Text

Rev 20 to Fermi 2 Technical Requirements Manual, Vol 1
	ML20236P924
Person / Time
Site:	Fermi
Issue date:	06/10/1998
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20236P915	List: ML20236P913; ML20236P924;
References
	PROC-980610, NUDOCS 9807170208
	Download: ML20236P924 (22)
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Fermi 2 l

Technical Requirements Manual Volume I Detroit l Edison ARMS-INFORMATION DTC: TMTRM l File: 1754 DSN: TRM VOL1 l Rev: 20 Date:06/10/98 Recipient 9807170208 980611 PDR l

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FERMI 2 - TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES Page *

Revision Eagg Revision 1 19 3/4 6-1 19 2 19 3/4 6-2 19 i 20 3/4 6-3 19 ii 20 3/4 6-4 19 lii 20 3/4 6-5 19 iv 20 3/4 6-6 19 v 20 3/4 6-7 19 3/4 6-8 19 TECHNICAL REQUIREMENTS 3/4 6-9 19 3/4 6-10 19 1-1 19 3/4 6-11 19 1-2 19 3/4 6-12 19 1-3 19 3/4 6-13 19 1-4 19 3/4 6-14 19 2-1 Blank 3/4 6-15 19 3/4 01 19 3/4 6-16 19 3/4 0-2 19 3/4 6-17 19 3/4 0-3 19 3/4 6-18 19 3/4 0-4 19 3/4 6-19 19 3/4 0-5 19 3/4 6-20 19 3/4 0-6 19 3/4 6-21 19 3/4 0-7 19 3/4 6-22 19 3/4 1-1 Blank 3/4 6-23 19 3/4 2-1 Blank 3/4 6-24 19 3/4 3-1 19 3/4 6-25 19 3/4 3-2 19 3/4 6-26 19 3/4 3-3 19 3/4 6-27 19 3/4 3-4 19 3/4 6-28 19 3/4 3-5 19 3/4 6-29 19 3/4 3-6 19 3/4 7-1 Blank 3/4 3-7 19 3/4 8-1 19 3/4 3-8 19 3/4 8-2 19

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3/4 3-16 20 3/4 12-1 Blank 3/4 3-17 20 5-1 Blank l 3/4 3-18 20 6-1 Blank j 3/4 3-19 20 3/4 3-20 20 CORE OPERATING LIMITS REPORT 3/4 3-21 20 COLR 6, Revision 1 3/4 3-22 20 3/4 3-23 20 Notation Page 3/4 3-24 20 1 1 3/4 4-1 Blank 2 1 3/4 5-1 Blank 3 1 TRM Vol. I LEP-1 REV 20 06/98 l

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16. 1.

FIRE PROTECTION LIMITING iCONDITIONS FOR OPERATION AND SURVEILLANCE REOURFMENTS 9A.6-1 3-9A.6-2 6 9A'.6-3 5 9A.6-4 5 9A.6-5 TRM REV 17

.9A.6-6 TRM REV 17 9A.6-7 TRM REV 17 9A.6-8 6 9A.6-9 TRM REV:17

-9A.6-10 6a 9A.6-11. 6a 9A.6-12 6 9A.6-13 6 9A.6-14. 3 9A.6-15 3 9A.6-16 3 9A.6 3 9A.6-18 3 9A.6-19 6' 9A.6-20 3 9A.6-21 TRM REV 7-9A.6-22 3 9A.6-23 TRM REV 8 9A.6-24 TRM REV 8

.9A.6-25 TRM REV 15 9A.6-26 TRM REV 15 9A.6-27 3 9A.6-28 3 TRM Vol. I LEP-2 REV 20 06/98

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FERMI 2 - TECHNICAL REQUIn n NTS MANUAL l

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TABLE OF CONTENTS - VOLUME 1 Section and Title Pace

INTRODUCTION..........................-................ 1 SECTION 1 DEFINITIONS TR 1.0 ' DEFINITIONS...............................

