Text

Plant,Status Meeting for Units 1 & 2
	ML17228B478
Person / Time
Site:	Saint Lucie
Issue date:	04/18/1996
From:	; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17228B477	List: L-96-109, Forwards St Lucie Nuclear Plant Status Meeting for Units 1 & 2; ML17228B478;
References
	NUDOCS 9604300241
	Download: ML17228B478 (149)
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ST. LUCIE STATUS MEEllNGAGENDA FOR APRIL 18, 1996 9:00 AM. SSB ROOlyI 4011 NIN CONDENSER WATERBOX PIPING MAINTENANCERULE STORES INVENTORYREDUCTION W. Bohlke J. Scarola D. Denver M. Snyder L. Rogers IHE 96-030 RCS LEAKAGE E-PLAN REPORTING J. Porter K. Heffelfinger FFD AUDIT

SUMMARY

MODIFICATIONCONTROL C. Burton J. Holt A. Pell S/G INSPECTION RX VESSEL/CORE SUPPORT BARREL INSPECTION G. Boyers K. Mayhew/

G. Pustover MAINGENERATOR INSPECTION PRESSURIZER CODE SAFETY VALVES R. Ball J. Price HUMAN RESOURCES OPERATOR ATTRITION 8c ASSUMPTIONS OPERATIONS MAINTENANCE SYSTEMS/COMPONENTS ENGINEERING CORRECTIVE ACTIONS QUALITYASSURANCE LICENSING SERVICES MATERIALS L. Morgan B. Frechette N. Motley C. Wood D. Denver B. Dawson W. Bladow E. Weinkarn C. Burton D. Quilty/

T. Kreinberg

OPERATING REPORT REC

Unit 1 Equivalent Availability DAILYEQINVALKNTAVAILABIUTY 51 DaYS on4ne es or 4/l6$95

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MonfhiyAverage EAFsg551)k Lost Generation SertiH Loss

~1st 4S94 Tats oats D$0$

~$502 Ba)rn rn a Not)tta)~ Cln)dlt rrasa snv EOUIVALENTAVAILABILIIYFACTOR UNIT1 100

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ssk Sr,e 75 4

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Unit2 Equivalent Availability OAILYEQUIVALENTAVAILAEIUTY 98 O070 ocv7cne es ot 4/15/96 00 xc

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In 4WSS enxn 4IS/00 4l1ccce xntl90 4nel90 4/10I00 4h850 ldaCC007AVOI09e EAFe95.7800 Last Gene/Stion SIVVIILoss 410

~177 77$

4000 4070 4101 4177 4107 41S1 Vvbi>>Velve 7en VAcccctxxptline cepex, vcceccxx pipins ceps.

Vececixxc pfpia cepex.

cccxcxec pccno cepec.

vnceecx p'ceo cepev.

Veccctxx p'Ciine cepar.

Reason Oeccci en 0 IxxvEcexn Pcnsedcce Cepccey ei 000 Cln/

EQUIVALENTAVAILABILflYFACTOR UNIT2 100

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75 Jxcactx CXLO

~ ~ ~ ~ ~ ~ ~

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~n Feb

AUTOMATICREACTOR TRIPS Jeff West - Operations Good Legend

~Actual Target 4

I I-3 O

0R 2

2 2

2 Target ~ 1 0

0 0

Oct Dec Jan '98 Mar May Date Jul Sep Nov Data Source: Jeff West

CONDENSER XATERBOX PIPING

ST. LUCIE UNIT 2 CONDENSER WATERBOXCORROSION I.

Current Situation 2A1 Waterbox: Out-of-service for repairs.

II.

Problem Statement:

Two through-wall holes identified in the 2A1 and 2B1 outlet water boxes on 4/9/96.

III.

Background:

~

84" diameter stainless steel components installed upstream and downstream the condensers during the 1995 refueling outage.

~

The installation coupled stainless steel with the carbon steel waterboxes and cast iron piping. The failures were in the carbon steel waterboxes.

IV.

Root Causes:

The failure mechanism for the through-wall holes and wall thinning was galvanic corrosion.

The galvanic corrosion resulted from the coupling of dissimilar metals (stainless and carbon steels) in a conductive, corrosive environment.

The large surface areas of the new stainless steel components and the small surface areas in the carbon steel (pinholes in the coating system) caused the corrosion rates to be extremely high.

~

The modified cathodic protection system installed concurrent with the stainless steel components did not adequately protect the carbon steel waterboxes.

~

The Design Review Process was also inadequate in that it did not identify this problem.

~

Post Modification Testing indicated less than adequate protection but the cognizant engineer did not believe change was necessary.

5

IV. Repairs

~

Areas of wall degradation have been weld repaired to restore wall thickness.

~

Breaches of the carbon steel coating system have been repaired.

~

Corroded portions of the baffle plates, installed at the condenser discharge, have been repaired or replaced.

V. Corrective Actions:

Ac ions Com le ed:

The internal surfaces of the S.S. components have been coated (as much as practical) to reduce the area of the stainless steel.

Additional anodes and reference cells have been installed in the proximity of the S.S. components in the 2A1 &. 2B1 loops.

\\

Temporary power has been provided to the 2B1 cathodic protection anodes.

An independent industry expert has provided input corrective actions.

I Testing has been conducted to determine the required number of anodes and proper operating levels of current.

Actions ln ro ress:

Installation of additional independent rectifiers and controllers will be

,implemented when parts are available.

An independent consultant is to prepare the Unit 1

&. 2 long term design

packages, Corrective Actions are being incorporated into the Unit 1 design scheduled for implementation during the upcoming refueling outage.

Future Actions:

~

ln future efforts, outside engineering resources will be utilized to support extraordinary engineering problems.

~

Use FPL Staff as a second opinion or alternate outside sources for design review of these problems.

IMPLEMENTATIONSCHEDULE FOR THE MAINTENANCERULE 1996 Updated 4/17/96 LEGEND:

xxxxxxxxxxxxxxx xxxxxmcolxxxxx xxxxxxxxxxxxxxx xxxxxxxxx II Description Person Responsible Date Comptete

= Scheduled

= Working

= Complete rea e pe Panel Member flock Ctmfno II Expert Panel Review Ol Perform Criterfe Cfmtno II Tees rrrrQ nants felts 0 n

.repose'rIItel ttntrrftl

< r.:.:::

ntrfr Perform Second ITR Of Mafnt Rufe fgrn emAtSt.Lucre II JAN 10 JAg 31 FEB 16 FEB 28 MAR 16 MAR22 MAR 31 APR 7 APR 30 JUL 10 PMSERSujouNTRV2.PRE

TASKS COMPLETED FOR MAINTENANCERULE SINCE 10 JANUARY PROGRAM UPGRADES MRule procedure revised wrt QA ITR, NUMARC 93-01, Turkey Point New system Performance Criteria wrt technical basis SYSTEM OWNERS MRule 'system owners'dentified System owners and supporting component engineers trained on MRule-Expert Panel members identified and trained on MRule ROOT CAUSE Trained system owners on RCA (Used INFO Good Practice techniques}

Developed site procedure on 'how to'or Root Cause Analysis Implemented SCE Guideline for ERT and RCA teams.

HISTORICALREVIEW 3 year review of SSC performance to ID potential a(1)s System Owner involvement BEN Limerick MRule Peer review NEI MRule conference (CE peer discussions)

NEI peer review at PSL

REVISED IMPLEMENTATIONMAINTENANCERULE SCHEDULE 1996 Updated 4/t7/96 LEGEND:

XXXXXXXXXXXXXXX XXXOOOQOQOIXXXX XXXXXXXXXXXXXXX XXXXXXXXX

//

Descrlptfon Person Responsible Date Complete

= Scheduled w= Working w Complete Issue 5'I Qtr Maht Rute Report Snyder II Expert Panel Review a(I)s And Goals Snydsr II Expert Panel Review Perform Criteria Snyder II System Falufe Notebook Clmlno II Maht Rute Imput For POD Welch>>ski II Expert Panel Member Notebook Clmlno II Site TVFor Increased MR Awareness Snyder II Site Newsletter For Msinl Rute Awareness Watch>>ski II Contractor Orlenlagon Snydsr II Reformat System Oescripthn Contractor II oot xla e Malnt Risk Assess mania V/ncent II MR Termhofogy Roslers Made 8, Phced Cfmho II ADM17.08 Procedure Upgrades Walchoskl II QA Peer Review At SONGs Watcheskl Il Mahl Rule Tralnhg For Management Snyder II e

SSE Scophg Contractor II Compiet ewew OIPSL Maintenance Rule alcheskl II oveop rogram For Structures Engineering II s

For Exctuding Systems From MR Contractor II neo as

~na ITROf Mahtenac>>

Rute QA/Snyder II Document Bash Ol Perform Criteria Snyder II Expert Panel Review Of PCP Snydsr II Program Compliance Plan-Finatrze Snyder II pgra e

a t

Rufo Quarterly Report Format Walcheskl II perl ans Review Ol Performance Bash Snyder II ncorpora o Scophg Sys Oescdptfon Contractor II r

nt DNerence ln Sys Oesaiption Contractor II Mshlenance Rute Tie To TEDB Cimlno II Revise System Engheer 4 Initai Training Watch>>ski II Document Ba s

For Sys Not In Maht Rule Snyder II Train/Inform Gen Pop Of Pfsnt MahlRuie Tralnhg II Create System Health Report Snyder II Per/orm First Perlodh Assessment Snyder II APR16 APR 30 MAY16 MAY30 JUN 15 JUN 30 JUL 30 AUG 30 FaUSERSV/IAINTRU3.PRE

REMAININGTASKS FOR MAINTENANCERULE IMPLEMENTATION RESOURCES FOR FINALMRVLEIMPLEMENTATION Dedicated

- 3 SCE engineers

- 1 ERIN contract engineer Supporting

- 3 SCE technicians

- System Owners

- Expert Panel members

- Engineering (Civil, PSA)

PROGRAM IMPROVEMENTS Expand scope of systems in MRule Update scoping documentation System Descriptions improvements On-line risk assessments COKIINUEDIMPLEMENTATION General plant population awareness - Flyers, posters, TV, newsletter, post outage training Evaluate a(1)s w/ System Owners 8c Expert Panel Documentation - System Failure History, Expert Panel notebooks Periodic Assessment BEN April

- ERIN contractor (MRule experience at Diablo Canyon, Limerick, Peach Bottom)

May

- Turkey Point critique of PSL MRule program

- San Ono&e QA ITR exchange June

- St. Lucie QA ITR July

- Palo Verde NRC MRule baseline inspection 4

10

STORES I ORY REDUCTION

'INVENTORYREDUCTION

SUMMARY

~

Review $8,700,000 Identi6ed as DME Without Plant Review (Rogers-indicator)

~

Walkdown Warehouses to Identify Additional Large DME Items (Rogers)

~

Inventory Bench Mark (Rogers)

~

Identify Problem Areas and Apply Additional Resources (Rogers - valve & I&C parts)

~

Auction $ 14 MillionApproved DME Material July/November 1996 (Quilty - indicator)

~

Track Effectiveness ofReviewed DME Material Removal form Site (Quilty - indicator)

LAR4-17-96 dmesumry

14

~

12 4

~

NUCLEAR MATERIALSMANAGEMENT WEEK ENDING APRIL 12, 1996 DME MATERIALREMOVED FROM SITE GOOD 10 8

W 8

4..

TARGET > ZERO DOLLARS BY IO/Se I

I I

I 1

1 g

m' 10 8,8.7 8.1 DME VERIFICATIONREVIEW GOOD 7

e.

8.1 TARGET ~ZERO DOLLARS BY 10/88 o

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R o,

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o4

~Io IO UPDATEDAND SUBMITTEDBY: MATERIALSMANAGEMENT-N. QUESADA DME.ÃLS

IHE 96-030 RCS L GE E-P REPORTING

Unit 2 RCS Invento Loss Greater than Technical S ecifications Problem: An Unusual Event was declared on March 31 at 1430 after Operations discovered and secured an approximate 30 GPM inventory loss from the CVCS System.

Root Cause:

-ReliefValve V2531 lifted to the HUTs due to high pressure in the ion exchanger supply header.

-The high back pressure was the result ofV2382 being in a throttled position versus fullyopen.

-V2382 was not adequately confirmed to be in the fullopen position after a routine de-lithiating evolution.

Corrective Actions:

-Add a pressure gage to the ion exchanger inlet header to improve method ofconfirming proper system operation.

-Review plant policy on use and maintenance ofvalve position indicators.

-Revise operating procedures to improve understanding ofproper methods for valve position verification.

