Letter Sequence Other |
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MONTHYEARML20247K8411988-04-0101 April 1988
Corrected Amends 146,142 & 117 to Licenses DPR-33,DPR-52 & DPR-68,respectively,incorporating Previously Effective Amend Numbers Inadvertently Omitted from Issued Tech Spec Pages
Project stage: Other
ML20247K7951988-04-0101 April 1988
Forwards Corrected Amends 146,142 & 117 to Licenses DPR-33, DPR-52 & DPR-68,respectively.Previously Effective Amend Numbers Inadvertently Omitted from Issued Tech Spec Pages
Project stage: Other
1988-04-01
[Table View] |
Corrected Amends 146,142 & 117 to Licenses DPR-33,DPR-52 & DPR-68,respectively,incorporating Previously Effective Amend Numbers Inadvertently Omitted from Issued Tech Spec Pages| ML20247K841 |
| Person / Time |
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| Site: |
Browns Ferry  |
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| Issue date: |
04/01/1988 |
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| From: |
NRC |
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| To: |
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| Shared Package |
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| ML20247K802 |
List: |
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| References |
|---|
| TAC-00176, TAC-00177, TAC-00178, TAC-176, TAC-177, TAC-178, NUDOCS 8909220030 |
| Download: ML20247K841 (6) |
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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217C2111997-09-11011 September 1997
Amend 249 to License DPR-52,providing Changes Required to Implement Improved Power Range Neutron Monitor Sys, Designated by Licensee as Group a Changes
ML20247K5171988-09-23023 September 1988
Amends 155,151 & 126 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Revising Tech Spec Tables 3.2.B & 4.2.B to Add Instrumentation Used to Trip & Isolate HPCI & RCIC Sys on Low Steam Supply or High Turbine Exhaust Pressure
ML20247K8411988-04-0101 April 1988
Corrected Amends 146,142 & 117 to Licenses DPR-33,DPR-52 & DPR-68,respectively,incorporating Previously Effective Amend Numbers Inadvertently Omitted from Issued Tech Spec Pages
ML20246M1461988-02-29029 February 1988
Amends 145,141 & 116 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Making Primary Containment Integrity Definition Operability Requirement & Action Statement More Appropriate & Consistent
ML20214H8511987-05-13013 May 1987
Amends 133,129 & 104 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Changing Tech Specs Re Rod Worth Minimizer & Rod Sequence Control Sys Requirements
ML20062A4171978-09-29029 September 1978
Amend 43 to Lic DPR-33;mod Conditions for Oper & Surveillance Equip
ML20247Q0301974-06-28028 June 1974
License DPR-52,authorizing Operation at Reactor Core Power Levels Not in Excess of 33 Mwt
1997-09-11
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18039A8871999-09-30030 September 1999
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, to Update TS License Conditions.Ts Change TS-381,consists of Administrative Revs That Delete License Conditions That Have Become Outdated,No Longer Applicable or Are Redundant
ML18039A8781999-09-28028 September 1999
TS Change 399 to Licenses DPR-52 & DPR-68,increasing Allowable Leakage Rate Criteria for MSIVs & Requesting Exemption to Portions of 10CFR50,App J.Rev 0 to Rept 2100918-R-002 Encl
ML18039A8221999-07-28028 July 1999
TS Change 398 to License DPR-58,providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys
ML18039A7981999-06-0303 June 1999
Application for Amends to Licenses DPR-52 & DPR-68,reducing Allowable Value Used for Reactor Vessel Water Level - Low, Level 3 for Several Instrument Functions
ML20196A9491998-11-19019 November 1998
Suppl 1 to 970602 Application for Amends to Licenses DPR-33, DPR-52 & DPR-68,allowing Continued Plant Operation with Single Recirculation Loop in Svc
ML18039A5011998-09-0808 September 1998
TS Change 354 to License DPR-52,providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys
ML18039A4981998-09-0404 September 1998
Application for Amends to Licenses DPR-52 & DPR-68,amending Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses,Per NRC Bulletin 96-003
ML18039A4771998-08-14014 August 1998
Supplemental Application for Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change TSs for Instrument Calibration Surveillance Frequencies.Proposed Changes Decrease Frequency of once-per-cycle by Substituting 24 Months for 18 Months
ML18039A4071998-06-26026 June 1998
Application for Amends to Licenses DPR-52 & DPR-68,revising TS Section 3.4, Rcs.