1-1 -

SECTION 2- SAFETY LIMITS

~ TR 2.0.- SAFETY LIMITS AND. LIMITING SAFETY SYSTEM SETTINGS.................................. .2-1 SECTION 3 APPLICABILITY TR.3/4.0 APPLICABILITY........................... 3/4 0-1 SECTION 3.1'

- TR 3/4.3.1 REACTIVITY CONTROL' SYSTEMS........ ... 3/4 1-1 SECTION 3!2 ~

.TRe3/4.3.2 POWER DISTRIBUTION LIMITS............. 3/4 2 SECTION'3.3 TR 3/4.3 INSTRUMENTATION TR 3/4.3.1 Reactor Protection System Instrumentation....................... .

3/4 3-1 TR 3/4.3.2 Isolation Actuation Instrumentation... 3/4_3-4 4

TR 3/4.3.3. : Emergency Core Cooling System Actuation Instrumentation....................... '3/4 3-8

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-TR 3/4.3.7.2 Seismic Monitoring Instrumentation.. 3/4 3-11

..L TR 3/4.3.7.3 Meteorological _ Monitoring y . Instrumentation................... 3/4 3-15

'TR 3/4'.3.7.7 Traversing.In-Core-Probe' System..... 3/4 3-19

'TR 3/4.3.7'8 . . Chlorine Detection System........... 3/4 3-21

'TR 3/4.3.7.10 . Loose-Part Detection System.........

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.SECTION 3.4 TR 3/4.4 -REACTOR COOLANT SYSTEM ,.................. 3/4 4-1 SECTION-3.5 TR 3/4.5 . EMERGENCY CORE COOLING SYSTEMS.......... 3/4 5-1 SECTION 3.6 TR 3 /4 . 6 CONTAINMENT SYSTEMS......................

.TR 3/4.6.1 Primary' Containment...................

TR ' 3 /4 . 6 . 2 Depressurization Systems..............

TR 3/4.6.3< Primary Containment Isolation, Valves.. 3.6-1 1 TR 3/4.6.4- -Vacuum.Hi.............................

TR 3/4.6.5 Secondary Containment.................

TR 3/4.3.6- Primary. Containment...................

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TABLE OF CONTENTS (Cont'd) - VOLUME 1 I

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Section and Title Pace 1

j SECTION 3.7 '

TR 3/4.7 PLANT. SYSTEMS........................... 3/4 7-1 TR 3/4.7.1 Service Water Systems.................

TR 3/4.7.2 Control Room Emergency Filtration System l TR 3/4.7.3 Shore Barrier Protection..............

TR 3/4.7.4 Reactor Core Isolation Cooling System.

TR 3/4.7.5 Snubbers..............................

TR 3/4.7.6 Sealed Source Contamination...........

TR 3/4.7.9 Main Turbine Bypass System and Moisture Separator Reheater..........

TR 3/4.7.10 Reserved.............................

TR 3/4.7.11 Appendix R Alternative Shutdown Auxiliary Systems....................

SECTION 3.8 TR 3/4.8 ELECTRICAL SYSTEMS..... ................

TR 3/4.8.1 AC Sources ............................

TR 3/4.8.2 DC Sources............................

TR 3/4.8.3 Onsite Power Distribution Systems.....

TR 3/4.8.4 Electrical Equipment Protective Devices - Motor Operated Valves Thermal Overload Protection........... 3/4 8-1 SECTION 3.9 TR 3/4.9 REFUELING OPERATION..................... 3/4 9-1 TR 3/4.9.1 Reactor Mode Switch...................

TR 3/4.9.2 Instrumentation .......................

TR 3/4.9.3 Control Rod Position..................

TR 3/4.9.4 Decay Time............................

TR 3/4.9.5 Communications........................

TR 3/4.9.6 Refueling Platform....................

TR 3/4.9.7 Crane Travel - Spent Fuel Storage Pool TR 3/4.9.8 Water Level - Reactor Vessel..........

TR 3/4.9.9 Water Level - Spent Fuel Storage Pool.

TR 3/4.9.10 Control Rod Removal...................

TR 3/4.9.11 Residual Heat Removal.................

SECTION 3.10 TR 3/4.10 SPECIAL TEST EXCEPTIONS................ 3/4 10-1 TR 3/4.10.1 Primary Containment Integrity........

TR 3/4.10.3 Shutdown Margin Demonstrations.......

TR 3/4.10.4 Recirculation Loops..................

TR 3/4.10.5 Deleted..............................

TR 3/4.10.6 Training Startups....................