CVCS I.ETOOWN

/SHUIOOWH COOLIHOf

~CY 220 IP

~CV 22010 LSTDOWH SACK fAKNUI%COHNOL VALVE PISVP.fILT2II 2h U2 OHLY TPIIC IIAOLIHT lOCAlflOW WOCATNI LCV2 I ISO ACE IS LSTDOWH ISQLAllPI NISI~

la 00 VALVSS OWKWA SYSTEM PLOW INST fITOSI ICS LCVSI LS TOOWH LSVSL COHThOL VALVS TOfLASH TQSI RGHX'. REGENERATIVE HEATEXCHANGlIR LOHX:LETOOWN HEAT EXCHANGER LSTDOWIISTAAWIT PUfllf flLTSA

$ 1

( lOOP l SEAL e

P~T5fI~ I cI fIII

Fault Tree Un@2 Rl:.S..lwontory Loco of 3Q1i98

'APPARENT RCS INVENTORYLOSS WAS CALCULATEDTO SE -1.B GPM, THEN -30 GPM FOLLOWINGADELITHIATING EVOLUTION'VCS LEAKAGEIN RAB RCS GE IN CONT ENT Rubd out baaed on CW Sump, QT, RDT levela INTERSYSTEM LEAKAGE

- Nut level IncreauI-30 GPM.

- Leakage ceaaed vrLIXRS bypaaaad EX E

Waiukwn Preaaure Teat RELIEF VALVEFLOW

-ERDADS conltmN TO HUT tV2531)

-2MO GPM leak SPENT INTANK OF S

Preaaure Teat RE VALVE S

LOW Bench Teat SaUafactory DRAINC CTION HEADE EDT/CDT Preaaure Teat CHARGE P PACIONO Wa~

TKRO ALL LEAKAO H~INT Pfeaaure Teat PACKING GE Preaaute Teal RELIEF V LEAKAGE Bench Teal SaUafactory HIGH SYSTEM PRESSURE ATV2631 VGCH KAGE Preaaure Teat IN Preaaure Teat KlhP ION CHANGER Hlhp S INER VALVEPOSITIONINO

- OPSlog-

- OburvaUon on return to aervke

- No atarm received OPS Iog

-ObaewaUon on return to aarvke MIS EO VALVE - V2382 reported aa 2-3 turne from fullopen OPE ACR ERROR

- No credible falure mode for HlhP

-ObaarvaUon on return to aervk>>

PR MECH NO SYP ALVE VAL TOR

- Allvatvea contlnned to cydo aat.

roeRanvacE/Faut neo os&

6-0 E-Plan Event 1

tl Conflicting Views ofthe Leakage Situation:

1.

Tech Spec RCS leakage detection systems did not indicate leakage and it was thought to be isolable.

2.

PSL historically has not considered itRCS leakage ifitis known to be isolable.

Telecon with NRC on 4/4/96, PSL stated:

1.

The UE declaration was based on valid criteria because leakage did exist, but procedural criteria were not clear.

2.

Declaration was not timely.

3.

Procedures willbe changed to ensure consistency.

4.

We willinstill culture "ifunsure...you are in the E-Plan".

Corrective Actions:

1.

Reinforce management expectations.

2.

Develop procedural guidance to define RCS leakage.

3.

Evaluate the training program E-Plan content and frequency on event declaration, timeliness and communications with oK-site agencies.

4.

Revise EPIP EALfor Unusual Event on RCS leakage.

6.

Revise RCS Inventory Balance Data Sheet 1.

FFD AUDIT S

RTNE F

R DUTY/ACCE AUTHORlZATIONAUDlT Summary:

The audit acknowledged that we are in compliance with regulations, but have numerous opportunities to improve our program and comply with our internal implementation documents.

Findings regarding site implementation activities:

Finding 1. Follow up testing for personnel in the conditional access program has not been administered consistently.

Response

Ihe tracking mechanism for the site FFD coordinator will be improved to require monthly vermcation of program compliance. A cross check by Security supenrision will be performed.

Finding 2. The implementation of random testing has been inconsistent. Some people selected for testing have not been tested, and the reason for not testing has not been properly documented.

Response

The random test process will be improved to veriiythat the selected employee is on site, before any test form is issued. Adherance to documentation requirements will be improved through revision of the test form, and a routine review of test forms by Security Supenrision.

Finding 3. The Site FFD Coordinator did not have a 3 year background check perfomed.

Response: This check has now been performed. The mechanism for ensuring compliance with this program requirement in the future is under review.

17

MODIFIC'ATION CO OL

ModTiication Control Improvements Actions Complete Reestabiished Configuration Control group Revised Procedures to implement NP - 703 Generated 1996 Top 20 List Generate 1996 top 30 list Initiate Real Time Engineering List Present Initiatives Generate 1997 Top20/30 List Future Initiatives Improve PCM closeout process 18

OUTAGE PREP TIONS

IMPROVEMENTS/ACTIONS OUTAGEMANAGEMENT r

vement Complete Unit 2 Refueling Outage Self-Assessment/Critique and identify additional Complete improvement actions Establish contingency plans for significant outage activities:

Core Baricl Examiiiation Westinghouse SG Tube Plugs Pressurizer Code Safety Valves Reactor Vessel 0-Ring Replacements Main Generator In@ection 4/23/96 4/23/96 4/23/96 4/23/96 4/23/96 Issue Opemtions and Maintenaiice procedure upgrades Due:

Maine Target:

3/29/96 Complete 4/26/96 Improve Outage Management:

~

Complete the addition of Schedulers for future outage planning Re-Establish use of Critical Mainteriance Management Process Institute outage work scope controls forUnit 1 1996 Outage Assess other plants'M processes Upgrade site-wide scheduling system Complete Complete Complete 4/20/96 8/30/96 19

17APR96 Span 04:00 16:00 624:00 112:00 120:00 120:00 671:00 30:00 281:00 12:00 42:00 30:00 24:00 628:00 18:00 30:00 30:00 24:00 67:00 240:00 80:00 240:00 09:00 120:00 240:00 08:00 80:00 60:00 16:00 66:00 64:00 84:00 16:00 32:00 103:00 01:00 APRIL Turbine and Rx Shutdown Hang Turbine Clearances Draft Outline PSL Unit 1 Refueling Outage 1996.

47 Days JUNE Generator Disassembly Perform Initial Generator Test Gen, Stator Wed e Re lacement LiftTest Main Steam Safety Valves Begin Cooldown Safeguards Test Complete Cooldown and Depressurlze HP Overhaul and Blade Rin Re iacement Gen. Winding Module Installation Generator Final Stator Testing Generator Reassembly Return Main Steam and Draw Vacuum SG Ins ection and Tube Plugging Rx Disassembly Polar Crane Load Test Complete Rx Disassembly LiftRx Head and Inspect 0-rings FillCavity, Unlatch CEA's, Remove 8 Incores, Remove UGS

'A'PSI, SDC, CCW Work Window Core Offload

'B'PSI, SDC, CCW Work Window Remove Core Support Barrel Rx Vessel Exam Valve Work with Freezes Reinstall Core Supprt Barrel Core Reload Install 8 New Incore Detectors, UGS and Latch Extension Shafts Set Rx Head and Final 0-ring Inspection Rx Reassembly, Filland Vent Heat-up and Pressurize NOP NOT, Ql-11's and PMT's Rx Start-up Hold In Mode 2 forTurbine Completion Roll Tur

UNlT 1 'l996 OUTAGE 1400 1200 PWO Planning Curve 1287 100%

IQ 1000 IllI-O 800 URZ 600 0

CL 400 200 2/9/96 2/16/98 2/22/96 2/28/98 3/6/96 3/13/96 3/20/96 3/27/96 4/3/96 4/10/96 4/17/96 4/24/96 4/29/98

Report Date:

16-A r-96 Data From:

16-A r-96 LMD Department A

-" APPROVED

'16-Apr-96 E

= E-WORK NPWO's U

= UNAPPROVED To Date Totals GRAND TOTALS After27 FEB 96 1

MECHANICALMAINTENANCE 40 67 2

INSTRUMENT& CONTROLS 0

30 40 3

ELECTRICALMAINTENANCE 13 10 26 C

PROJECTS /MAINTENANCESUPT.

21 TOTALS EMERGENT NPWOs PLANNED (Status >=30):

A 92 E

21 26 163 TOTAL 113 EMERGcvn.xts No/e: EWORK requires evaluation an proval prior to betng APPROVED 4ltrvss 5.

Unit 1 Outage PCMs Total for oUtage................

68 Major Packages................

Minor Packages.................

~

1 1 3

~

~ 55 Total Delivered.................

49 Not Yet Delivered...............

19

ST. LUCIE NUCLEAR ENGINEERING UNIT 1 1996 OUTAGE SCHEDULE BASELINE SCHEDULE JAN. 2, 199B UPDATE AS OFAPR12,1998R, ENSLEY LEGEND:

TT C3H EB+

C

~ REA Number W Descrlptlon M DateDue a

Resp. Disc.

~

Engr'd Matte. Ordered

~

Engr'd Matte. Required M Orlglnal Plant Ust W Emergent Packages

~

By Outage StartrDurtng Outage W

PC/M Not Required W Capital sstMittll N!! !

WBhaded Box Represents

~ ---',!;:!

,'.',..:,:Completed Package SLN 95411 3.10 NONDERNCORE 41298 FUELS PMAI984I3 777 PMAI98412492 EDG COP TUBE EDG UNLDVLV 4.19.98 4.28.98 SITE MEC SITE MEC REWINDCWP 4-19.98 PEG ELE STAR951049 1A2 DIESEL TK 4.26-96 SITE MEC PMAI96.03470 24 SPOOL PCE CIAS EDG START 4.19.98 4 28.98 SITE MEC PEG EI.E SLN 93461.11 STAR 950970 AIDcRNs poLARcRANE 4.15.98 4 2448 ITEMECtCI + SITECIV

+

STAR 951667 TAR 950323A SNUBBER CRIT CP LKOFF 4 15 98 4 19.96 SITE CIV ITE MEC EDG RADPLNM 4.29.98 SITE MEC TAR 951 080 RTGB GR ALRM 4.2948 SITE EI.E PMAI96-03479 DIG INDLIGHTS 4 29.98 ITE ELE/SC PMAI96 03453 DBLJAC BONET 440-96 SITE MEC PMAI98 02452 480V LC LIFT 4.2646 SITE CIV PMAI984I3 785 CNTMTRNG LGT 4<0.98 PEG ELE PMAI964I2-148 EDG EXHAUST 440.98 SITE IV STAR 9S1283 RCP SWEEPS 440.98 SITE LIC STAR 951136 MV08.1 B MTR 440.98 SITE ELE MSIVBXUP 4.29.98 PEG MEC PMAI96.03 728 1B EDG VLTREG 540.98 SITEELE PMAI9603 11S RCP VIBPROB 540 98 SITE ELE STAR 951197 1A1 RCP CCW 540.98 SITE MEC PMAI98 03 277 LCV 11 24 A/B 5.17.98 SITE MEC PRESS INSL 540.96 SITE MEC STAR 95056S 1B2 ANNA 13 540.96 PEG ELE STAR950428 MV09.13 ST NUT 540-98 PEG MEC STAR 950582 EXCORE POS 540-98 SITE MEC +

APR MAY G.COMMONDRBSICLNESu998PIEPRE

Operations Outage Preparations Procedures;

-13 procedures remain to be revised to support"Verbatim Compliance" for outage.

-Operations outage procedures will be FRG approved prior to 29 April.

Clearances:

-237 Clearances have been identified to Operations as of 17 April 1996

-111 Clearances have been created for the outage as of 0800, 17 April 1996.

-100% of clearances are expected to be complete prior to start of outage.

25

1996. SPRING OUTAGE GOALS UNITI 1.

Personnel Safety - Lost Time Injuries.. ~...............

~. 0 2.

Doctor Case Injuries................................

z6 3.

NRC Violations...................................0 4.

Outage Duration.............. ~.........

s49 5.

Personnel Radiation Exposure.. ~..............

~316 MRem 6.

Personnel Contaminations (any Contamination Resulting in a Skin Dose)............................

z10 7.

Contaminated Floor Space within 14 Days Post Outage.................................

<1,500 ft'.

Cubic Feet of Radiological Waste Gen.............

<6,300 ft'.

Outage Budget.......,.............'.........