ML18039A3901998-06-12012 June 1998
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs
ML20249A5641998-06-10010 June 1998
Supplemental Application for Amend to Licenses DPR-33,DPR-52 & DPR-68,revising ITS Section 5.0 Re Administrative Controls
ML18039A2691998-03-16016 March 1998
Suppl 1 to TS Change 384 to Licenses DPR-52 & DPR-68, Allowing Units 2 & 3 to Operate at Uprated Power of 3458 Mwt Representing Power Level Increase of Five Percent
ML18039A2591998-03-0303 March 1998
Application for Amends to Licenses DPR-52 & DPR-68,revising TS 393 Re pressure-temperature Curve Update
ML18039A2201997-12-30030 December 1997
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS Change 395,removing non-conservatism Associated W/Lco 3.5.C, RHR Svc Water & Eecw.
ML18038B9581997-10-0101 October 1997
Application for Amends to Licenses DPR-52 & DPR-68, Consisting of TS Change 384,allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt.Proprietary Rept Re Power Uprate Safety Analysis,Also Encl.Rept Withheld
ML20217C2111997-09-11011 September 1997
Amend 249 to License DPR-52,providing Changes Required to Implement Improved Power Range Neutron Monitor Sys, Designated by Licensee as Group a Changes
ML18038B9041997-06-19019 June 1997
Application for Amends to Licenses DPR-52 & DPR-68, Requesting Temporary TS Change to Provide one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities
ML20137U1081997-04-11011 April 1997
Suppl 1,TS Change 353S1 to Licenses DPR-33,DPR-52 & DPR-68, Revising Existing Custom for Units to Include Changes Associated W/Implementation of Pr Neutron Monitor Upgrade & to Incorporate Changes
ML18038B8321997-03-12012 March 1997
Application for Amends to Licenses DPR-52 & DPR-68, Consisting of TS Change 376,extending EDG Allowed Outage Time
ML20132B7301996-12-11011 December 1996
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS-386,increasing TS 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity.Rev 3 to J11-02761SRLR Rept Encl
ML20117P3311996-09-15015 September 1996
Application for Amend to License DPR-68 to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations
ML20117G7081996-08-30030 August 1996
Application for Amend to Licenses DPR-33,DPR-52 & DPR-68, Eliminating License Condition 2.C.(3) on Thermal Water Quality Stds
ML20113B1851996-06-21021 June 1996
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising SLMCPR & Bases Description of RHR Removal Suppl Fuel Pool Cooling Mode
ML20112G3811996-06-0606 June 1996
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs
ML20117H5131996-05-20020 May 1996
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS Change 373,revising TS to Implement Guidance of GL 87-09 & NUREG-1433,Rev 1
ML20108D8911996-05-0303 May 1996
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Withdrawing Amend 219,temporary TS 343T,RV Water Level Instrumentation & Amend 228,temporary TS 347T,250 Volt DC Control Power Supply Sys AOT for Unit 2 Only
ML20107F9591996-04-14014 April 1996
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Revising Minimum Required Number of Operable Rv Water Level Trip Sys During Period That RCS Instrument Line Excess Flow Check Valve Surveillance Tests Being Performed
ML20096C4341996-01-10010 January 1996
Suppl to TS Change Request 364 to Licenses DPR-33,DPR-52 & DPR-68,revising TS to Implement 10CFR50,App J,Option B, Performance Based Testing.Suppl Incorporates Word Door to Note in SR 4.7.A.2.g.Corrected TS Encl
ML20095E4051995-12-0808 December 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of Proposed TS Change TS-364,revising TS Section 4.7.A to Implement Recent Rule Change to 10CFR50,App J to Incorporate Option B for Containment Leak Rate Testing
ML20093B0451995-10-0202 October 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS-371 Bases Sections 3.5.A & 3.5.B, Core Spray Sys & Residual Heat Removal Sys & 3.5.C, RHR Svc Water & Emergency Equipment Cooling Water Sys
ML20092F3191995-09-13013 September 1995
Application for Amend to License DPR-68 Changing TS Table 4.2.B & 4.2.C to Delete Requirements to Perform Daily Instrument Checks for Steam Supply Low Pressure & Turbine Exhaust Diaphragm High Pressure
