IR 05000315/1993003

Enforcement Conference Repts 50-315/93-03 & 50-316/93-03 on 930108.Areas Discussed:Violations & Areas of Concern Identified During Insp & Corrective Actions Taken or Planned by Licensee

ML17329A756
Person / Time
Site:	Cook
Issue date:	01/15/1993
From:	Hartland D, Isom J, Jorgensen B, Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17329A755	List: IR 05000315/1993003 ML17329A754
References
50-315-93-03-EC, 50-315-93-3-EC, 50-316-93-03, 50-316-93-3, NUDOCS 9301250068
Download: ML17329A756 (48)

Text

U.S.

NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-315/93003; 50-316/93003 Docket No. 50-315; 50-316 License No. DPR-58; DPR-74 Licensee:

Indiana Michigan Power Company 1 Riverside Plaza Columbus, OH 43216 Meeting'Conducted:

January 8,

1993 Meeting At:

Region III.Office, Glen Ellyn, Illinois Type of Meeting:

Enforcement Conference Inspection Conducted:

Onsite at D.

C.

Cook Nuclear Plant, December

through 18, 1992.

Inspectors:

JAL)'Do Seni or s >

Inspector ar an Resident Inspector

5'eviewed By:

. L. Jorgen n, Chief Reactor Projects Section 2A

/8 i Approved By: W..

S afer Chief Reactor Projects Branch

ate ate ate ate Meetin Summar Enforcement Conference on Januar

1993 Re ort No. 50-315 93003 Areas Discussed:

A review of the apparent violations and areas of concern identified during the inspection, and corrective actions taken or planned by the licensee.

The. enforcement options pertaining to the apparent violations were also discussed with -the licensee.

9301250068

'730115 PDR ADOCK 05000315

PDR

DETAILS Persons Present at Conference E.

E. Fitzpatrick, Vice President, Nuclear Operations A. A. Blind, Plant Hanager G. A. Weber, Plant Engineering Superintendent J.

S.

Wiebe, Safety and Assessment Superintendent J.

R.

Sampson, Operations Superintendent S. A. Richardson, Production Supervisor R. J. Sieber; Shift Supervisor P.

G. Schoepf,. Project Engineering Superintendent S. J.

Brewer, Nuclear Safety and Licensing Manager D. Halin, Nuclear Licensing Manager R. Rickman, Outage Manager

.

W.

G. Smith, Jr., Chief Nuclear Engineer M. Ackerman, Nuclear Licensing Engineer K. J. Newell, System Engineer R.

B. Bennett, Senior Engineer U.S. Nuclear Re ulator Commission Re ion III A. B. Davis, Regional Administrator, RIII W. L. Forney, Deputy Director, Division of Reactor Projects, RIII W.

D. Shafer, Chief, Reactor Projects Branch 2, RIII E.

R. Schweibinz, Senior Project Engineer, RIII J.

Luehman, Office of Enforcement (via telephone)

W.

M. Dean, Licensing Project Manager, NRR (via telephone)

J.

A. Isom, Senior Resident Inspector, RIII D. J. Hartland, Resident Inspector, RIII R. L. Bywater, Reactor Engineer, RIII B. A. Berson, Regional Counsel, RIII R.

W. DeFayette, Chief, Enforcement and Investigations Coordination Staff, RIII G. H. Smith, Enforcement Specialist, RIII D. H. O'Neal, General Engineer (Intern)

Enforcement Conference An enforcement conference was held in the NRC Region III office on January 8,

1993.

This conference was conducted as.a result of the preliminary findings of the inspection conducted on December 3 through 18, 1992, in which apparent violations of NRC regulations and license conditions were identified.

Inspection findings are documented in Inspection Report No. 50-315/92022; 50-316/92022, transmitted to the licensee by letter dated December 31, 1992.