~$25 Million

10. Unit Performance

- 60 days Post Outage Availability................... ~93%

26

FIGURE l-2 UNIT4 '96 REFUELING

, OUTAGE GOALS 1'. NUCLEAR SAFETY PROBLEM GOAL ZERO ACTUAL ZERO

2. PERSONNEL SAFETY

- LOST TIMEACCIDENTS ZERO ZERO

3. DOCTOR CASE INJURIES

4. MEET OR BEAT THE OUTAGE

- SCHEDULE DURATION

5. MEETOR BEATTHEOUTAGE

< 40 DAYS 35 DAYS 11 HOURS 21 MINUTES

- BUDGET

< $22.5 MILLION

< 22.5 MILLION

6. PERSONNEL EXPOSURE LIMITS

< 215 MANREM by dosimeter

7. PERSONNEL CONTAMINATIONS (ANYCONTAMINATIONRESULTING IN A SKIN DOSE)

8. CONTAMINATEDFLOOR SPACE WITHIN14 DAYS POST OUTAGE

<10 2

<1750 ft 3

469 ft

9. CUBIC FEET OF WASTE GENERATED

<6400 ft 3

2400 ft

10. OUTAGE RELATED SIGNIFICANT CONDITION REPORTS

<10 6

27

HOURS 100 UNIT 4 1996 REFUELING AHEADOR BEHIND SCHEDULE 31 DAYS, 19 HOURS 80 60 40 20 (20) 2$ tdta27 23 2$

(40)

(60)

(80) 7 6

15 Ie 1215 10 11 It 13 5

1220 21 31 32 ACTUAL (100)

I I

5 I

~

II 1$

1112 II 21 212121 2$

$ 1 I~

1112 ovrxos

+>+>+v @>@>@-@-@>@>@-@>@>gg e

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e e ~

e e

e e.e~~e'e~e e'e eve.emcee rb

~0

~+

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~co

~rb (0

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~Tx ceo

~rb ~0 w

152 43 OUTAGE DAYS I) 3 Loss Polar Crane Inspection/Torque Aad Ctps 2) 44 Loss Polar Crane Large Hoo'k Impacted Stops/

Caused Damage 3) 14 Loss Pokrr Crane cable replacement on Ihe man hoist 4) 16 Loss Polar Crane cabte replacement/rework the slack cable grist swdch 5) 5 gan CADMductwork removaVcondsaals 6) 14 gain Rx vassal datensenkig set up 7) 5 gsn Axhead delension 6 stud removal 8) 9 gain Ax stud eqvymenVcavd y seal ring 9) 8 toss polar crane repax aux hoot gear box gasket replacement moving eqrdpment into containment 10) 12 loss as (ound rod drag test dursten axtendded/

SF G crane south hoist load cable lorn Irom ds (emanation 11)

Core unload progressng on schedute 12) 6/G lube ptuggingis crit+a(path 13)

S/G tube plugs ahead ol schedule/

CADMcanopy seals have Iha crdrcat path 14) 5 gain canopy seal clamps on crilioal path 15)

I galri csnopy seatclarrps ahead 16) 4A RHR Hx repair now has crilrcsl path

17) 4AAHAHxoncrdicalpath 18)

MOV.750packng gland damage and movals lasting has crdical path 19) 24 gain commenced core on load/bvtk work activities (<rushed 20) cora on load progressing 21) core on load progressing 22)

Axcavdy dian/Rx head seVrx cavity decon 6 paint 23)

Rx head stud hold plug removals cteanng Sel vp (or lensiolng 24) 7 gain Axhead stud insenion 6 tansiorung 25)

On schedule 26)

Gn schedule 27)

On schedule 28) 8 loss Sslegusrds lasting

~ Bus cles my relay (aded 29) 4 loss Sategusrds lasting/MG 6 relay/Kesavi relay (sited 30) 15 loss CV 2906/2908 laded to stroke

~ 4A CSP akgnmerit IL IST/TE432 RSC TC replacement 31) 18 toss RHR kitadock teal laded. MOV 863/VB (use blown/

TE432 ACS TC reptacemenl 32) 4 gan Aeschedrda Rx protection teal 5 RCP cossl down data 33)

(7 toss CV 2908 pdot valve tailed 34)

~ 1 loss API'5 K 8/D 10 signal condikoner/connector ctearxng delayed start o( lower power physios 35) 29 loss lvrbna tube od system msllunction 6 repair 36)

UNIT Otd LIRE 0 Cue JILVLIIIJIWIAtNrrr sr

SHIFT DIRECTORS SHIFT DIRECTORS DEPUTIES DIRECTOR JEFF WEST FRANKMcGLYNN JOHN BRADY DONNACALABRESE CHRIS BURTON TS BOB FRECHETTE LEE LARGE HARRY BISHOP ROBIN MIXON TONY MENOCAL

UNIT2-FRED GIGELE, CARL CRIDER

Outage Projects - SL1-14 Project Lead/

Task Manager Responsible Manager 10 Year Reactor Vessel and Core Barrel inspections Contingency plan for repairs K. Mayhew (Supv:G. Pustover)

Marchese Denver Pressurizer Code Safety Valve replacements Flange work/mods C. Ward Denver RPS NIS Upgrade Repair detector positioning devices Hardware replacement (detectors, drawers, etc.)

G. Pustover R. Olson Marchese Steam Generators(Overall)

Westinghouse SG Tube Plugging 8 PAP RWI bottom inspection water management plan R. Ball (Supv:Flowers)

R. Frechette Marchese H. Johnson RCGVS Valve replacements and piping modification Incore Instrument Assembly replacements V07161 and bypass replacement Polar'crane load test TCV-1~B replacement 1A 81B LPSI common piping valve work G. Rodgers R. Olson G. Rodgers D. English H. Fagley N. Motley Marchese Marchese Marchese Marchese Marchese Marchese EDGs overall McLaughlin/Ware Wood Charging header isolation valves repair SE-02-1,2,3 T. Sanders Marchese FCV%7-1A/1B maintenance Springs, Airpress s.p., elastomers T. Sanders Marchese SIT valve maintenance Quantify leakage pr~utage V3634 stem replacement N. Motley

'. Fulford N. Motley Marchese ICWpiping at intake structure external corrosion inspection Repair contingency Purge Valves RCB permanent A/C modification, HJTC replacements HP turbine 8 seal ring replacement R. Ball (Supv: Yates)

C. Swiatek H. Fagley R.'Olson R. Ball Marchese Wood Marchese Marchese Marchese 30

Main Generator Maintenance/ModiTication R. Ball Nichols/Wolaver a

Condenser Tube Cleaning System and Debris Filter installation D. Sipos Atmospheric Steam Dump valves seat repair N. Motley D. Sipos Marchese Marchese Turbine turning gear auto/remote engagement repair RCPs (all issues)

ESF testing SIT dump testing ECCS fullflowtesting OPS-reduced inventory/mid loop mgr OPS-refueling Clearances OPS procedures OPS-vent and drain hoses MOVCoordinator-Ops Pressurizer(Overall)

Reactor Maintenance Pre/Early and Post RCS 8 RCB Inspections Relief Valves Cranes RCB Cleanup Reactor Cavity Seal Ring Maintenance Procedures Engineering Packages NPWO Planning Wolaver B. Haines P. Fulford J. Hallem P. Fulford R. Weller R. Weller R. Lamb R. Weller C. Johnson A. Haii C. Ward B. Haines R. Riha N. Motley English M. Goodiel T. Kreinberg Menocal Denver Menocal Wood Marchese H. Johnson H. Johnson H. Johnson H. Johnson H. Johnson H. Johnson H. Johnson H. Johnson H. Johnson Marchese Marchese H. Johnson Marchese Marchese Marchese Dawson Menocal Denver Menocal

OUTAGE PROZECTS

S G INSPECTION

ST. LUCIE STATUS MEETING APRIL 18, 1S96 STEAM GENERATOR INSPECTION I

EDDY CURRENT TESTING SCOPE OF TESTING Bobbin Coil Testing:

- all active tubes full length MRPC Testing:

- all active hot leg tube expansion transitions.

- 20% of cold leg tube expansion transitions.

- 20% of dented hot leg tube support inter.

- selected bobbin coil indications (diagnostic).

-- 1200 indications at drilled supports.

CONTINGENCY PLANNING Back up equipment 8 components Data analysis personnel scheduled for 8 hr shifts 24 hr LANsupport for transfer of examination data.

Qualified Bobbin Coil Sizing for IGAJSCC damage Applies to tube damage except at drilled supports Review Inspection Plans with NRC next week 32 SG4-1 B.WPD

ST. LUCIE STATUS MEETING APRIL 18, 1996 STEAM GENERATOR INSPECTION II MECHANICAL8 WELDEDTUBE PLUGGING SCOPE OF PLUGGING Mechanical Plugging:

400-500 tubes expected Welded Tube Plugging:

None Expected CONTINGENCY PLANNING Welded tube plugging Plug repair/replacement-drilling and EDM.

Plugs in sufficient numbers to meet site needs Mechanical &welded tube &,tubesheet plugs Oversize welded tube and tubesheet plugs Tube stabilizer cables for circumferential cracks at:

Top ofthe Tubesheet Upper Drilled Support Plates SG4-18.WPD

ST. LUCIE STATUS MEETING APRIL 18, 1996 STEAM GENERATOR INSPECTION II Ill REPAIRS FOR WESTINGHOUSE ALLOY600 PLUGS REASON FOR REPAIRS WCAP-12245 Revision 3, Addendum 4 to "Steam Generator Tube Plug Integrity Summary Report", May 1995.

Prevent tube perforation due to plug top release SCOPE OF PLUG REPAIRS (Framatome)

Install Plug-A-Plug (PAP) into base of plugs

'I r

A S/G Hot Leg -254 PAPs B S/G Hot Leg - 234 PAPs PC/M in place for PAP Installation PAP also limits leakage through plug 8 perforated tube CONTINGENCY PLANNING Cleaning 8 tapping plug threads for installation.

Replace any plugs not suitable for PAP installation PAPs acceptable without final crimp to lock cup 8 cap sere W Plug Top Remnants can remain in the tube 34 SG4-18.WPD

ST. LUCIE STATUS MEETING APRIL 'I8, 1996 I

$TEAIN GENERATOR INSPECTION IV IN-SITU HYDRO TESTING OF S/G TUBE DEFECTS REASON:

NRC Concern - Plants operating with IGA/SCC Flaws.

Demonstrate Structural Integrity ofTubing.

Demonstrate Adequacy of Inspection Program.

SCOPE OF IN-SITU HYDRO TESTING 4-6 Most Severe Flaws -. Circumferential-8 Axial Orientation CONTINGENCY PLANNING Industry Results Favorable Flaws at PSL-1 not as Severe Test Pressures Limited:

P 1.4P 3P Adjusted forTemperature 8.Locked Support Plates Bladder Installation to Mitigate Leakage during Test Bladder Tested for Extrusion Through Fracture Face IfTube Burst Occurs:

Stabilize Tube 8 Evaluate Adjacent Tubes for Plugging Evaluate Inspection Program 8 Implement Repairs 35 SG4-18.WPD

ST. LUCIE STATUS MEETING APRIL 18, 1996 STEAM GENERATOR INSPECTION V

SECONDARY SIDE ISSUES SCOPE OF WORK NONE:

Last Cycle of Operation for S/Gs, Additional Sludge Loading is a Long Term Concern Prior Inspections for Steam Separation 5

Feedring Equipment Acceptable PROJECTED SAVINGS

$350,000 (Contractor Costs) 36 SG4-18.WP0

~ VESSEL COpp SUvvonz s INSPECTzo

0

REACTOR VE SEL EXA1VHNATION TOTALSCHEDULED DURATION:144 HOURS ( 6 DAYS)

EXAMSERVICES PROVIDED BY: SOUTHWEST RESEARCH INSTITUTE

~

EXAMINATIONS OPE:

- VESSEL EXAMINATIONREQUIRED EACH 10 YEARINTERVAL(ASME SECTION XI&REG. GUIDE 1.150 )

- CIRCUMFERENTIAL,LONGITUDINALANDMERIDIONALWELDS

- INLETANDOUTLETNOZZLETO SHELL WELDS

- INLETANDOUTLETNOZZLEINNERRADIUS

- INLETANDOUTLETPIPING WELDS

~

EXAMINATIONMETH D

- ALLEXAMINATIONSWILLBE PERFORMED FROM THE ID OF THE VESSEL

- EXAMINATIONEQUIPMENT: "PAR DEVICE"OPERATED BYSWRI

- SUSCEPTIBLE AREAS WILLBE EXAIVQNEDFIRST (IENOZZLETO VESSEL WELDS)

~

PREVIOUS ULTRASONI EXAMSPERFORMED:

- BASELINEKDQdINATION(PRIOR TO OPERATION)

- FIRST 10 YEARINTERVAL(APtuL 1983) 37

e CONTINGENCYPLANNING

- SWRI EXAMINATIONEQUIPMENT FAILURES/ CORRECTIVE ACTION

- FLAWEVALUATIONS(FRACTURE MECHANICS):

JPN: SUBHASH KURANA TRIICtUI Itlll!GRI ROC O

APtBCH

~

KNO INDICA

- APREVIOUSLYUNRECORDED ASME SECTION IIIREJECTABLE FLAW HAS BEEN DETECTED DURINGAREVIEWOF RADIOGRAPHS.

- LOCATION:CIRC. WELD 10-203 (LOWER SHELL TO BOTTOMHEAD WELD)

ADJACENTTO THE CORE BARRELLUG@60 DEG.