ML20086G6951995-07-10010 July 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68 Revising TS Base Section 3.7.A/4.7.A to Clarify Method of Determining Operability of Drywell to Suppression Chamber Vacuum Breakers
ML20085K4731995-06-16016 June 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS to Allow TIP Sys to Be Considered Operable W/ Less than Five TIP Machines Operable
ML20084T9631995-06-0202 June 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Clarifying Definition of Operability for RHRSW Sys Standby Coolant Supply Capability & Revising Instrument Numbers in Tables 3.2.F & 4.2.F for Instruments Upgraded
ML20085D5891995-06-0202 June 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms,Per GL 94-02.Proprietary GE Rept NEDC-32433P Encl.Rept Withheld
ML20083M0351995-05-11011 May 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Reflecting Interim Addition of Scram Pilot Air Header Low Pressure Trip Function on Unit 3
ML20080J2771995-02-23023 February 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS-348 Re Residual Heat Removal Sys Interlock Installation
ML20077K2171995-01-0404 January 1995
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Proposing Changes to Ts,By Revising Applicability & SR for Irm,Aprm High Flux (15% Scram) & APRM Inoperative Trip Functions
ML20077A5081994-11-15015 November 1994
Application for Amends to Licenses DPR-33,DPR-52,DPR-68, DPR-77 & DPR-79,deleting Audit Frequencies & Requirement to Perform Radiological Emergency Plan & Security Plan Audits from TSs
ML20149G2391994-10-0707 October 1994
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising Surveillance Requirements for Plant Operation W/ Inoperable Diesel Generator
ML18037A8741994-05-11011 May 1994
Application for Amend to License DPR-52,consisting of TS Change TS-347T to Temporarily Extend AOT of TS 3.9.B.8 While TVA Replaces Batteries & Associated Hardware That Supply 250 Volt Dc Control Power to Units 1 & 2 Shutdown Boards
ML20065H2201994-04-0404 April 1994
Suppl 1 to TS-322 to Licenses DPR-33,DPR-52 & DPR-68, Eliminating Reactor Scram & Main Steam Line Isolation Functions Associated W/Msl Radiation Monitors
ML20065E3651994-03-31031 March 1994
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Extending Load Line Limit & Revising Rod Block Monitor Operability Requirements & Deleting Specific Value for Rated Reactor Loop Recirculation Flow Rate
ML20065F2511994-03-31031 March 1994
Request for Amend TS-319 to Licenses DPR-33 & DPR-68, Lowering Trip Level Settings for HPCI & RCIC Steam Line Space Isolation Instrument Channels
ML20065E3841994-03-30030 March 1994
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TSs Re Analog Transmitter/Trip Sys,Level 1 Reactor Water Level Setpoint & Various Calibr Frequencies
ML20065D4931994-03-29029 March 1994
Request for Amend TS-340 to License DPR-68,revising TS to Add Operability & SRs to Support Unit 3 480-volt Load Shed Logic Sys Being Added by Design Change
ML20059C4981993-12-23023 December 1993
TS Change 346 to Licenses DPR-33,DPR-52 & DPR-68, Incorporating Recommendations for Snubber Visual Insp Intervals Contained in GL 90-09, Alternative Requirements for Snubber Visual Insp Intervals & Corrective Actions
ML20057G2511993-10-12012 October 1993
Request for Amend TS-320 to Licenses DPR-33,DPR-52 & DPR-68, Deleting Existing RWCU Sys High Temp Detection Switches from Tables 3.2.A & 4.2.A & Adding New RWCU Sys Temp Loops for Unit 3 & Clarifying Tables 3.2.A & 3.2.B for Units 1,2 & 3
ML20057E8621993-10-0707 October 1993
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS 313,adding High Range Primary Containment RMs & Recorders to Tables 3.2.F,4.2.F & TS Section 6.9.2 in Response to NUREG-0737,Item II.F.1.3
ML18037A4761993-09-30030 September 1993
Request for Amend TS-312 to Licenses DPR-33,DPR-52 & DPR-68, Removing SDV Air Header Pressure Trip Switches Scram Function from Unit 2 TS & Clarifying Description of SDV High Water Level Bypass in RPS for Units 1,2 & 3
1999-09-30
[Table view] |
Text
- _ - _ _ _ __ _ - _ _ _ _ _ - _ - _ - _ _ _ _ _ _ . - _ _ - _ _ _ - . ___ _ -______-_ ___ ._-__ . _ _ _ _ - - _ _ - _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ - - _ - _ .
l- 3 k
3.7/4.7: CONTAINMENT SYSTEMS
\ LIMITING CONDITIONS FOR OPERATION SURVF.ILLANCE REQUIREMENTS 3.7.C. Secondary Containment j 4. If refueling zone secondary I containment cannot be l maintained the following p conditions shall be met:
- a. Handling of spent fuel and I all operations over spent fuel pools and open reactor wells containing fuel shall be prohibited.
- b. The standby gas treatment system suction to the refueling zone will be blocked except for a controlled leakage area sized to assure the achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water-in all three reactor zones.
D. Primary Containment Isolation Valves D. Primary Containment Isolation Valves
- 1. When Primary Containment 1. The primary containment Integrity is required, all isolation valves isolation valves listed in surveillance shall be Table 3.7.A and all reactor performed as follows:
coolant system instruttent line flow check valves a. At least once per shall be OPERABLE except as operating cycle the specified in 3.7.D.2.
OPERABLE isolation valves that are power operated and automatically initiated shall be tested ,
for sinulated automatic initiation and closure times.
- b. At least once per quarter:
,(1) All normally open power-operated isolation valves (except for the main steam line power-operated isolation valves) shall be fully closed
.g 3.7/4.7-17
- E' 8909220030BBO40b59 ADOCK 050
- Amendment No. 145 PDR P
DR Cor'rected : 4/1/88 .
____________-___-__-___-_____-A
3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS- /
3.7.D. Primary Containment Isolation 4.7.D. Primary Containment Isolation Valvee Valves 4.7.D.1.b (Cont'd)
(2) With the reactor power less than 75%, trip main steam isolation valves individually and verify closure time.
- c. (Deleted)
- d. At least once per operating cycle, the operability of the reactor coolant system instrument line flow check valves shall be verified.
- 2. In the event any isolation valve 2. Whenever an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE, reactor power INOPERABLE, the position of at operation may continue provided least one other valve in each at least one valve in each line line having an INOPERABLE valve having an INOPERABLE valve, is shall be recorded daily.
OPERABLE and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. The INCPERABLE valve is restored to OPERABLE status, or
- b. Each affected line is isolated by use of at least one deactivated containment isolation valve secured in the isolated position.
- 3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l l
BFN 3.7/4.7-18 Arendment NO. If5, 146 Unit 1 Corrected: 4/1/88 l
l
.____-____________-___-__________-___-______a
3.9/4.7 CONTAINMENT SYSTEMS
.g LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j 3.7.C. Secondary containment
-4. If refueling zone secondary ,
containment cannot be l maintained the following j conditions shall be met:
- a. Handling of spent fuel and {
all operationr over spent fuel pools and open reactor wells containing fuel shalli be prohibited. l
- b. The standby gas treatment system suction to the rafueling zone will be !
blocked except for a l controlled leakage area l
sized to assure the -
achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water in all three reactor zones.