TRM Vol. I ii REV 20 06/98 l

w FERMI 2 - TEr'wI m REQUIREMENTS MANUAL i TABLE OF CONTENTS (Cont'd) -

VOLUME 1 Section and Title Page SECTION~3.11

.TR 3/4.11 RADIOACTIVE EFFLUENTS.................. 3/4 11-1 TR 3/4.11.1 Liquid Effluents.....................

SECTION 3.12 TR 3/4.12 DELETED................................

SECTION 5 DESIGN FEATURES TR 5.0 DESIGN FEATURES........................... 5-1 TR 5.1 SITE......................................

TR 5.2 CONTAINMENT...............................

TR 5.3 REACTOR CORE..............................

TR 5.4- REACTOR COOLANT SYSTEM....................

TR 5.5 METEOROLOGICAL TOWER LOCATION.............

'TR 5.6 FUEL STORAGE..............................

TR 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.......

SECTION 6 ADMINISTRATIVE CONTROLS TR 6.0 ADMINISTRATIVE CONTROLS................... 6-1 TR 6.1 RESPONSIBILITY.............................

TR 6.2 ORGANIZATION..............................

TR 6.2.1 Offsite and Onsite Organizations........

TR 6.2.2 Unit Staff..............................

TR 6.2.3 Independent Safety Engineering Group....

TR 6.2.4 Shift Technical Advisor.................

TR 6.3 UNIT STAFF QUALIFICATIONS.................

TR 6.5 REVIEW AND AUDIT..........................

TR 6.5.1 Onsite Review Organization (OSRO) .......

TR 6.5.2 Nuclear Safety Review Group (NSRG) . . .. . . .

TR 6.5.3 ' Technical Review and Control............

TR 6.6 REPORSECTIONLE EVENT ACTION...............

TR 6.7 SAFETY LIMIT VIOLATION....................

TR 6.8 PROCEDURES AND PROGRAMS...................

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n FERMI 2 - TErw ICAL REQUIREMENTS MANUAL TABLE OF CONTENTS ~(Cont'd) - VOLUME 1

~Section and Title.....................................Page

- TR 6.9 REPORTING REQUIREMENTS.......................

-TR 6.9.1, Routine Reports.........................

TR 6.9.2 'Special Reports..........................

TR 6.9.3 Core Operating Limits Report............

TR 6.10 RECORD RETENTION.........................

.TR 6.11 RADIATION PROTECTION PROGRAM.............

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TR 6.12 HIGH RADIATION AREA......................

TR 6.13 PROCESS CONTROL PROGRAM..................

TR 6.14 OFFSITE DOSE CALCULATION MANUAL..........

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FERMI 2 TECHNICAL REQUIR N nTS M wUAL TABLE OF CONTENTS (CONT'D) - VOLUME 1 LIST OF TABLES TRM Table Number Title Page 1

1.1 Surveillance Frequency Notation........... 1-3 1.2 Operational Conditions.................... 1-4 3.3.1-2. Reactor Protection S Times...............ystem Response

...................... 3/4 3-2

.3.3.2-3 Isolation Actuation System Instrumentation Response Time............. 3/4 3-5 3.3.'3-3 ' Emergency Core Cooling System Response Times..................................... 3/4 3-9

^3.3.7.2-1 Seismic Monitoring Instrumentation........ 3/4 3-12 4.3.7.2-1 Seismic Monitoring Instrumentation Surveillance Requirements................. 3/4 3-13 3.3.7.3-1 Meteorological Monitoring Instrumentation. 3/4 3-16 4.3.7.3-1 Meteorological Monitoring Instrumentation Surveillance' Requirements................. 3/4 3-17 1

3.6.3-1 Primary Containment Isolation Valves...... 3/4 6-2 3.8.4.3-1 Motor Operated Valves Thermal Overload Protection................................ 3/4 8-2 l

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l. 3 /4 . 3 INSTRUMENTATION 3/4.3.7.2 SEISMIC MONITORING INSTRUMENTATION

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l LIMITING CONDITION FOR OPERATION l

3.3.7.2 The seismic monitoring instrumentation shown in TRM Table 3.3.7.2-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required seismic monitoring instruments inoperable, restore the inoperable instrument to OPERABLE status within the next 30 days.

b. With the above required ACTION and associated completion time not met, initiate a corrective action program document if one has not already been initiated.

SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in TRM Table 4.3.7.2-1.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Technical Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum, and resultant effect upon unit features important to safety.

TRM Vol. I 3/4 3-11 REV 20 06/98

TRM TABLE 3.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS '

INSTRUMENTS AND SENSOR LOCATIONS RANGE ' OPERABLE

1. Active Triaxial System

a. Active Triaxial Accelerometers

1) HPCI Room il g 1

2) Base of RPV Pedestal, In Drywell il g 1 b .- Active Seismic Recording System *

1) Relay Room, Auxiliary Building NA 1**

c. Active Seismic Playback System

1) Relay Room,' Auxiliary Building NA NA

2. Passive Triaxial Peak Shock Recorders

a. HPCI Room *** 1

b. Relay Room, Auxiliary Building *** 1

c. Refuel Floor, Reactor Building _ *** 1

d. Diesel' Generator-Room, RHR Complex *** ' 1

e. Pump Room, RHR Complex *** 1

f. Cooling Tower, RHR Complex *** 1

Including seismic trigger.

- With reactor control room annunciation.

- - Each passive accelerometer has 12 reeds, each monitoring a different frequency. The frequencies correspond to varying accelerations.

The widest range is i 90 g.

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TRM TABLE 4.3.7.2-1 1'.

i SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l-CHANNEL CHANNEL FUNCTIONAL CHANNEL INSTRUMENTS AND SEhfSOR LOCATIONS CHECK TEST CALIBRATION

1. Active Triaxial System

a. Active Triaxial Accelerometers

1) HPCI Room .NA SA R

2) Base of 2PV Pedestal, In Drywell NA SA R

b. ' Active Seismic Recording System

1)' Relay Room, Auxiliary Building ** M(a) SA R

c. Active Seismic Playback System

1) Relay Room, Auxiliary Building M SA -R

, .2. Passive Triaxial Peak Shock Recorders

a. HPCT Room NA NA R

b. Relay Room, Auxiliary Building NA NA R

c. Refuel _ Floor, Reactor Building NA NA R

d. Diesel Generator Room, RHR

-Complex NA NA R

e. Pump Room, RHR Complex NA NA R

f. Cooling Tower, RHR Complex NA NA R

Including seismic trigger.

- With reactor control room annunciation.

l ~(a)Except seismic trigger.

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.TRM Vol. I 3/4 3-13 REV 20 06/98

INSTRUMENTATION BASES' 3 /4. 3. 7. 2. SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulatory Guide 1.12,

" Instrumentation for Earthquakes," April 1974.

Entry into Action b and the initiation of a corrective action program document will cause a determination of deportability to the commission in accordance with the requirements of 10 CFR 50.72 and 10 CFR 50.73.

TRM Vol. I 3/4 3-14 REV 20 06/98

7 3 /4 . 3 INSTRUMENTATION 3 /4 . 3'. 7. 3 ' METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

3.3.7.3 The meteorological monitoring instrumentation channels shown in TRM Table 3.3.7.3-1 shall be OPERABLE.

APPLICABILITY: At all times, b.CLIRN:

a. With less than the required channels OPERABLE in TRM Table 3.3.7.3-1, restore the inoperable channel to OPERABLE status within the next 7 days.

b. With the above required ACTION and associated completion time not met, initiate a corrective action program document if one has not already been initiated.

SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in TRM Table 4.3.7.3-1.

TRM Vol. I 3/4 3-15 REV 20 06/98

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METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE

a. Wind Speed

1. Elev. 10 meters 1

2. Elev. 60 meters 1

b. Wind Direction

1. Elev. 10 meters 1

2. Elev. 60 meters 1

c. Air Temperature Difference

1. Elev. 10/60 meters 1 TRM Vol. I 3/4 3-16 REV 20 06/98

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TRM TABLE 4.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

a. Wind Speed

1. Elev. 10 meters D SA

2. Elev. 60 meters D SA

b. Wind Direction

1. Elev. 10 meters D SA

2. Elev. 60 meters D SA j c. Air Temperature Difference

1. Elev. 10/60 meters D SA l

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-INSTRUMENTATION BASESE 3/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring .

I instrumentation ensures that suf ficient meteorological data are l available for estimating potential radiation doses to the public.

as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the~ recommendations of Regulatory Guide 1.23, l- "Onsite Meteorological Programs, " February,1972.

i Entry into Action b and the initiation of a corrective action program document will. cause a determination of deportability to

.the commission in accordance with the requirements of 10 CFR 50.72

- and 10 CFR 50.73 f

TRM Vol. I 3/4 3-18 REV 20 06/98

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3/4.3 INSTRUMENTATION 3/4'.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION '

3.3.7.7 The traversing in-core probe system shall be OPERABLE with:

a. Five movable detectors, drives and readout equipment to map the core, and-

b. Indexing equipment to allow all five detectors to be calibrated in a common location.

APPLICABILITY: When the traversing in-core probe is used for:

a. Recalibration of the LPRM detectors, and b.* Monitoring the APLHGR, LHGR, MCPR, or MFLPD.

ACTION:

With the traversing in-core probe system inoperable, suspend use of the system for the above applicable monitoring or calibration functions.

SURVEILLANCE REQUIREMENTS 4.3.7.7 -The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use when required for the LPRM

. calibration function.

Only the detector (s) in the required measurement location (s) are required to be OPERABLE.

TRM Vol. I- 3/4 3-19 REV 20 06/98 1

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INSTRUMENTATION

BASES' 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor Core.

The TIP system OPERABILITY is demonstrated by normalizing all probes.(i.e., detectors). prior to performing an LPRM calibration function. Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the reactor core, thus all detectors may not be required to be OPERABLE. The OPERABILITY of individual detectors to be used for monitoring is demonstrated by comparing the detector (s) output with data obtained during the previous LPRM calibration.

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TRM Vol. I 3/4 3-20 REV 20 06/98

3/4.3 INSTRUMENTATION l 3/4.3'.7.8 CHLORINE DETECTION SYSTEM i

LIMITING CONDITION FOR OPERATION 3.3.7.8 Two independent chlorine detectors shall be OPERABLE with their trip setpoints adjusted to actuate at chlorine concentration of less than or equal to 5 ppm.

APPLICABILITY: All OPERATIONAL CONDITIONS.

ACTION:

3. With one chlorine detector inoperable, restore the inoperable detector to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain isolation of all control room emergency intakes by placing the HVAC system in the chlorine mode of operation,

b. With both chlorine detectors inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain isolation of all control room emergency intakes by placing the HVAC system in the chlorine mode of operation.

SURVEILLANCE REQUIREMENTS 4.3.7.8 Each of the above required chlorine detectors shall be demonstrated OPERABLE by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

b. CHANNEL CALIBRATION at least once per 18 months.

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INSTRUMENTATION BASES' l

3/4.3.7.8 CHLORINE DETECTION SYSTEM l

The OPERABILITY of the chlorine detection system ensures that an accidental chlorine release will be detected promptly and the necessary_ protective actions will be automatically initiated to l

provide protection for control room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placad in the chlorine mode of operation to provide the required protection. The detection system required by this Technical Requirement is consistent with the recommendations of Regulatory Guide 1.95, l " Protection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release", Revision 1, January, 1977.

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3 /4 . 3 INSTRUMENTATION 3 /4 . 3 '. 7 .10' LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.10 The loose-part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

I ACTION:

{

a.

With one or more loose-part detection system channels inoperable, restore the inoperable channel to OPERABLE status within the next 30 days.

b. With the above required ACTION and associated completion' time not met, initiate a corrective action

. program document if one has not been already initiated.

SURVEILLANCE REQUIREMENTS

'4.3.7.10 Each channel of the loose-part detection system shall be demonstrated OPERABLE by performance of a:

a. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b '. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.

TRM Vol.'I 3/4 3-23 REV 20 06/98

e INSTRUMENTATION BASES' 3/4.3.7.10 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The ellowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors, " May 1981.

Entry into Action b and the initiation of a corrective action program document will cause a determination of deportability to the commission in accordance with the requirements of 10 CFR'50.72 and 10 CFR 50.73.

TRM Vol. I 3/4 3-24 REV 20 06/98 L '

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ML20236P924

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