- FLAWHAS BEEN CHARACTERIZED,BY CSI ANDIDENTIFIEDON STAR 951893.

- WELDAREACONTABKMGFLAWWILLBE EXAMINEDFIRST TO ALLOW FOR FURTHER EVALUATION.

38

'IR 4 CORE E~UPPO T 4 RREI REPRI ~

~

REPAIRS PERFORMED ON 8 OF 9 LUG AREAS

~

REPAIRS CONSISTED OF CRACK ARRESTING'HOLES AND BYPASS LIMITINGPLUGS AND PATCHES

~

DESIGN MET ASME CODE AND CSB DESIGN BASIS REQUIREIVlfNTS

~

REPAIR NOT STRUCTURAL

~B INSPECTI N SC PE PLAN

~

VI LINPE I

N

~

TO PERFORM VISUAL INSPECTION PER NRC COMMITMENTS

~

ABB TO PERFORM USING HIGH RESOLUTION CAMERA MOUNTED IN SUB EXPECTED DURATION 2 DAYS.

~

I I

N N

Y FPL SUB FOR VISUALEXAMINATION USE OF ECT AND/OR UT FOR FURTHER CHARACTERIZATIONOF INDICATIONS D BL

~

CSB PER ASME SECTION XI VT 3

~

REPAIR CONSISTENT TO 1986 VISUAL

ATI INITIALENGINEERIN EV LUATI N

~

PREVIOUSLY DISPOSITIONED CRACKS ACCEPTABLE

~

NEW CRACKS TO 3" ACCEPTABLE FOR AT LEAST ONE OPERATING CYCLE.

~

CRACKS IN EXCESS OF 3" REQUIRE ADDITIONALEVALUATION.MAY NOT BE ACCEPTABLE.

~

Pl.

ND

~

CRACKS IN PLUGS ACCEPTABLE.

~

CRACKS IN PATCH PLATES ACCEPTABLE

~

COMPLETE LOSS OF PATCH PLATE NOT ACCEPTABLE

~

LOSS OF ONE PLUG.TO 8" ACCEPTABLE FOR CYCLE 14

~

PLUG ROTATION ACCEPTABLE CONT NGENCIE ABB REACTOR INTERNALS ENGINEER WILLBE ON SITE MOST CONDITIONS CAN BE EVALUATEDFOR AT LEAST ONE CYCLE MAJOR FINDINGS REQUIRE FURTHER ANALYSIS/POSSIBLE REPAIR COMPLETE PATCH FAILURE UNLIKELY.DESIGN REVERIFICATION REQUIRED.

REPAIR REQUIRED.

~

CSB CRACKS IN EXCESS OF 3" REQUIRE FURTHER EVALUATIONINCLUDING FRACTURE MECHANICS. REPAIR MAYBE REQUIRED

~

PHYSICAL REPAIRS THIS OUTAGE NOT REQUIRED UNLESS EXTENSIVE PROBLEM DISCOVERED.

~

REPAIR BY WELDING NOT LIKELY-I REMOVALAND REINSTALLATIONOF PATCHES AND/OR PLUGS REQUIRE NEW TOOLING, TESTING ETC.

40

MAIN G ROTOR zzsmCrION

MAINGENERATOR OVERVIEW

~

Stator Winding Improvement Modules Installation

~

Generator Testing (Electrical and Mechanical)

~

Complete Stator Rewedge - (all 42 slots)

~

Core Torque Check

~

Generator Clearance (including Hydrogen Purge, Main Steam, Generator)

(2 Days)

~

Remove Generator Rotor (Craft Labor)

(5 Days)

~

Generator Work(by Westinghouse)

(27.5 Days)

~

Reassembly ofGeneratorfExciter (Craft Labor)

(10 days) 8

~

Vibration Levels on Coil Ends are moving in an upward level. Started at 3 mils, presently at 13.4 mils, Target is 20 mils in which itis recommended to reduce power until vibration levels go below 20 mils, which could be approximately 1 to 30 percent power reduction.

~

Based on Trending ofEnd Turn Baskets, they are no longer functioning as a consolidated unit.

~

We are only monitoring 6 Coil Ends on each end ofthe generator out ofa total of42 coils or 84 End Turns.

Qgtions:

~

Install RF Monitorper Factory Mutualifwe do nothing (Cost Approx. 100K)

~

Do partial module installation ofmodule package (Cost Approx 750K plus labor)

~

No one has had success doing a partial

~

Westinghouse has never performed a partial ofthis type based on their proposal to us.

~

Do complete Module Mod. (Cost 23 Mil)

~

Do Rigi-Flex Rewind which includes modules - new Design - (Cost approx. 6 Mil)

~

Main Steam and Generator Clearance in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with Generator Degassed &Purged.

~

Develop Contingencies forwhat could happen.

~

Westinghouse to start work prior to rotor removal to initiate work on critical path item.

~

Pre-job planning and setup.

~

Hydrogen Leak Rate Test Prior to Shutdown

~

Pre-job material staging on turbine deck

~

Staging contingency material in Orlando Wh Westin h u e:

~

They have performed same modification on numerous other units with success

~

ABBwanted a 6 month lead time

~

ABBhas never done a 4 pole end turn modification on a Nuclear Unit.

~

Keystone could only install Westinghouse Materials but has no Nuclear Experience or Nuclear background.

See Attached List 41

t9lE AJz'nag' ngoduMS Dirc/C rc orppporcpea PS'rPp r/srrv

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yh PPQCOCCPJ fge +rue CCPr'rCPC/i&/ f0 PPPOVF iRV/e IC/

oc/r rc/9 PIPernt~L c'>IP/ws'dms'ruclc~frAc iorc/r

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/PPOoe rcrAYurnL Fi'c9uerrc f cue//rPdoUc HAe, /Zo W2. c=wc-'P/rrcrg prc~uorupy.

~ /roc/r'OC S rgef Al/J9rCh'f// Scar,aq 4 Aucl 7G ar/fIPs/~~ shor+ 0 're,c,u '+ fe rd es ouzfIPoc/r Aecsglue Co:I deffec.f.o< a~c/sfrar> o~ g4C, g ruurCrO CuA// rrCPJ'P7VOrCP

PRESSURIZER CODE SAFETY VMVES

ST. LUCIEUNIT 1 PRESSURIZER SAFHYVALVE SPRAY UNE PRESSURIZER CUBICLE V.1200 PRESSURIZER V-1202

]

V 1201 QUENCH TANK NEW HANGER 43

ST LUCIE PRESSURI2ZR SAFETY VALVE SEAT LE%KM& ELIMINATION ACTIONS SEAT LAPPING INCfKASED DIMENSIONAL CHECKS STA5tDAIK)IZATION 2

'ESTING PRACI'ICES

'ISEZMAL BINDING CHECK INCREASED TEST PRESSURE FOR LEMQ~ TEST

. FINAL AIR TEPI'ATCZKD AMBIENTAIR TEMPERATURFS AT TEST STANDS 3

SEAT DESIGN IMPROVENEÃIS INSTM~X) PLEXIDISC 4

TEIL PIPE LOAD REDUCrIGN M05KTORED WITH INSTALLED SIHAIN GAGES EACH (X7IRGE ADJUSTED LOADS WITH FLANGE WEDGE COÃlROLLED HEATUP RATE 5

S VALVE BODIES-1630 LBS TO 10000 LBS PURCHASED NEW BLOCK VALVE BODIES l

TP~'ED FOR THERMAL EFFECZS TFATK) FOR TAIL PIPE LOAD EFFECIS

PZR SAFETY VALVENOZZLE LOADS 14000 12000-MY Mz M x m

10000 8000 II-z eooo-0 4000 2000 4033 2507 456 753 693 790 168517631803 5867 6640 981 763 357 3112 2914 992 Ag/

V-1200 V-1201 V-1202 V-1200 V-1201 V-1202 V-1200 V-1201 V-1202 Before Mod 1992 'fter Mod 1993 Cycle 13 SNO 2/96

Von Mise 5~WM~', ~

~5'

'555 gc A5' W

5" W cc5~

20164.1 17301.4 14438.8 11675.B 871S.08 5850.30 2987.53 124.757-

'4'A:::5............

5 5

5

":CrayCC-..C "V5'.CCC C

.5 C

'C:"5 Q@ 'g..

'""5+

X-

+ 'jg

'" ~+

"+PE/piieRi~~V<~~~~%

46

IlNPROVEMENTStAGTIONS V

Strengthen the Management Skills of our Supervision:

Include the followingattributes in personnel performance appraisals:

- Adherence to procedures

- Compliance with Industrial Safety Program Develop and issue guidelines to foreman and supervisory personnel on assessing employee performance.

Evaluate and modify, ifnecessary, accountabilities of foremen/

supervisors to ensure handling employee perfonnance is a key responsibility.

Ensure these accountabiTities are clearly identiQed in the foreman/ supervisor selection process.

Complete Interview forenoon and supervisor incunkents to ensure they

'/30/96 are willingto meet the eyectations ofthe position in handling employee performance issues.

Improve Labor Relations:

~

Reduce number ofunion grievances not handled within 10 days.

Include indicator for review.

47

ST LUCIE PLANT Total Employees Lynn Morgan - Human Resources 830 27 83 828 820 810 I 800

~

790 Te>sel 1905 eas 811 802 780 770.

Tarsat 1000 710 UZI 760 Sept Oct Nov Oec Jan Feb Mar Apr May June July Aug Sept Oct Nov Oec

'95

'96

~Employees Target

GRIEVANCES Grievances > 10 Days - Total Grievances > 10 Days - by Dept 25 20 15 10 26 18 14 12 10 28/96 3/8/96 3/18/96 3/25/96 4/1/96 4/8/96 4/15/96 4/17/96.

Oate ops MM TRNG Data aubmlted by: CD Scott-HFt 340 320 300 280 260 240 220 Download Population

'/30/95 1/31/96 2/29/96 3/31/96 331 224 216 214

'GOAL-Comptete by December 31, 1168

NUCLEAR DIVISION EXEMPT ABSENTEEISM MARCH, 1996 12 Month Average

~ 9 8

>. 5 4

3 O

62 1

NUCLEAR DIVISION NON-EXEMPT ABSENTEEISM MARCH, 1996 12 Month Average q6

>. 5 4

O3 82 1

B STAFF SL TN 2.74 2.80 2.68 2.01 2.07 2.03 1.93 1.88 1.79 12 months endtn A

M J

J A

2.59 2.57 1.95 1.84 1.90 1.?7 6

0 N

2.57 2.61 2.49 1.89 2.01 2.13 1.83 1.92 1.90 2.04 2.25 1.77 J

F 1.98 1.91 2.15 2.13 2.13 2.14 1.78 1.99 1.99 PSL PTN 2.48 2.30 2.07 4.41 4.69 4.71 12 months endln A

M J

JB STAFF 6.85 6.51 6.56 6.57 2.02 4.67 7.24 2.03 4.41 S

0 6.21 5.93 2.04 2.32 4.49 4.68 5.64 4.69 0

J 5.95 5.16 2.57 2.78 4.46 4.60 5.45 2.71 4.55 6.37 2.87 4.40 NUCLEAR DIVISIONBARGAININGUNITABSENTEEISM MARCH, 1996 12 Month Average 9

>- 8 P~ 5 4

O

~

3

<2 12monthssndln A

M J

A S

0 N

D J

F M

PTN 5.14 5.11 5.23 5..52 5.48 5.50 5.35 5.49 4.82 4.71 4.56 5.64 5.66 5.69 5.58 5.56 5.62 5.70 5.90 6.19 6.76 6.99 6.76 PSL

PSL OPERATIONS STAFFING COMPLEMENT 40 II COMPLEMENT Q CURRENT 35

~0 30 0I-u20 0

EL

~ 10 7

7 12 3 t 3p 28 t

p OPS SUPV NPS ANPS NWE SRO/RCO TECH SNPO PIPELINE CLASSIFICATION

145 144 OPERA TlONS STAFFING

~P OF POSITIONS

---.-.MIN

.. MAX 140 135 0

130 00 125 00 120 115 110 143

.136

~ ~

134 131

~ ~

~

124 124

. ~ '

~

120 115 l

1

\\

1 W ~

~ ~

.'3'

~

~ H'36 136

\\

127

\\

124

115 112 Jan.90 Jan.91 Jan.92 Jan.93 Jan-94 Jan.95

.YEAR Jun-95 Jan-96 Mar-96

'3/98 Support Resources transferred to OST OPS STAFForo D A'8TAFF-R 4I

OPERATIONS ATTRITION 8 NON-LICENSEO OPERATORS 9 LICENSED OPERATORS 1990 1991 1992 1993 1994 1995 1996 DPS STAFFIIIGDISK AIATTRIT.R4 4117/98

OPERATIONS

IMPROVEMENTS/ACTIONS OPERA'HONS r

vement Reduce the Number of Operator Work Arounds:

Reduce the number ofOWAs to less than 15 by December 31, 1996.

Currently working oF as per target goal.

Improve Operator Procedures to ensure technical accuracy and ensure they can support operation under verbatim procedural compliance.

Phase 1 procedures (16) are on schedule for completion date of 17 May 1996. Willbe on track as of4/19/96.

Unit 1 procedures have been identi6ed to support Unit 1 outage and have been prioritized to support schedule.

54

OPERATOR WORK AROUNDS Updated and Submitted by: OST-Fulford MONTH Aug-95 Sep-95 Oct-95 Nov-95 Dec 95 Jan-QB Feb.QB Mar-QB Apr.ge May-98 Jun-98 Jut-98 Aug.se Sep-QB Oct-QB No v.98 Dec.se OPEN TARGET 79 98 103 101 41 45 55 47 48 44 43 40.

38 30 20 18 17 18 15 120 operator ln performing duties within the approved procedures or ln accordance with the intended design.

100 g-Decrease due to separation of OWAs from Operator fnconveniences.

80 rs 60 OPEN

~

% ~ TARGET 40

~ -l.--

~ ~

Year End Target=15 20 Aug.95 Oct.95 Dec-95 Feb.96 Apr-96 Jun.96 Aug.96 Oct-96 Oec-96 Time (Month)

ST. LUCIE NUCLEAR PLANT OPERATIONS DEPARTMENT PROCEDURE UPGRADE PHASE 1 LEGEND:

XXXXXXXX XXXXXX XXXXXX XXX PROCEDURE¹ DESCRIPTION DATE OUE RESPONSIBLE 1.0030121 Rx Plt Heatup D. Wislams

~o S

2-0030121 Rx Plt Heatup D. Wilsams heccrieieXeo S

14I030122 Rx Stertup M. Koeebchetc IND REVIE R

2-0030122 Rx Startup ILKoyebchetc SHADED BOX REPRESENTS COMPLETED PROCEDURE UPGRADE D DRAFT S

SUBCOhllMITTEE R INDEPENDENT REVIEW F

FRG APPROVAL D1 DISTRIBUTION 1k

. '8 1-00301 27 Rx COOIBown O. Williams 50.59 Req.

F 2.0030125 2 ON0127 rorhrrre axeman RX COOI5OWn D. Brown D. Witsams FRGApprov F

IND REVI R

1.0030120 Pre ebii Chock&a D. Brown DRAFT D

2.0030120 PlosQrr Chechorl D. Brown DRAFT D

1 0030124 Turbtne Starlup D. Brown

~eo S

2.0030124 Turbtne Startup O. Brown hcbcccrneee S

3I22I9B 4I4/96 4I19196 513195.

5I17IBB opERAtloxs pRocEouRE upoRAoE PHASE 1JKS e/rrrre

ST. LUCIE NUCLEAR PLANT OPERATIONS DEPARTMENT PREOUTAGE PROCEDURE REVIEW LEGEND:

XXXXXXXX

XXXXXX, XXXXXX XXX PROCEDUREB DESCRIPTION RESPONSIBLE STATUS SHADED BOX REPRESENTS COMPLETED PROCEDURE UPGRADE/REVISION 1.01 20021 Drain RCS Kogelschatz Processhg P

1.0210021 VCTH2/N2 Bonsatl Processing P

141 10022 C

Eiden esca Kogefschatz Processing P

1-1800024 Fa S Dice Cevay Kogefschatz Processing P

1-230020 N2 Sys Normal Bonsag FRG F

1.080050 MSIVTest Scott FRG F

14410021 SIT Normal Pennenga svbeeeeii/see D

1-1010020 Inst AlrSys OP Lorenlzen FRO F

1-081 0021 a/cede X Se WEEams Draft D

1.0910024 D

Bus Removal Pennenga seeeeeiersee S

1.0120023 RCP Normal Lorentzen Draft D

1.0700028 FdrwbTeel Lorentzen Draft D

1.0210020 Chg-t/D Normal Patterson Dratt D

1 0700021 Cond/Feed Norm Pennenga Draft D

1-1210051 WR Nl Func B. Scott Draft D

14120020 FIB &Vent RCS D. Brown Dra/t D

D Dl P

F S

DRAFT COMPLETE DISTRIBUTION P/ocessfng T FRG SUBCOMMITTEE 3/16/98 3/27/98 4/6/98 4/12/98 4/19l98 4l28//98 OPERATIONS PRE4WTAOE PROCEDURE REVIEW OIITAOE

1996 lIANREM TARGET 400 300 5

200 Unit 1 Refuegng Outage Outage Budget~ 310

~ r

~ ~

~Actual

Target 100 4 582 4.718 Jan Feb Mar Apr May

'un Jul Aug Sept Oct Nov Dec Time (Month) 1996 PERSONNEL CONTA(ilNAT(ONSTARGET 80 70 60 o

50 Unit 1 Refueling Outage

~Actual

~ - Target 20 10 0 2, 2

r

~ ~

Jan Feb Mar Apr May Jun Jul Aug Sept Oct Nov Dec Time (Month)

ST. LUCIE PLANTCONTAIIINATEDFLOOR SPACE 4000 3500 3000 2500 2000 1500-1000 500 Inaccessible cree f~

BstÃtÃlserhs wrrh Twkey PoH end ksspksa wkh kskssky preclksss.

Post outage recovery of contaminated floorspace.

250 280 12

~

\\

~

I

~

Unit 1 Refueling Outage

~Actual

- - - - - Target Sep-Oct 95 Nov Oec Jan-Feb Mar Apr May June Jul Aug Sept Oct Nov Dec 95 Time (month)

Unit 0 CPI (Chemistry Performance Index) 1AO 120 C7 1.10 O

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~ INPOGOALcc 125 DAILYCPI QTR AVG CPI g

CO CO CD g

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DATE I

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Unit 2 CPI (Chemistry Performance Index) 1.40 1.30 1.20

~ - ~ ~

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INPO GOALo 125

- - ~ - ~ DAILYCPI QTR AVGCPI g

CO CD CO g

CD CO CO CO CD CO CD CO CO CD CO CO CD CO CO DATE 60

IMPROVEMENTS/ACTIONS r

yement Program/Procedures Status Update:

~

Maintenance Procedure Upgrade Project

~

Pro Group

~

Minor Maintenance Process Plant Material Condition (Key Performance Indicator):

I

~

PWO Backlog Control Room Green Tags (C-Tag')

~

Aged PWOs (>12 months - Golden Oldies)

~

Leaks (Primary/Secondary)

~

Temporary Leak Repairs Valves:

~

Integrated Qews

~

Leaks

~

Valve Program 61

K'sTs LUCIEPLANT MAINTENANCEPROCEDURE UPGRADE PROJECT TASKN: DEVELOP PROCEDURES/GUIDELINES FOR FREQUENTLY PERFORMED MAINTENANCEACTIVITIESWHICHCURRENTLYEMPLOYTHE USE OF VENDOR TECHNICALMANUALS 1&C SPC/t FI>d PS Level Swlkhss mugs 4C richer Level Co/Craters 101/gs 4C V<<$SUC Cht Bd tndcuas s0ugs 4C Magneecl Level Swschcs S0ugs 4C HO0085: Add Rcw Ec&rprnc/C

$01/98 4C Roscmcurc Trsnsntscrs t00/$$

1&C Bench Calhrascn 1100/gs t0t)tds@i.;,w

&Cc px U~xwo<<% 14C Fo>d><<o Pneu C<<trot<<s C00/gs 4C

&chero0 Press Swschcs muss 14C IS,C 14C V2Ccru Atontc Setup Rod Crop VI 4 V2 Rchdrdn SSOP/co M<<>ta Computer TCV 12 I S0I/gs S00/gs 1001/gs I&C CEOM Cahle Regal/

It00/CS

,,@ltd+/I/tt;";

4!'cs')'LIc&<<t,"":'.:.>~

4C Ul Cat SCBO Rad Mo/Rota S00138 14C Ut Letdown Process Men\\ore 101/td 4C V2 Ccru Alom/c PIO Proc MCCR 10108 4C 14C V2 Can Alon/C VtCd Oeckrecrce CMM<<tror 4cs. IS&el,vv&0M S0008

'0010$

MC Unit 2 LPM

&CK@>@cK;mc SSCc,.,.cw >un 'g '

I'Ugt!/'Ss'T(CIsc

,'kO'OS";ALII)

""K~c "2;"'&C VICalofCCW Rad Montors 10008 MECH Oregon Vaue s mms MKCH Tergal Rodr Vel/es 101/$ 8 MECH Borg Warner clues

&0108 MECH ye/wsy Vsuca S010$

1&C V2Cen Atcntc SSL Proc Mont t/3008 MKCH Wcssnghcusc Valves S00/3$

14C ul Scone Op 0 ca

<<n Proc Mcn I00ugs MKCH Wc51<<l IIScg cute Vat/ca 10010$

4C V142C<<rcLol Proc Mont Rct>y Iu3008 MECH

/amc sbury Vahres It0008 I&C tcc Is/yaI<<s Cathreson 120 ugs 14C U2 Safeguards Mere/a CSL 12010$

ICC OP.K-ISCOO23 1&C Procectce 101/ST I&C ITT Baden IryclAclual as I/3ugt Psgccssd s(u

<<Mcc'JSIUta %

dcdtcFOII '

hlECH Ocrtng SS<<CK$ >$

0'~S.!F!S Jt'I'nU~W>

MECH Coal Cony.

Leldownulvs 1010$

MECH Herry Pran Vst/esVCI/ca

&0108 MECH Cress<<

(Ccnsotdatedt

&00/38 MECH Vaka &y Vahras 100108 wcc>.$>dtt cu.AT

$IScuALI "

Oltl 8 dttt5$ ?:>>-<<"'Octobey>EK MKCH Valsir tac Vnucs'1/3008

"-">togsr'ii5eTS circe Procedures

~cry/amah>/ng PSL.2 Plant Spe 1201/gs ODUSO'11USdtc <<<Bsris 'l4 IIIFOb

ST. LUCIEPLANT MAINTENANCEPROCEDURE UPGRADE PROJECT TASK¹2: REVISE AND ENHANCE EXISTING MAINTENANCEPROGRAM AND EQUIPMENT PROCEDUREs KNOWN' REQUIRE IMPROVEMENTS To Cofncfde viith DMslon Work Process tfftff4'>>ff2ftf&~4 f/8]f88<;::-".,~"-":;.if'~

Ef,BCT,';:-::,"";':,;:;";,"-"

0'nylon'-2:"'.020067;:@

Timp'.F)vi/Jiimjyery 1A1f88KCP~%kf 082007ff,! i<g",;'

f81/tiff!.".">>"-'-""-%%4 Rafts'e':;:,,":,.g':,,'!,.

Rb'dsd'Jfrrtt fry(.-'w..

aiid*f;f(e'dlgidPjy Pi'o'ci'lfiirej<~';yoii'",.<~

ffXGTjij$$+g~

eiivc)oillINga'a>

f,'esj:bj:doIinti.y';

Re~ac'pPWQi!,.0 0,,'00)'0'0%pi) '~<~<

KCG<TRv~~~'~

Sit Nff8K.";;~;~'f,hCTi<f4Gg",,'>>~ Revhe Conduct ofMafntenance ADM.08.02

POWER BLOCK PWO BACKLOG Joe Marchese - Maintenance PWO Backio PWO backlog are non-outage corrective work orders (WorkType 5 status 22-4S) on components/equipment in the power block. Total includes ail Work Type 1, Work Type 3 &Work Type 5.,

all hold codes 900 800 700 600 O0 600 400 0

300.

200 100 TOTALRR 2030 Good t.

end -tur5

~urtt 1

~urrit2

~Corecn

X Total Terrtet Tergel ~ 350 Totel trSMech 155 taC 20 Efect Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jut Aug Sep Oct Nov Dec

'95

'96 Date octa Source: perrrort

SUMMARY

STATUS Discipline Mechanical Electrical I&C ProJects Total Unit 1 71 80 160 Unit 2 117 10 110 239 Common 13 14 27 Total 201 17 204 426

CONTROL ROOM DEFICIENCIES C-TAGS Randy Olson - l&C

- The number of Control Room/Board Green Tags.

It provides an tndlcatlon ofthe attention given to maintaining control room Instruments in an operable condition.

80 70 Bo-50 Cg c) ao O

>o 30 20

".OUTAGE 11.