D. Primary containment Isolation valves D. Primary Containment Isolation Valves
- 1. When Primary Containment 1. The primary containment Integrity is required, all isolation valves isolation valves listed in surveillance shall be Table 3.7.A and all reactor performed as follows:
j coolant system instrument line flow check valves '
- a. At least once per shall be OPERABLE except as operating cycle the specified in 3.7.D.2.
OPERABLE isolation valves i
that are power operated and automatically I
initiated shall be tested f for simulated automatic initiation and closure times.
- b. At least once per quarter:
I j (1) All normally open power-operated isolation valves (except for the main steam line power-operated isolation valves) shall be fully closed and reopened.
gTV y 3.7/4.7-17
)
Amendment No. 141 Corrected: 4/1/88 j
3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS ..
3.7.D. Primary Containment Isn1stion 4.7.D. Primary Containment Isolatiet.
l- Valves Valves i
4.7.D.1.b (Cont'd)
(2) With the reactor power less than 75% trip main steam isolation valves individually and verify closure time.
- c. (Deleted) 1
- d. At least once per operating.
cycle, the operability of the reactor coolant system instrument line flow check valves shall be verified.
- 2. In the event any isolation valve 2. Whenever an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE, reactor power INOPERABLE, the position of at opacation may continue provided least one other valve in each at least one valve in each line line having an INOPERABLE valve having an INOPERAPLE valve, is shall be recorded daily.
OPERABLE and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. The INOPERABLE valve is restored to OPERABLE status, or
- b. Each affected line is isolated by use of at least one deactivated containment isolation valve secured in the isolated position.
- 3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
BFN 3.7/4.7-18 Amendment *.0. 142, 142 Unit 2 Corrected: 4/1/88 a____-____ -___. ._ _ - . _ - -
t
(*g 3.7/4.7- CONTAINMENT SYSTEMS i
LIMITING CD'NDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i4 l- 3.7.C. gecondary Containment 4 If refueling zone secondary containment cannot be maintained the following conditions shall be met.
- a. Handling of spent fuel and all operations over spent fuel pools and open reactor wells containing fuel shall be prohibited,
- b. The standby gas treatment system suction to the refueling zone will be blocked except for a controlled leakage area sized to assure the achieving of a vacuum of f
at least 1/4-inch of water {
and not over 3 inches of water in all three reactor f zones, f
D. Primary Containment Isolation Valves D. Primary Containment Isolation valves
- 1. When Primary Containment 1. The primary containment Integrity is required, all isolation valves isolation valves listed in surveillance shall be Table 3.7.A and all reactor performed as follows: l coolant system instrument line flow check valves a. At 1 bast once per shall be OPERABLE except as operating cycle the specified in 3.7.D.2.
OPERABLE isolation valves that are power operated and automatically initiated shall be tested {
for simulated automatic '
initiation and closure times.
- b. At least once per quarter:
1 (1) All normally open power-operated 1 isolation valves '
(except for the main steam line power-operated isolation valves) shall be fully closed g{y 3.7/4.7-17 Amendment No. 116 Corrected: 4/1/88 l
1
_---_-__--__-_____--_----------------------------a
F 3.7/4.7- CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPE]ATION SURVEILLANCE REQUIREMENTS /
3.7 D. Primary Containment Isolation 4.7.D. Primary Containment Valves Isolation Valves 4.7.D.i.b (Cont'd) ~
(2) With the reactor power less than 75%,
trip amin steam isolation valves individually and verify closure time.
- c. (Deleted) .
- d. At least once per operating cycle. the operability of the reactor coolant system instrus.snt line flow check valves shall be verified.
- 2. In the event any isolation valve 2. Whenever'an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE, reactor power INOPERABLE, the position of at operation may' continue provided least one other valve in each at least one valve ia each line line having an INOPERABLE valve having an INOPERABLE valve, is shall be recorded daily.
OPERABLE and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. The INOPERABLE valve is restored to OPERABLE status, or
- b. Each affected line is isolated by use of at least one deactivated containment isolation valve secured in the isolated position.
- 3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall {
be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
BFN 3.7/4.7-18 Amendment NO. II6, 117 Unit 3 Corrected: 4/1/88
_ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _