AND-level is stabilized at 35 in.,
YHEN consider swapping.to single element control AND restor'ng PW control to automatic until repaire-can be ,
Ma3e. ,
Since automatic RPP control requires the least operator attention, and single element. control does not use feed -
flow / steam flow inputs, on a failure of either of these signals efforts should be made to return to the automatic >
single element mode as soon as possible.
?
' O'I - 10 0 B AS ES , Rev. 9 j l Pago J of 4 I C AH / s n.k 3.4 IP level drop is riot evident on-redundant instrumento, THEN consider possible instrument sensing line failure AND verify actual level utilizing inst runents with Independent sensing lines.
In the event that redundant inst rument s ic not respond correspondingly, it is essential to util.ze independent instruments to determine actual level and thus respond accordingly. An indicated level reduction can occut frca leakage / failure of an instruments variab;e leg, while an indicated level increase can occur trcm 4 eakageffailure cf an instruments reference leg. (Reference Rescd ut ien of Generic Issue 101) 3.5 IP the selected FW 1evel transmitter has failed, TlEN transfer to the alternate level transmitter.
If the selected level transmitter is t alli t.g , it la appropriate to transfer to the alternate . r a nsnti t t e r to stop the level transient and restore reaet.r leve; t ,
norr.al. (Re*erence: Resolution of Generic Isste 101) 3.6 IP recirc runback occurred, TEEN reset the runback per S43.0.B.
Certain plant conditions, specified under OT-100, Verification of Automatic Actions, will cause t t.e reeltc.
pumps to runback to achieve 62% rated ccre flou cr 28i rated speed. When these plant conditicno have be e r.
cleared, the runback logic must be reset i t, order +
.aasr the speed of the recire. M-G :.ets.
3.7 IP third condensate pump is not available, THEN maintain RFP suction pressure above 3u0 psig by limiting Reactor power.
When fewer than three condensate pumps are operating, feed flow must be restricted to prevent tripp;ng the RPPs on low suction pressure. The actual low suction pressure trip point setting of the RTPs is 241 psig. 100 psig has been conservatively chosen as a limit to acccant for possible calibration shift.
V t
l OT-100 BAE9S, Rev. 9 l
' l !
. Page 4 of 4
.. CAH/smk l 1
4.0 VERIFICATION OP AUTOMATIC _ ACTIONS Actions Cond1tions j 4.1 ~ Recirc. reduced to a One RTP ulth less than !
speed corresponding to 20% flow r 62% rated core flow. AND low reac?or level !
IT/.5") .
i 02 One condensate pump tripped ,
with total Feedwater flow i l- greater than 85%
4.2 Recire. runback to 28% of Total reedwater flow icas indicated speed than 20%
Ol low Reactor level (12.5')I of Pump discharge valve less than 90% open.
4.3 REACTOR HI-LO LEVEL alarm 30" 4.4 hram 12.5" t.oup'II isolation 1
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DATE 04/03/92 09150 NRMS RECEIPT ACKNOWLEDGEMENT SEQUENCE # 3924020S20 9
LGS PROCE,DURES - APPROVED ORIGINALS D1$ TAC 00E- OT-U1 TOs NRC UTFSITE PROCEDNQ OT-100 BASES REVISION 009 DATE 04/01/91
( t ! HAVE RECEIVED THE SUBJECT MATERIAL SIGNA 1URit _____________________________________________ DATE _______________
PLEASE RLTURN THIS FORM PRuuPTLY TO LCS ADMIN. SERVICES (LGS-340 )
WITHIN 15 OAYS OF THE ABOVE PRINT-DATE.
, p(if ,
sJ . t II\
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. l I 0
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1
- DATE 04/03/92 09
- 50 NRMS DOCUMENT CONTROL FORM SEQUENCE # 3924020820 i , i LOS PROCEDURES ~ APPROVED ORIGINALS
?!STRCODE 01-U1 00...............................................................................
OLGS S!MULATOR
~~
LOS-LTC 01 C** LGS OFFICE DCC/ WALK 01 !*
OLGS TRAIN CTR LGS-LTC 03 C**NUNEZ, R. LGS-LTC 01 !*
OMAINT/!CC LIBRARY DCC/ WALK G1 !**0PERATIONS SUP. CTR. OCC/ WALK 01 !*
ONRC OFFSITE OUTGOING 01 Ce* PLANT OP. SUP. FAC. OCC/ WALK 01 !*
0 TRAINING C00R0!N. OCC/ WALK 01 !** SHIFT MGR OFFICE OCC/ WALK 01 !*
OCONST BLOG LIB OCC/ WALK 01 !**SUPPT LLOG LIB #1 OCC/ WALK 01 !*
0 CONTROL RM CART LGS DCC/ WALK 02 !*
- SL' PPT BLOG LIB #2 DCC/ WALK 01 !*
- EMERG. OP. FAC. LGS DCC/ WALK 01 C** TECH. SUPP. CTP. LGS DCC/ WALK 01 !*
CINPO OUTGOING 01 !**_______________________________- ____ *,
CLGS LIBRARY LGS /A2-1 01 !**_____ _ _ _ . _
0..............................................z.................................
REQUESTS FOR CHANCES TO THIS O!STRIBUTION LIST MUST BE ADDRESSED TO THE ORGANI2ATION. RESPONSIBLE FOR ORIGINATING THE ATTACHED DOCUMENT (SEE NUCLEAR ,
RELATED DOCUMENT REGISTER (NROR) FOR RESP. ORG.). THE RESP. ORG. WILL !
AUTHORIZE THE LOCAL DAC SUPERVISOR TO MAKE THE NECESSARY CHANGES.
ATTACHED IS-A COPY oft i PROCEDNO OT-100 BASES .,
REVISION 009 OATE 04/01/92 UNCONTROLLE03 LIBRARY, INDO, NUNEZ, R.
l 100 BASES, 101, 101 BASES, 103, 103 BASES, 104 ,
OINFO-OT-100,104 BASES, 112, 112 BASES, 116, 116 BASES 6
O