UNIT1~7 UNIT2cn4 4Oed

~raneocdnge x

regni Nnccecgn rncgcl 10

~ MO+OAyernegeeng Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jut Aua Sep Oct Irov Dec

'95

'9B Date Data: M. VWas

SUMMARY

STATUS Ready to Work or Workln Engineering! RTA AWP Other Holds Total Non-Outage Outage Total 12 20 Oldest PWO ¹ Discipline Unit 1 10/2/94 0137 EM (OUTAGE)

Unit 2 5/4/94 3017 1&C (OUTAGE)

AGED PWOs > 12 MONTHS GOLDEN OLDIES Joe Marchese - Maintenance

~Aed P Woe:

Non-outage corrective maintenance work type 5 PWOs older than.12 months.

50 40 0

530 q 20 0

Good

~ urrtt 1

~ unit 2

~Common X

Total Target 10 Target ~ 0 Sep Oct Nov Dec 'an Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

'SS

'S6 Date cata Source: paatport SUMNIARYSTATUS Unit1 Unit 2 Common Total Mechanical Electrical I&C Construction Total 0

0 17 Oldest PWO ¹ Discipline 8/11/94 2093 Mech 7/25/94 0562 Mech

LEAKS N. Motley Leaks:

- Active leaks (primary and secondary) 70 60 50 rrr 40 V

30 2:

20 OUTAGE UNIT 1 = 25 UNIT2 = 10 As of 4/6/96 Legend Good J ~ Non.Outage Non.Outage Target 10 a

0 8

$ *$ 0 0

P P

P 8

0

. Non-Outage Target~10 0

~

Sep Oct Nov Dec Jan

'95

'96 Feb Mar Apr May Sun Svt Aug Sep Oct Nov Dec Date Data Source: passport

SUMMARY

STATUS Unit1 Unit 2 Total Non-Outage 21 29 Oldest (Non.outage)

PWO¹ Status 2/9/95 4560 AWP 12/5/95 5730 ENG

LEAKREPAIRS FITTINGS Greg Pustover - Programs Leak Re airs:

Leaks that have been temporarily repaired.

55 50

~

45 Ln 40 a.

35 "30 25 o

20 0

15 10 tegend Good

~ Una1

~unlt2 Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

'95

'95 Date Data Source: JoelKagan(SCE)

SUMMARY

STATUS Unlt1 Unlt2 Total Total 21 10 31 Page

SYS z

COMPO ENGlNEERING

IMPROVEMENTS/ACTIONS SYSIXÃS &CChVIÃÃ6ÃISENGPKERlNG r

vement Improve Equipment Reliability:

~

Emergency Diesel Generators

~

Reactor Coolant Gas Vent Valves

~ "

Pressurizer Code Safeties (Unit 1/Unit 2)

(Unit 1)

(Unit 1/Unit 2) 6/96 5/97 Strerg6~ System Perfonnance Monitoring

~

Maintenance Rule PM Basis Program 7/96 12/96 Strengthen Root, Cause Analysis:

~

System &Component Engineers Trained

~

Event Response Guidelines

~

Root Cause Analysis Guidelines Complete Complete Complete 69

Plant St. Lucie Emergency Diesel Generator Reliability improvement Plan Matrix Problem Root Cause Units 1 &2 Governor Actuator Vendor teardown: report Corrective Actions Plant initiated 6 year failures identified fatigue due to length overhaul Preventative Maint service; recommended 6 year item.

periodic factory overhaul.

STARS 950059 &950529

1. Replaced all suspect electronic components and Unit 1 EDG Governor unstable Older design electronics during surviellances (tied to grid) very susceptible to "NOISE" optimized alignment with Status and Long Term Notes Allunit 2 actuators overhauled Nov-95 Unit 1 actuators replacement and set up May 96 outage.

NOTE: EDG's are in MAINTRULE "A-1"due to governor actuator failures. This is the get well item.

Engineering evaluating upgrade of governor system to more current design (Woodward 2301A) with proven noise rejection features.

"NOISY"inputs identified.

vendor rep support.

NPWOs:

1A: 95026166 1B: 95026332 Unit 1 8 2 EDG Governor Actuator Wiring grounds rough surface; vibration induced abrasion.

Raychem sleeve covering for abrasion protection STARs 951062 and 951055 PWOs 95024478 95026057 Two failure modes Identified:

Allfour EDGs inspected and Vendor design: governor wiring harness wires in contact with Completed repairs and added Engineering developing improved design to eliminate abrasion concern:

Unit 1: 97 outage Unit 2: April97 outage PC/M 030-196M Issued for unit 1. New design relay and Unit 2 Control Relay sockets failures Pins relaxation and solder

'oint failure due to cracks.

suspect sockets replaced.

NPWOs: 1A: 95031756 sockets. Work willbe accomplished during the May 96 outage.

(Unit 1 has similar design)

Removal / insertion (PM) and 1B: 95031676 2A: 95031265 vibration. STAR 951721 Report JPN/CSI MET 95-223 2B: 95032588 Unit 2 PC/M to be issued and work accomplished during the April97 unit 2 outage.

Unit 1 fuel oil piping failure Fatigue due to vibration; this engine had underwent high vibration during 8-31-95 valve fail event. STAR 951322 Pipe replaced: others inspected NPWO: 6035 System engineer monitors engine piping closely; visual exam of fuel line components at least monthly.

Identified during trend analysis Radiator replacement is May 96 outage replacement.

PC/M implemented on 1B1 (leaking)

Unit 1 cooling water relief valves Vendor design; valves placed in flow stream.

weeping and not seating.

Units 1 and 2 diesel fuel Underground piping; corrosion PC/M implemented on 1A, 2A, Unit 1 Radiator performance of engine jacket water temp.

scheduled as an outage Job STAR 951575 provided safety assessment to operate until System engineer monitors and trends performance.

Allfour PSL 1 EDG radiators to be replaced during the May 96 outage.

Other three engines valves to be completed May 96 Unit 1 outage (PC/M 171-195 issued)

New design piping incorporates stainless steel guard pipe.

transfer piping failures of unprotected carbon steel.

and 2B: 92-225 8 95-096.

4/17/96

3.5.

>. 2.5.

D 3.22

~OST AVAILABILITYDUE TO EQUIPMENT PROBLEMS - UNIT 1

~MTLYAGTUALS

~YTD AVERAGE TARGET 1.67 1.64

~ g g ~

Q I ~oog g ~o%

% ~

0 8 ~

% ~

g g ~

Q ~ +

oo 1.3 0.5 0.11 Jan-96 Feb-96 Mar-96 II Apr-96 May-98 Jun-96 Ju!.96 I

Aug-96 Sep.98 Oct-98 Nov-98 Dec-98 3.5-LOST AVAILABILITYDUE TO'EQUIPMENT PROBLEMS - UNIT 2 3-th>.2.5. -- ~

D 2.53

~ MTLYACTUALS

~YTD AVERAGE TARGET V

a a ~ & W ~

W H ~

W W ~

R

% ~

W W ~

W 1.28 0.85 0.5 0.

0.03 0

I Jan-96 Feb-96 Mar-96 Apr-96 May-96 Jun-96 Jul-96 Aug-96 Sep-96 Oct-96 Nov-96 Dec-96 4/17/96 SCE Dcpf.

f/xmx(prrI.xlx

ENGINEERING

ENGINEERING Na or Im rovement Areas Improve Configuration Management Controls:

Implement Temporary System Alteration Reduce Open TSAs Reduce Age ofOldest PCMs Complete 6/30/96 12/31/96 Improve FSAR:

Assessment Team Effort Corrective Actions Unit 1 Corrective Actions Unit 2 Maintenance Procedure Review:

Program to review procedure for QC holdpoints in QI 7 Site Contract Coordinator identifies target procedures SCE/JPN performs review

'tatus being reviewed in Outage Meeting SL1-14 Outage Modifications 68 PC/Ms approved for Outage 49 PC/Ms issued by Engineering 19 remaining PC/Ms to be issued Complete 12/15/96 9/30/96 2/97 LEFM 72

TEMPORARY SYSTEM ALTERATIONS TSA Kris Mohindroo - Engineering 50 45 40 35 30 v-25 20 15 10 Good Legend

~unit t

~untt2

X Total Target

.Verget ae-..--.

Oct Dec Feb Apr Jun Date Aug Oct Dec Data Source: Kris Mohtndroo

SUMMARY

STATUS Disci line Mechanical Electrical I&C En Ineerln 0 Bratlons Health Ph slee Construction SCE Total Unlt1 0

14 Unit 2 0

Total 14 0

21 Oldest TSA Disci line 3/4/95 I&C 5/10/94 I&C

PLANT CHANGE/MODIFICATIONS Kris Mohlndroo - Engineering 1 50

~ ~

~ ~ ~

~ ~

~

~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~

~ 0

~ ~ ~ ~ ~ ~

~

~ ~

Good Legend 125 g

100 O

75 0

0 50 Open PCrM Tergal ~ 80

~unit1

~unlt2

~Common

X Total Target 25 0

Oct Dec Feb Apr Jun Date Aug Dec Data Sovrce: Krta MoMndroo

SUMMARY

STATUS-WORKING Disci line 0 enPC/M PC/Ms >24 Mo.

Unlt1 55 Unit 2 20 Common Total 81

0 ST. LUCIEPLANT-10 OLDEST OPEN PC/M's PC/M NUMBER DESCRIPTION DATE ISSUED DATE FRG'D SCH CLOSE DATE STATUS ANDACTIONS REQUIRED TO CLOSE 193-189 Open Blowdown Cooling Water Heat Exchanger Vacuum Breaker Valve Changeout 2/I I/89 12/11/89 5/30/96 PC/M implemented. Action plan to resolve slight periodic leakage problems withpermanent drain catcher. Engr PC/M planned for 4/19/96 276-189 ICW Isolation Valve V21165 Relining 335-190 Check Valve Hinge Pin and Bonnet Modifications on CCW pump discharge check valves V14143, V14147 and V14151 171-191 Resizing and replacement ofMOV'11iermaI Overload Devices on 137 MOV's 186-191 Intake Cooling Water Support Modifications 086-292 Radiation Monitoring Computer Replacement 203-192 Replacement of95 Sigma Meters in the.Control Room and Hot Shutdown Panel do to obsolesence Issues.

12/6/89 7/18/91-Sup 0 3/25/93-Su I

7/17/91 7/I/92-Su I

4/22/92 12/21/92 2/7/90 4/13/93-Sup 0 4/13/93-Su I

9/19/91 Not FRG'd 5/7/92 4/6/93 UNITI PC/M work activities placed on hold U194 fall outage due to required OUTAGE duration-work scope needs to be reviewed and planned for the upcoming U196 outage or PC/M cancelled.

UNIT I PC/M implemented on valves V14147 and V14151. Modifications to OUTAGE V14143 planned fornext refueling outage. Willclose PC/M upon completion ofthe work activity UNITI PC/M implemented on 122 valves.

15 valves remaining to be modified.

OUTAGE EM needs to schedule remaining work Willclose PC/M upon corn letion ofthe work activity UNITI Sup 0 Complete.

Sup. I was budget approved at the MRB I/30/96 for OUTAGE im lementationdurin the1996Unit I outage.

5/24/96 PC/M implemented. ICMhas one PWO associated with two remaining CRN's which is required to be worked to close the PC/M. Willclose PC/M u n completion ofthe work activity.

5/24/96 PC/M partially implemented with 15 instruments installed. Recommend as-building what work has been completed and close PC/M. New PC/Ms can then bc gcncratcd based on planned work activities.

235-992 Supp. 0 -Replace 8h remove Pax Phone Sys 8h install 10/1282 fiber o tio cables 11/3/92 6/30/96 Partial implementation - Final scope to be reviewed and completed 235-992 Su

. I -U adin ofCommunication S stem 5/13/93 5/14/93 6/30/96 Partial im lementation - Final sco to be reviewed and corn leted 094-293 Thcnnal Overload replace, EMTforcondenser sam ling um s

5/17/93 6/15/93 6/30/96 Replace incorrectly sized thermal overload (TOL)heaters for Condenser Sam ling Pm s 2AI,2A2,2B1,8h 2B2

ST. LUCIE NUCLEAR ENGINEERING UNIT 1

1996 OUTAGE SCHEDULE BASELINE SCHEDULE JAN. 2, 1996 UPDATE AS OF APR 8, 1998 R. ENSLEY LEGEND:

TT FUhNOrrOAl A 0H

+

C MRlll@Qilrr IF!%lot W REA Number W Descrfptlon M Date Due W Resp. Disc.

~ Engr'd Matls. Ordered

~

Engr'd Matls. Required M Orlglnal Plant List W Emergent Packages

~

By Outage Start/During Outage W PC/M Not Required W Capital MShaded Box Represents Completed Package SLN95413 10 PMAI9843.777 NONDEPINCORE EDG COP TUBE 4.12.98 4-1S48 FUELS

'ITEMEC PMAI9642492 EDG UNLDVLV 4-26 98 SITE MEC PMAI9843 785 EDe RADPLNM CNTMTRNe LeT 4-29 SB 440.96 SITE MEC PEG ELE STAR 951089 B13308XEVWV REWINDCWP 4.12-98 4.19.98 SITE MEC PEG ELE STAR 94110488 RWT INSP 41298 PEG CIV PMAI96-03470 24" SPOOL PCE 4.1946 SITE MEC SLN 93461.11 A/DCRN'S 4-15.98 ITE MEC/Cl +

O.'F.UEL'tt!i!$

35 5 RPSWtG Jlf'lilt ll I STAR 9516S7 SNI/BBER CRIT 4.15 98 SITE CIV STAR 951049 1A2 DIESEL TK 4.28-98 SITE MEC STAR 951080 PMAI9842-148 RTGB GR ALRM EDG EXHAUST 4.2948 440-98 SITE ELE SITE CIV PMAI98.03479 STAR 951283 CIAS EGG START D/G INDLIGNTS RCP SWEEPS 4 2848 4.29-S6 440.98 ITE ELE/SC SITE UC STAR 950970 PMAI98.03 453 STAR 951138 POLARCRANE DBLJACBONET MV08.1BMTR 4 2448 440-98 440-98 SITE CIV

~

SITE MEC SITE ELE AR 950323A CP LKOFF 4 19.98 ITE MEC PMAI98.02452 480V LC LIFT MSIVBXVP 4-28 98 4 29.98 SITE CIV PEG MEC PMAI96-03.728 IB EDG VLTREG 540.96 SITE ELE PMAI98.03.115 RCP VIBPROB 540.96 SITEELE STAR 951197 1A1 RCP CCW 54046 SITE MEC PMAI98.03.277 LCV-11.24 A/8 5.17-98 SITE MEC PRESS INSL 5404S SITE MEC STAR950585 1B2 ANN A-13 540 98 PEe ELE +

STAR950428 MV09.13 ST NUT 540.96 PEG MEC STAR 950882 EXCORE POS 540.98 SITE MEC +

APR MAY 0:COMMCNIDREISKfla!ESIISSBPIEPRE

CO PROG

0

'7

IMPROVEMENTS/ACTIONS ACIIONPROGRAM r

"v nt Standardize Process:

~

Implement PMAIprocess

~

Implement CR process

~

Transfer all STARs to CR process Status as of4/15/96:

~

Only 5 original STARs remain (none are overdue)

~

No overdue CRs

~

120 overdue PMAB Complete Complete Complete ACIIONS

1. PMAIprocedure (AP0006129) lacks instructions necessary for successful use by plant personnel/training not corxhctaK 2.

STARs were closed without initiating departrrrerrt concurrence.

Training conducted.

'* Procedure revised.

Licensing/QA/PGM/ corrcurrcn~e mallltalIled.

Inrleperrdent Review substituted.

PCR was never approved.

Con!roHed copy distribution of CR/PMAIprocedure.

Implemented CR process (CR process does not require the concurrence)

3. Technical issues requiring near term corrective action are currently documerded on PMAZs with extended due dates.

Technical issues identified have been corrected.

Review a random sample of closed STARs to ensure no unresolved technical issues associated with nuclear safety.

77

coI CORRECTIVE ACTION PROGRAM TR 1996 REPORT

CRs Generated By Quarter 1,200 1,000 1,073 800 600 400 374 329 565 480 200 1st Qtr 95 2nd Qtr 95 3rd Qtr 95 4th Qtr 95 1st Qtr 96

~

130iMonth - Non outage

~

360/Month - Outage 1QTR015.pre

CRs Stratified By Initiating Department 1st Qtr 1996 100 80 60 40 20 57 45 36 36 27 27 26 22 2P 16 6

4 2

2

'2 2

2 A

B C

D E

F G

H I

J K

L M

N 0

P Q

R S

T U

- V W

~ A"-OPS g B=LIC g C"-QA II D=IC ~ E"-OM nil F-"OST g G=QC g H=CA ~ I=MM Q J=SCE

~ K=ENG g L=PM g M=MP ~ N"EM ~ 0"PS g P"RE S Q"NMM IH R=IS 5 S=HP ~ T"SEC, Q V=CHEM 1 V=MPRJ ~ W=RC

~

Operations was the highest contributor

~

QA/Licensing participate fully 1QTR001.

re

140 120 124 CRs Stratified By Causal Factors 1st Qtr 1996 100 80 60 40 33 33 20 13 13 12 12 12 11 7

4 4

4 1

1 0

taCp VC A

B C

D E

F G

H I

J K

L M

N 0

P Q

g A~WritComm g B*WorkPractices g C~Malnt/Test 59 D=Equlp Spec 8 Mfgr~ E=Des Contlg lHF~Worir/Org Plan g G=Man-Mach Interface g H~Plant/Sys Ops ~ I~Tmg/Qual LrgJiEqutp Cond gK~Mgmt Methods (QL~VerbComm QM~SupvMelhods

~ N~ChgMgmt 5O~EnvtronCond iIP~ResourceMgmt

~ Q~Exlemat The top four causal factors or root causes for all CRs issued in the 1st Qtr of 1996 were:

- Written Communication - Deficiencies in the written presentation or exchange of information; e.g., procedures, drawings, vendors manuals, Tech Specs, etc.

Work Practices - The method a worker routinely uses to ensure the safe and successful performance of a task; e.g., lack of self checking, failure to use/follow procedures, etc.

- Maintenance/Testing - The process of ensuring that components/systems are maintained in optimum condition and tested for operability; e.g., inadequate PM, improper reassembly, etc.

Equipment Specification, Manufacture, and Construction - The process that includes the manufacture and installation of equipment in the plant; e.g., inadequate/incorrect spare parts, inappropriate service req'mts., etc.

1QTR002.pre

Written Communication Trend 1st Qtr 1996 140 120 124 100 80 60-40 45 69 78 20 0

1st Qtr 95 2nd Qtr 95 3rd Qtr 95 4th Qtr 95 1st Qtr 96

~

Written Communication - Deficiencies in the written presentation or exchange of information; e.g., procedures, drawings, vendor manuals, Tech Specs, etc.

1QTR011.pre

Written Communication Stratified by Document Type and Department 1st Qtr 1996 Procedures 100 80 75 Written Communication 50 40 30 20 10 48 10 4

60

'0 A

B C

D E

F 40 34 I=

A~Inadequate Oocumenl ProvtstonsR8~Techntcat Inaccuractes NC~Other D=lmproper Chg Implementation g E~Omfssion of Relevant InfoQF~tnsufttctent Info 20 A

B C

D E

F inadequate Documentational Provisions OPS 32.6%

+A=Procedures g 8=Engr Docs (Dwg, PCM, TEDB)g C=Regulatoy PSiF SAR)

QD=PWO gE=Other gF=PO SCE 14.9%

IC 11.9%

MP 9.0%

MM 76%

P 1.6%

Chem 3.0%

OM 4.6%

OST 4.6%

EM 4.6%

IS 6.0%

1QTR005.pre

Written Communication-Engineering Documents "Technical Inaccuracies" Causal Sub-Factor Stratified By Document Type 100 80 75 Written Communication 30 25 20 15 10 26 Engineering Oocuments 60 40 20 34 A=Technical Inaccuracies g B=lmproper Chg Implementation C=lnadequate Document ProvlslonsiID-"Omission of Relevant Info 0

A B

C D

E F

gA-"Procedures g B~Engr Docs (Dvttg, PCM, TEDB)pc=Regulatory (TS/FSAR)

QD=PWO gE~Other Q~F=PO Technicai inaccuracies Drawings 50.0%

1QTR006 re TEDB 26.5%

PCM 23.5%

Work Practices Trend 1st QTR 1996 80 60 40 48 39 44 20 24 1st Qtr 95 2nd Qtr 95 3rd Qtr 95 4th Qtr 95 1st Qtr 96

~

VVork Practices - The method a worker routinely uses to ensure the safe and successful performance of a task; e.g., lack of self checking, failure to use/follow procedures, etc.

1QTR012.pre

Work Practices Stratified By Department 1st Qtr 1996 50 40 30 38 Work Practices Documents Not Followed Correctly OPS 273%

IC 15.9%

20 10 MM 11.4%

PLT 2.3%

LIC 2.3%

MPRJ 2.3%

MP 2.3%

HP 45 0

A 8

SCE 9.1%

NMM 6.8%

EQG 9 1%

EM 6 8%

gA=Docs Not Followed Correctly '8 Req'd VertfNot Performed pc~Other g D=Up-To Date Documents Not Used g E~Self Checking Not Applied 1QTR007.pre

CONDITION REPORTS CONSOLIDATION OF PROCESSES

- FROM STAR PROCESS CORRECTIVE ACTION REQUEST QUALITY CONTROL(form 3900)

NON CONFORMANCE REPORT DEFICIENCY REPORT OPEN ITEM NOTICE DISCREPANT FIELD CONDITION REPORT CONSTRUCTION CORRECTIVE ACTION NOTICB QA AUDIT FINDINGS ISEG RECOMMENDATIONS 10 CFR21 NOTIFICATIONS OPERATING EXPERIENCE FEEDBACK(FOP)

OUTAGE CRITIQUE ITEMS POST TRIP REVIEW ITEMS FIELD CHANGE NOTXCE DRAWING DISCREPANCIES IN HOUSE EVENTS ENVIORNMENTAL CORRECTIVE ACTION RBPORT PLANT LABELLING DEFICIENCIES

- ADDED ON 4/1 OPERATIONS FEEDBACK(Data Sheet 7)

RADIOLOGICAL OCCURRENCES/INCIDENTS/TRENDS NRC SPECIAL REPORTS PBRSONNEL SAFETY(Doctor cases/LTI/trends)

- NOT INCLUDED IN CR PROCESS PLANT WORK ORDERS RELAY WORK ORDERS NUCLEAR SAFETY SPEAKOUT CONCERNS REQUEST FOR ENGINEERING ASSISTANCE PERSONNEL SAFETY FORM 1880/1880A TRAINING TSARS LOGGM3LB SECURITY EVENTS RADIOLOGZCAL DEFICIENCIES 87

0

QUALITY ASS

QA AUDITS/PERFORMANCE MONITORING 5 findings and 1 weakness identified; Finding; Program deficiencies for tracking component cycles and transient events.

Repeat from 1993.

Finding; Failure to strictly adhere to plant procedural compliance in Operations and Maintenance.

3 Findings; STAR/PMAItransition implementation.

Weakness; Failure to self-assess error in estimating critical condition, INDEPENDENT TECHNICALREVI'EWS HVE 41-B PM parts availability, preparation and staging.

Reviewing IHE-96-030, Unit 2 RCS leakage and letdown system reliefvalve lift.

Ongoing assessment ofOEF program compliance and effectiveness.

Facilitating plant self-assessment with support from outside PSL technical specialist, A series of24 hour Conduct ofOperations observations.

QC INSPECTION PROGRAM 93 surveillances were conducted during the 1st quarter '96 resulting in an 8% error rate for the Maintenance Dept. Procedural non-compliance was the principal cause, split between EM, MM 8c Pxoject Groups, IEcC 0% error. (5 STARs, 3 unsat/sat reports were written by QC),

OTHER QA ACTIVITIES Follow-up audit/survey on Plan to Improve Operational Performance.

Unit 1 outage safety review.

Peak shift Maintenance Performance Assessment.

~

OVERALLASSESSMENT Need to continue to focus on procedural compliance and attention to detail.

Maintenance rule implementation, July 10, 1996; we are behind the industry.

Rcv. 2 4-l2-96

LI SING

, IMPROVEMENTS/ACTIONS r

vement Improve Support to Operations in the Use and Interpretation ofthe PSL Technical Specifications:

~

Further evaluate co.benefi ofimplementation ofImproved Standard Technical Specifications gSTS).

~

Improve the Technical Specifications BASES:

Submit PLAs to remove the BASES &omthe PSL Technical Specifications Index Use the ISTS BASES for PSL BASES improvements.

~

Evaluate the need for Technical Specifications position statements.

6/30/96 6/30/96 On-going (post-PLA approval) 6/30/96 Address and improve the implementation ofthe Operating Experience Feedback (OEF) Pmgram.

Detemine the need to track both 10 CFR $50.72 and 10 CFR.)50.73.