The purpose of this conference was to (1) discuss the apparent violations, causes, and the licensee's corrective actions; (2) discuss

several areas of concern; (3) determine if there were any escalating or mitigating circumstances; and (4) obtain any information which would help determine the appropriate enforcement action.

The licensee's representatives did not contest any of the apparent violations and were in agreement with the NRC's understanding of the areas of concern.

However, with regard to Violation 50-316/92022-03, the licensee's representatives and the NRC agreed that failure to identify and correct the adverse trend of lube oil inventory for the Unit 2 "AB" emergency diesel generator (EDG) was a root cause of the EDG lube oil trip.

Failure to correct the before and after pump seal

~

leakage was a contributing cause.

Therefore,.the NRC will utilize the failure to correct the adverse trend of lube oil inventory as its basis for consideration of enforcement action for this apparent violation.

The licensee's representatives described the events which led to the apparent violations, including root causes and corrective actions taken and planned.

A summary of the licensee's corrective actions is included in pages 41 through 43 of the attached handout that the licensee provided at the conference.

Included among these were immediate actions to restore operability of the 2 "AB" EDG and verify operability of the other EDGs..

Also included were longer-term actions to review/revise procedures, provide additional guidance to personnel for performance of tours, review the work request process, perform an engineering review of the lube oil gauge design adequacy, review other level gauge installations, and increase the frequency and scope of level alarm

'operational checks.

The licensee also addressed the safety significance of the EDG inoperability.

At the concl'usion of the meeting, the licensee was informed that they would be notified in the near future of the final enforcement action.

Attachment:

As stated

NRC ENFORCEMENT CONFERENCE DIESEL GENERATOR LUBE OIL TRIP JANUARY 8, 1993

MANAGEMENTCONCERN ISSUE RECEIVED HIGH LEVEL OF UPPER MANAGEMENTATTENTION

~ Thorough Irrimediate Actions

~ Included Inspection of Bearings-

~ Notification to Operating Shifts

~ Checking of Other Lube Oil Tanks

~ Established Interface With Resident Inspector

~ Multidisciplinary Task Force

~ investigate Event

~ Determine Root and Contributing Causes

~ Operations Task Force

~ Review Tour Practices

~ Review Data Sheet Practices

AGENDA I. INTRODUCTORY REMARKS II. BACKGROUND

~ A, System Description

~ B. Chronology III. ROOT AND CONTRIBUTING CAUSES IV. ISSUES AND CORRECTIVE ACTIONS

~ A. Process Related Issues

~ B. Equipment Related Issues

~ C. Work Scheduling Issues V. SAFETY AND LICENSING SIGNIFICANCE

~ A. Time of Inoperability

~ B. Safety Significance

~ C. Factors for Consideration Vl. CONCLUDING REMARKS

Diesel Generator Lube Oil System Function r

~ To provide clean, warm lube oil to the Emergency Diesel Generator bearings and valve gear during operation and while in standby servic tlute

~eaa te aeVal

~tee I~

Veaavt vlf

~DD ere I~

~Iter e

'Vel

~rUUI I~I er

~ te% IUV Ik

~III~ Ieae

+5@.('aa

~

~IIr U tee ~

~ar Ital~

~

D r

Late I~

fee IU UD ~ ~

~ eaer D

~ I'tt eeet

~ er te'e$

$

I>>tQ Iere aev a teel ea ella'

I ee

~UI

~ eat

~ a II~

eet IDe

~ Ieara tactl II~

~tear I veeet

~Iel U

'Ut ~

\\ ~/ gA ter

~Dt UUI tew

~Ct-K

<<

DO->--

~ II~

~ 'r ee

~ear

<<e UII~

ENcRGENCY OlESEL GENERATOR LUBE OIL SYSTEM

J Diesel Generator Lube Oil

.

System Instrumentation Sump Tank Level Gauge (LLI-210)

~ Local level indication (200 to 700 Gallon)

~ Pressure Guage Sump Tank Level Alarm (LLA-110)

~ Controi Room annunciator on low (395 Gal.)

or'igh (650 Gal.) level

~ lVlagnetrol Displacement Level Alarm

. System Pressure Indicator (LPI-220)

~ Local Pressure Indicator (0-100 PSIG)

'ow Pressure Alarm (LPA-220)

~ Control Room annunciator if oil pressure drops to 35 PSlG Low Pressure Shutdown (LPS-220)

~ Control Room annunciator (Oil Pressure Extreme Low) and engine trip (during non-safety related operation) ifoil pressure

. drops to 25 PSIG for 25 second TO ENGINE DRIVEN PUMP MAGNETROLDISPLACEMENT-TYPE LM LEVELALARMSYSTEM 110 LSX 702 LLI 210

'l3.375"

~ ~

10.5" I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I45.625'

I I

I I

I 42lI 37lI 24 II 23 5" 10 5" INITIAI FILL (750 GALLONS)

Hl LEVELALARM ( 650 GALLONS)

ADMINMIN LEVEL ( 405 GALLONS)

LOW LEVELALARM ( 395 GALLONS)

FOOT VALVE SUCTION (135 GALLONS)

2.5" SUCTION 75" uNETO PUMPS

Instrumentation Taps TO UPPER VALVEGEAR LPI LPA LPS LPX 220 220 220 220 TO CAMSHAFT TO CRANKSHAFT FROM

'DUPLEX STRAINER LPI 220 LOCALNDCATOH(0.100 PQG)

-6 LPA 220 LOWPRESSURE ALAI'-COHTROL ROOQ t25 PSN))

LPS.220 LUBE ON. PRESSURE EXTRA LOWALA)II-COHTROL ROOil 4 EHGNE SWTDOWH (25 PS6 WAS SEC TNT DELAY)

Event Description DG2AB Lo-Lo Lube Oil Pressure Trip

~ September 28, 1992

~ Routine Operations Department Surveillance

~ Engine Start

~ Lo-Lo Lube Oil Pressure Trip Due To Low Lube Oil Sump Tank Level

~ Engine Declared Inoperable

Immediate Corrective Actions

.~ Oil Level Check

~ Replenished Oil Supply

~ Repaired B&APump Leak

~ Verified Oil Supply on Other Engines

~ Checked Bearing Clearances

~ Inspected 44 Bearing

~. Initiated Root Cause Investigation

Root Cause Investigation DG2AB Lo-Lo Lube Oil Pressure Trip

~ Investigation Team

~ System Engineer

~ Safety 8 Assessment

~ Operations

~ l8 C Engineer

~ Project Engineering

~ Actions Taken

~ Reviewed Operations Tour Data

~ Reviewed Surveillance History

-

~ Reviewed Maintenance History

~ Reviewed Level Gauge Design Change Package

~ Interviews with Operations, Maintenance, Environmental

~ Field Observations

800 737 GAL 2 AB LUBE OILTANKINDICATEDLEVEL

~ INDICATORLEVEL 600 HIGH LEVELALARM-650 400 200 WEEKLY TANK LEVEL 0 LOW LEVEL ALARM-395 ACTUALDIP STICK READING 309 127 MSRMNTS 4/29 DATE 9/28 SURVEIL-LANCES OIL SAMPLES 5/5 5/'t 9 6/25 7/24 8/9 8/17 9/t 6 LOWOIL PRESS TRIP 9/28 OTHER EVENTS AR WRITTEN ON 5/9 COMMUNICATION 6/3 2 6/1 8 WALKDOWN B8 A PUMP FROM ENV. ENG.

TO PLAN SEAL LEAK ON LEAKRATE LEAKREPAIRS

ROOt CauSe Failure to Identify Adverse Lube Oil Level Trend The Effect...

Precluded Timely Response

~ Oil Suppiy Not Replenished

~ Oil Leak Not Investigated/Corrected

~ Eventual Loss of Adequate Oil Supply

Contributing Causes

~.Failure To Recognize Parameter Outside Acceptance Criteria

~ Pump Seal Leakage

~ Level Alarm Failure

~ Level Indicator Problems

500 ESTIMATEDTlME OF tNOPERABlllTY 9/2 THROUGH 9/28 400 LOAL RM-395 ADV!N> '='"1 - ~~0')

300 INDICATED LEVEL TREND 200 MIN START - 212 100

8/26 FOOT VALVE-135 ACTUAL LEVEL TREND 9/2 9/9 9/1 6 9/23 9/28 Assumes constant 9.5" level difference

PROCESS RELATED ISSUES

~ FAILURE TO IDENTIFYADVERSE LUBE OIL LEVEL TREND

~ FAILURE TO RECOGNIZE PARAMETER OUTSIDE.

ACCEPTANCE CRITERIA

~ FOLLOW-UP PREVENTIVE ACTION

DATA COLLECTION/TRENDING PROCESS OVERVIEW DATACOLLECTIONlTRENDING.

~ OPERATIONS PROCEDURES

- 4030 AND 5030 SERIES

~ OPERATOR,TOURS

DATACOLLECTION/TRENDING PROCESS OVERVIEW TOTAL PLANT PARAMETERS AVAILABLE PARAMETERS WHICH ARE COLLECTED, MONITORED, AND TRENDED IN PLANT PROCEDURES (e.g., 4030 AND 5030 TEST PROCEDURES)

NTROL ROOM RMS, AND CORDERS CO ALA PARAMETERS COLLECTED, MONITORED, AND TRENDED BY

%q(yP A OVERLAP BETWEEN

. SURVEILLANCES AND.TOURS PARAMETERS COLLECTED, MONITORED, AND TRENDED DURING THE PERFORMANCE OF ROUTINE PLANT TOURS

FAILURE TO IDENTIFY ADVERSE TREND CONTRIBUTING FACTORS

~ INSUFFICIENT TREND DATA AVAILABLETO UNIT SUPERVISOR

~ ACCEPTANCE CRITERIA NOT STATED IN DATASHEET SHORT TERM CORRECTIVE ACTIONS

~ DATASHEET REVISED

~ INCREASED FREQUENCY OF DATACOLLECTION

OMI 5030 ATTACMNENT l2 UNIT 2 LURE OIL ANO EHC TANK LEYEL Test I 073 ATTACHKllT7I AY/DATE:

IN TURbINE L.O. TK.

ST F.P.T. L.O. TX.

EST F.P.T.

L.O. TX.

AST F.P.T.

CONTROL FLUID TK EST F.P.T.

CONTROL FLUID TK IN cosTRDL FLUID Tx.

Ubf OIL HOLDINC TX.

EN L.O. TX.

DIESEL L.O. TK.

DIESEL L.O. TX.

N/A N/A N/A N/A

) 7.5 7. 5 VED

"I b f<,0 7.5'9, 7.8 Q,O Q,o 7.S r/A FR gy 5AT S.F 7:S-4X 43 N/A N/A N/A N/A CS-5 CNbeENTS oi'I

~o Qc 4+

Y/DATE

.S.

REYIEM R%QRO TO OPERATIONS ACC ONE NEEX AFTER LAST ENTRY FR SAT Gw J

CS-5

UNIT 1 LUBE OILAND EHC TANKLEVELS OHI~

AlTACHMENT<<1.

Test <<~

ATTACHMENT<<1 Minimum Lever

~

I I

I

~ 2.5

-

2.5'ay Date Makr Tur5tle LO. Tank East FPT LO. Tank West FPT LO. Tank SUN MON

"-/-1/ P '"7'~/.

-/0

/

I THU rc/3r/~

FRI

/I /93 SAT r /2/53 Cs-s,t

Mah Contrct ~ 5'

Fled Tank N/A N/A Lube Ol Hok51ng Tank New LO.

Tank AB Diesel LO. Tank

'3 Z

9/

z's" 807.+

- 5O7.4 rg7 7

~'S" 5 p7.$

5 07.

Cs-5 CD Dkrset LO. Tank Operator's Intr@Is 2'l" CZ9 C

II

~

~ I

'2't" r

p'Mlrimum Level pertakrs to normal operations.

Comments Season:

4'~8.

Cs-30 U.S. Review SUN MON Tglg WED QDV/f>

AZ >I>l~ 4/k 1HU i/51/fl FRI SAT I /I /T5 I/Z/

<<5 5IaI FORWARD TO OPERATIONS ACC ONE WEEK AFTER LAST ENTRY J cs-5

Pa0e 81 at 180 Rev. 10, CS4, 8. 12. 30

FAILURE TO RECOGNIZE PARAMETER OUTSIDE ACCEPTANCE CRITERIA CONTRIBUTING FACTORS

~ OPERATORS NOT FULLY AWARE OF ACCEPTANCE CRITERIA

~ ACCEPTANCE CRITERIA NOT EFFECTIVELY COMMUNICATED

FAILURE TO RECOGNIZE PARAMETER OUTSIDE ACCEPTANCE CRITERIA SHORT TERM CORRECTIVE ACTIONS

~ OPERATIONS MEMORANDU IVI

~ ESTABLISHED SHIFT REVIEW TEAM

~ ASSISTANT SHIFT SUPERVISOR

~ TOUR OPERATORS

~ DAILY"DIP STICK" READINGS

~ DATASHEET REVISED TO SHOW ACCEPTANCE CRITERIA

FOLLOW UP. PREVENTIVE ACTIONS

TOUR PROCEDURE WALKDOWN

'ON-LICENSED.OPERATORS, LICENSED OPERATGRS, SUPERVISORS, REVIEW OF TOUR PROCEDURES CRITICAL PARAMETERS

~ ACCEPTANCE CRITERIA AND COIVIMUNICATION METHOD

~ TRENDING

"POCKET" VERSION OF TOUR PROCEDURES

.OPERATIONS POLICY ON TOUR ROTATION

PROCESS RELATED ISSUES SUMMARY

~ EXISTING PROCESS FOR DATA COLLECTION, MONITORING, AND TRENDING EFFECTIVE

~ SYSTEM ENGINEER PROGRAM HAS ENHANCED TRENDING PROCESS SHORT TERM CORRECTIVE ACTIONS PREVENT SPECIFIC EVENT

~ BROAD-BASED FOLLOW-UP ACTIONS

EQUIPMENT RELATED ISSUES

f Ilgwu

! '%~><i~f

~ '

~

~2

~ee C3

~ ~

Level Alarm Failure Investigation

~ Disassembly and Inspection

~ Maintenance History Search

~ Industry OE (NPRDS) Search

~ Preventive Maintenance Practice Conclusion

~ Available Information Indicated No Deficiencies In Level Alarm Maintenance Program Actions

~ Verify Operation of Level Alarms on Other 3 Engines

~ Increase Frequency of Operational Checks From 2RO to )RO

~ Full Operational Check

Level Indicator Problems

.

Investigation

~ Design

.

~ Non-standard Instal lation/Sample Tap

~ Final Design Raised Gauge Elevation Above Tank Penetration

~. Appropriate Reviews/Approvals Obtained

~ Post Modification Test

~ Bench, Calibration

~ Post Installation Leak Inspection

~ Field Observations

~ Sampling Operation Introduced Air into Sensing Line

. Positive Bias on Indicated Level

Level Indicator Problems (Continued)