Reportable Event notifications, 89

REGULATORYSTATUS Recent NRC Ins eckions RESIDENTS'ERIODIC: 2-21-96 to'3-30-96 (3 inspectors)

HEALTHPHYSICS/RADIATIONPROTECTION: 2-26-96 to 3-1-96 (1 inspector)

SPECIAI INSPECTION - UNIT1 DROPPED CEAAND REACTOR TRIP: 2-24-96 to 2-29-96 (3 inspectors)

MAINTENANCE/SURVEILLANCE:3-4-96 to 3-8-96 (1 inspector)

MAINTENANCE/SURVEILlANCE:3-25-96 to 3-29-96 (1 inspector)

OPERATOR UCENSING: 3-25-96 to 3-29-96 (1 inspector)

OPERATOR LICENSING EXAMS:3-25-96 to 3-39-96 (2 inspectors)

PHYSICALSECURITY PROGRAM FOR POWER REACTORS: 4-1-96 to 4-5-96 (CANCELLED)

Estimated NRC ins ector man-hours as of March 31 1996: 1904 Violations Status

. Four Cited Violations as ofMarch 31, 1996 One Non-Cited Violation as'of March 31, 1996 Potential Violations

1) LER 9&03; Failure to acces procedure when sampling containment

2) LER 9843; Failure to conduct adequate log readings and reviews

3) LER 9&03; Violation ofTechnical Specification 3.0.4

4) IHE 9842; Failure to access procedure

5) IHE 9842; Failure to report completion of procedure

6) Failure to properly disposition out ofspecification CEDM coil stack readings

7) Reactivity manipulations not properly logged Potential Nonunited Violations

1) Improper Health Physics Practices

2) Control of contaminated tools in Hot Tool Room U comin Ins ections throu h June 1996 EMPLOYEE CONCERNS PROGRAM: 4-29-96 to 5-3-96 (2 inspectors)

MAINTENANCEIMPLEMENTATION:S4-96 to 5-1 0-96 (2 inspectors)

ENGINEERING/10 CFR 50.59: 5-13-96 to 5-17-96 (1 inspector)

INSERVICE INSPECTION: 5-13-96 to 5-17-96 (1 inspector)

CORRECTIVE ACTION PROGRAM: 6-24-96 to 6-28-96 (3 inspectors)

MAINTENANCE/SURVEILLANCEOBSERVATION:6-24-96 to 6-28-96 (1 inspector) 90

NRC VIOLA IONS 15 Good Legend ur 10 S~

O o

5 X

~Actual Vtotettons

~Actual Has Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

'9B Date LICENSEE EVENT REPORTS 20 15 Legend 10 CFR 50.73 LER

~10 CFR 50.72 Phone calls v-10 0

5 5

Jan Feb Mar Apr May 'un Jul Aug Sep Oct Nov Dec

'9B Date Data Source:

Ed Wetnkem

FOP's TO BE PROCESSED 30 20 h.o 15 10 10 17 28 Good

~Actual 0

Jan Feb Mar Apr May Jun Jul Aug Sept Oct Nov Dec Time (Month)

FOP's IN REVIEW 25 20 15 h.

10 12 12 Good

~Actual 0

Jan Feb Mar Apr May Jun Jul Aug Sept Oct Nov Dec Time (Month)

FOP's TO BE CLOSED (CLOSE-OUT

SUMMARY

)

35 30 25 27 31 Good

~Actual 20 0

15 10 Jan-96 Feb Mar Apr May June Jul Aug Sept Oct Nov Oeo Time (month)

Szavrczs 0

IMPROVEMENTS/ACTIONS r m vement Improve the Procedure Administration Process to Blare Quality Procedures:

~

Temporary Change Action Plan

~

Convert Procedures to Guidelines Improve the Safety Focus ofthe FRG:

~

Tech Spec Improvement

~

Allother items Improve Training Dept Contribution to Conservative Plant Ops

~

IHE Training Review Team

~

Nuclear Policy 914 implementation

~

Enhance L.O. Requal Exam Practices Improve Plant's ability to implement the E-Plan efBciently

~

Upgmde and Revise the ERO More &quent limited scope drills ValidattJUpdate EP Training Content Implement Configurafion Control process

~

Reestablish Configuration ManageLna)f Group

~

Revise AP 0005745 "Request for Engineering Assistance"

~

Initiate Real Time List for Minor Modifications Develop 20/30 Lists

~

1996 Top 20 list

~

1996 Top 30 list

~

1997 Top 20/30 list Complete Complete 6/96 4/25/96 4/25/96 4/18/96 3rd Qtr/96 7/96 9/96 Complete Complete 4/15/96 Complete 4/18/96 5/5/96 94

l 0

TEMPORARY CHANGES TO PROCEDURES Jim Holt - Information Services 350 300 250 0

200 0

cr 150 R

100 Legend

~Untt1

~Vntt2

~common

X Total Target 50 Oct Dec Feb Apr Jun Date Oct Dec Oata Source:

Jtm Holt

SUMMARY

STATUS Oldest TC (daVs) 89 89 89 89 67 68 Dlsclpllne 0 eratlons Mechanical Electrical ILC Reactor En

~

SCE HP Total Unit 1 23 26 Unlt2 18 25 Common 25 Total 50 76

INDUSTRlALSAFETY - RECORDABLE DOCTOR CASES Klm Heffelflnger - Protection Services 35 30 25 5

nI 20 15 X

'to

~ ~

~ ~ ~

22 16

~

~ 4 ~ \\

11 23 3

3 4

Target ~18 Good Legend

~Actual 1996

~Actuat 1996 Target Oct Dec Feb Apr Jun Date Aug Oct Dec Data Source:

Ktm HeffeNnger

ST. LUCIEPLANT t

BUDGET PERFORMANCE INDICATOR 10v 1996 O626 BUDGET PERFORMANCE ACTUAISTHROVCHMARCH1000 100 M

O 10 I

0 0O 0

ZO OO 10 1996 CAPITALBUDGET PERFORMANCE ACTUALSTTNOVCHMARCH1010 4

X0 E

5 IC OO

'X IX0

~

XX'8VCCET 20 IMONTNLV)

~ACTUAIS 20 IMONAC.YJ

~ FORECAST 2A (MONKEY)

~SVOCET gUMAATIVQ Q ~ACTUAlS FXRRAAmg

~ X FORECAST (CVUAAATIVE)

~>

E

~I 12 10 CAN FES MAR APR MAY AJN AA AUC SEF OCT NOV OEC 97

PSL TRAINlNGOBSERVATIONS 100'/o 80/o 70/o 80/o 50'/o J20 c

40%

30o/o

~Actual 20/o 10/i 0i/o

~Wgp~~ y832 ~8M yeats~ "1885'~ ~$ ~

4088 ~'

7/98

'oI88 9N881 Aluaa". 55jw'2/38 i&%Actual~

Data Source: P. Fincher 1IXr/o 35i/i 0i/o 2/o 95%

98

N'ATERIALS 1

INIPROVEMENTS/AGTlONS r

yement Outage Material Availability:

~

Delivery ofmaterial has been expedited for 90 Pcs

~

No PWOs have been canceHed for lack ofparts Reiuce the Cost ofCarried Inventory:

Reduce value ofinventory to $38 million Reduce the value ofovermax inventory to $2 million 12/31/96 12/3V96 Increase Spare Part Availability:

~

Reduce the number ofrestocks to 500 Reduce the mrmber and age ofnon-outage clerk order AWPs to 70 Reduce the nurnlxr ofpurcb~ requisitions older than 30 days to 20 Complete 7/1/96 7/1/96 99

C

INVENTORYVALUE Dan Quilty - Nuclear Materials Management ro O

100 75 42.3 43.5 Good Legend

~Actual Target 50 Ol5 25 45.2 44,2 39.4 42

~

Target ~ 38 Oct Dec Feb Apr Jun Date Oct Dec Data Source:

Norman Quesada

WAREHOUSE RESTOCKS 3000 2500 2672 2000 n

E 1500 8.

8 1000 500 0.

Jan 1280 Feb Mar 116 Apr June July Date Aug Sept

~ ~ ~ ~

Oct Ncv Oec

~Actual

Target Good OVERIWAXINVENTORYVALUE 3.5 Lr 2.s 1.5 3.3

. ~

4.0

~ e 2.6

~ L'

~

- Actual

~ ~ Target 0.5 0

Jan Feb Mar Apr May

'une July Aug Se pt Oct Ncv Oec Oate

NONUTAGE AWP (STATUS 45 8 48) 180 160 140 120 80 60 40 20 135 188

~Actual

Target Good Jan Feb Mar Apr May June July Aug Sept Date Oct Nov Dec OPEN REQUISTIONS OVER 30 DAYS 250 200 150 100 C

50 111 126 e

~Actual

Target Jan Feb

Mar Apr May June July Aug Sept Oct Date Nov Dec

l NUULhAMMAI EHIAI.S MANAGEMENT 10 OLDEST AWP'S WEEK ENDING APRIL 12, 1998 UN ORIGINATION DATE 1/14/93 COMPONENT/ASSOCIATE/NAME V14143 CHECK VALVEFOR COMPONENT COOLING WATER PUMP 1A DISCHARGE TITLE IMPLEMENTPCM

¹335-190M 9300144401 SL1-14 177522-1 WORK ORDER SCHEDULE STOCK CODE P.O./P.R.

P015383 ACTION COMMENTS PUR DELIVERYDATE 5/6/98 3/18/93 SR-07-1B/SAFETY RELIEF VALVE PERFORM IST FOR LPSI 1B & HPSI 1B PP INSPECTION & RPR SUCTION FLNG LK.

9300884501 SL1-14 37251-3 57194-1 PO 14283 PO 13496 PUR DELIVERYDATE4/5/96 DELIVERYDATE 5/10/96 8/4/93 J5-1 GRAPHITE ANODE FOR INTAKESTRUCTURE REPLACE TRAVELLING SCREEN ANODES 9302132001 SL1-14 217764 P 014417 PUR DELIVERYDATE4/26/98 9/28/94 9/26/94 9/26/94 FCV-24-107/VALVE/CONTROL DISASSEMBLE AND VALVEFOR ES DRAINTO CNDSR INSPECT REPAIR 1A FROM HP EXH AS NEEDED FCV-24-108/VALVE/CONTROL DISASSEMBLE AND VALVEFOR ES DRAINTO CNDSR INSPECT REPAIR 1A FROM HP EXH AS NEEDEO FCV-09-1A2 FLOE CONTROL DISASSEMBLE AND VALVEFOR FEEDWATER PUMP 1A AS NEEDED 8402438601 SL1-14 8402439701 SL1-14 9402439801 SL1-14 594784 595674 595334 594784 595674 595334 1787314 28004-1 582884 582974 56314-1 PO 14506 PO 14417 PO 14417 PO 14506 PO 14417 PO 14417 PO 13477 PO 14489 PO 13539 PUR DELIVERYDATE 4/26/98 PUR DELIVERYDATE4/26/96 PUR DELIVERYDATE4/26/96 9/28/94 CONTAINMENTSPRAY PUMP 1A BORIC ACID BUILD UP ON SUCTION FLANGE 9402441501 SL1-140 27837-1 27972-1 27977-1 29493-1 PO 14609 PO 14489 PO 14489 PO 14308 PUR DELIVERYDATE4/24/96 9/26/94 9/26/94 9/26/94 FCV-09-1 B2/VALVE/FLOW CONTROL VALVEFOR FEEDWATER PP 1B DISCHARGE FCV-24-100/VALVE/CONTROL VALVEFOR ES DRAINTO CNDSR 1A FROM HP EXH FCV-24-101NALVE/CONTROL VALVEFOR ES DRAINTO CNDSR 1A FROM HP EXH DISASSEMBLE AND INSPECT REPAIR AS NEEDEO DISASSEMBLEAND INSPECT REPAIR AS NEEDED DISASSEMBLE AND INSPECT REPAIR AS NEEDED 9402443101 SL1-14 9402443801 SL1-14 9402443901 SL1-14 30300-1 583154 562894 583344 594784 595874 1787314 1787344 594784 595874 1787314 1767344 PO 15018 PO 13539 PO 13539 PO 13539 PO 14508 PO 14417 PO 13477 PO 13892 PO 14506 PO 14417 PO 13477 PO 13892 PUR DELIVERYDATE 5/3/96 PUR DELIVERYDATE4/22/96 PUR DELIVERYDATE4/25/96 UPDA D SUBMITTEDBY: MATERIALSMANAGEMENT~ N. QUESADA p'4050LD.

SL1-14 PURCHASING BACKLOG 350 g

300 250 200 150 SL1-14 PWO'S WITHA DELIVERYDATE PAST 429 REVIEWED BYMAINTENANCE ACCEPTABLE DELIVERY NUMBER TO EXPEDITE OP's REVIEW"MUSTS"TO WORK PWO'S CANCELLED 267 240 148 92 82 0

~

C4 tA CD h

4 0

FOR FULLEXCEPTION LISTINGREFERENCE FILE F:tCOMMONWMMPSL'KXCEP483(LS

~TOTALBACKLOG~ LINEITEMS ORDERED Previous Da 's Backlo Incomin P.R.'s Line Items Ordered Line Items To P.E.

Total Backlo 4/09 4/10 4/11 4/12 4/15 235 208 196 146 119 44 43 13 24 30 71 51 61 50 25 4

2 208 196 146 119 124 4/16 124 22 40 106 4/1 7 4/18 4/19 4/22 PURBKLOG.XLS

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