Corrective Actions

~ Gauges Taken Out of Service on All Engines

~ Daily Dipstick Readings Being Performed/Trended Preventive Action

~ Level Indicating System Re-Design Under Evaluation

.Other Actions

~ Review Other Level Gauge Installations for Similar Deficiencies

~ Shared Sensing Line

~ Gauge Elevation

~ Low Pressure Systems

~ Consider Programmatic Actions Based on Outcome of This Review

IDENTIFICATION, P RIORITIZATIONAND SCHEDULING OF BBcA PUMP SEAL LEAK

~ Material Condition Deficiency

. Identified on May 9, 1992 and Action Request Generated to Correct

~ Action Request Reviewed and Prioritized for Next Scheduled AB Diesel Generator Outage

~ Action Request Planned and Scheduled for October 19, 1992 Train Outage

WORK CONTROL PROCESS CONCLUSIONS

~ Material Condition Deficiency Properly Identified And Processed

~ Action Request Promptly Reviewed And Properly Prioritized

~ Corrective Maintenance Appropriately Scheduled For Next Diesel Generator Outage

ON-GOING ENHANCEMENTS TO THE WORK CONTROL

.

PROCESS

~ Implementation of a Plant Wide 12-Week Work Schedule Cycle

~ Creation of a Work Classification Organization

~ System Engineer Involvement in the Work Control Piocess

J TIME OF INOPERABILITY

DIESEL ESTIMATED TO BE'INOPERABLE SEPTEMBER 2, 1992

~ Average Oil Leak Rate

~ Uncovering of Foot Valve

~ Measured Drawdown

~ TECHNICALSPECIFICATION REQUIREMENTS

~ 2 Diesels Required, Modes -1-4

~ 1 Diesel Required, Mode 5 UNIT IN IVIODE 5 AT TIME OF DISCOVERY (9/28)

~.IVlode 5 Entered September

~ Diesel Inoperable 23 Required Days

~ 2CD Diesel Operable

SAFETY SIGNIFICANCE EVENT HAD LOW SAFETY SIGNIFICANCE

~ Offsite Power Continuously Available

~ Offsite Sources

~ Alternate 69 KV Source

~ Redundant Diesel Operable

~ Procedures for Repowering Equipment from Unit)

~ Decay Heat Load Lovr

~ Following Refueling Outage-36

P ROBABILISTICRISK ASSESSMENT MINIMALINCREASE IN CORE DAMAGE FREQUENCY

~ 6.26 E-05 Per Reactor Year Baseline

~ 6.46 E-05 per Reactor Year wl23 Days Diesel inoperability

~ Increase of only 3'/o

~ Minimal Impact Due to:

~ 3 Offsite Power Sources

~ Reliability of Redundant EDG

FACTORS FOR CONSIDERATION MANAGEMENTINITIATIVEIN IDENTIFYINGROOT CAUSE OF EVENT AND TAKING CORRECTIVE ACTIONS

~ Thorough Immediate Actions

~ Multidisciplinary Task Force

~ Operations Task Force

~ Enhancements to Work Control Practices Already Underway

FACTORS FOR CONSIDERATION (Continued)

CORRECTIVE ACTION PROMPT AND EXTENSIVE

~ Immediate Actions to Restore Operability

~ Short Term Changes to Lube Oil, Data Collection

~ Changes to Operations Tour and Data Review Practices

~ Level Gauges Removed From Service

~ Review of Other Level Gauge Installations for Similar Deficiencies:

~ Increased Frequency and Scope of Level Alarm Operational Checks

r E

FACTORS FOR CONSIDERATION (Continued)

EVENT HAD LOW SAFETY SIGNIFICANCE

~ Availabilityof Offsite Power

~ Redundant Diesel

~ Minimal Increase in Core Melt Frequency ALLREPORTING REQUIREMENTS SATISFIED

~ Resident Kept Informed of Developments

'

LER Complete and Thorough ABILITYTO RECOGNIZE LOW LUBE OIL CONDITION HAIVlPERED BY EQUIPMENT PROBLEMS

~ Low Level Alarm

~ Level Gauge

~

~

I Cc SUMMARYOF CORRECTIVE ACTIONS EDG INOPERABLE LONGER THAN TECH ALLOWABLEOUTAGE TIME ACTION STATUS Check Lube Oil Level in All Diesels Completed (September 28)

Lube Oil Tank Level Restored to Normal Operating Range Completed prior to return to operable status Lift Ch'eck Performed on EDG Bearings Completed prior to return to operable status Inspection of AllVisible Bearing Surfaces for Abnormal Wear Completed prior to return to operable status Bearing ¹4 Pulled and inspected Completed prior to return to operable status Replacement of Defective Before and After Pump Seal

'I Repair of Level Alarm Completed prior to return to operable status Completed prior to return to operable status Revision of surveillance test procedures for monthly EDG operability test to include recording of lube oil level

Completed

~,

~

j, Zla 'eS SUMMARYOF CORRECTIVE ACTIONS FAILURETO PROMPTLY IDENTIFYAND CORRECT OIL LEAK ACTION STATUS initiate Daily Dipstick Readings of Lube Oil Tank Complete Engineering Review of Lube Oil Gauge Design Adequacy (Gauges Tagged Out)

Complete Review of Work Request Process for Possible Enhancements to Ensure Detailed information, Required for Proper Work Prioritization, is Provided Complete Issue Memo to Shifts Complete Increase Frequency and Scope of Level Alarm Operational Checks to Refueling Outage Frequency Next Refueling Outage Verify Operation Of Level Alarms On Other 3 Diesels During Next Scheduled Outages Review Other Level Gauge Installations for Similar Deficiencies

March 15, 1993

STATUS SUMMARYOF-CORRECTIVE ACTIONS FAILURE TO INCLUDE ACCEPTANCE CRITERIA FOR EDG LUBE OIL LEVEL ACTION Revise Lube Oil Inventory Log Sheet to Complete Include Minimum Allowed Level and Require Recording of 7 Consecutive

.

Readings Establish a Tour Assignment Policy to Require, Whenever.Possible, an Operator to be Assigned a Plant Tour=

for a Long Enough Period to Establish Personal Ownership of that Tour January 31, 1993 Review Tour Procedures for Appropriate Critical Parameters, Acceptance Criteria, Communication Method, and Trending Method June 30, 1993 All Tour Operators wilt Complete a

Review of the Tour Procedures, Including Walkthroughs March 31, 1993 Issue a Tour Guide, Sized to Fit in a Pocket, to be Used for Reference Only by the Tour Operators

March 31, 1993

APPENDIX

Major Components Sump Tank

~ 754 Gallon Capacity Engine Driven Pump

~ Positive Displacement, Gear-type, 441 GPM at 514 RPM and 140 F lube oil, casing relief set at 75 PSIG Full-flowFilter

~ Single steel vessel containing 34 individual, disposable 10 micron filtering cartridges 3-way Bypass Valve

~ 9 individual thermostatic elements operating in parallel Cooler

~ Shell and tube, two pass tube side (ESW),

single pass shell side (oil)

Duplex Strainer

~ 2 individual steel vessels with a manual transfer valve. Each vessel contains 3-100 mesh screens and is capable of handling full system flow.

B&APump

~ Positive Displacement, Gear-type, 90 GPM at 75 PSIG, runs continuously

Major Components (Continued)

Heater Pump

~ Positive Displacement, Gear-type, 6 GPM, runs only when engine is in standby Heater-

~ 7.5 KW, 5.6 GPM capacity Bypass Filter Pump

~ Positive Displacement, Gear-type, 39 GPM, runs only when engine is in standby Bypass Filter

~ Single-steel vessel containing 18 individual disposable 3 micron filtering cartridges Upper Valve Gear Oil Control

~ Two independent flowpaths, each containing a solenoid valve and a pressure regulating valve, that control the flow of oil to the upper valve gear.

While the engine is in standby, oil is supplied to the valve gear for 2 minutes every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Oil is supplied to the valve gear continuously while the engine is running.

46