ML17228B478

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: ML17228B476 ML17228B478
References
NUDOCS 9604300241
Download: ML17228B478 (149)

Text

e 9b0430024i 9b0423 PDR ADQCK 05000335 P PDR

ST. LUCIE STATUS MEEllNG AGENDA FOR APRIL 18, 1996 9:00 AM. SSB ROOlyI 4011 NIN W. Bohlke J. Scarola CONDENSER WATERBOX PIPING D. Denver MAINTENANCERULE M. Snyder STORES INVENTORY REDUCTION L. Rogers IHE 96-030 RCS LEAKAGE J. Porter E-PLAN REPORTING K. Heffelfinger FFD AUDIT

SUMMARY

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

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

T. Kreinberg

OPERATING REPORT REC

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

<<vgS<<.'<<aa~~v"",'<<V)t<<p,,<<a)err <<: Wr)t "crvs'frt<<<<rtrtot5$ 4~ittf'"Wjtttf)kc<<'Nc$)$$ <<cc<<<<cf4@4rtt <<I)',<<wrcst"r<<$ .'-'~'1 ~vJS'.""tfr<<5/j:",$ ~~ S5)r'c rrrst>p so

~ t

~<<

iI ~g) 9I )s )) rt) )t)

) )c) st S<<

IS

<<M P,A tf c)

MonfhiyAverage EAFsg551)k Lost Generation SertiH Loss

~ 1st 4S94 Tats oats D$ 0$

~ $ 502 Ba)rn rn a Not)tta) ~

EOUIVALENTAVAILABILIIY Cln)dlt rr asa snv FACTOR UNIT 1 100 ~~

ssk Sr,e 75 JJOC%?as') V mrs 4

( ~ ~ ~ ~

Goo4 Zl

~ <<

50

~<<

Unit 2 Equivalent Availability OAILYEQUIVALENTAVAILAEIUTY 98 O070 ocv7cne es ot 4/15/96

et/ +,'. I /n'0 <</ad+~ L'15~7'd!.~4$ .Sc'c'p";

<<" oc'~~c "/3c. cc'a>>n/xr ~J7>, c. ~dx ..~~a~>W'dccCXC i Pi a'40, .

cc c~c lc

-'cCX II It i,

4 p 00 l' " "

Fl /4 I 'cl>> xxc te/'7, xc I

~ c cc 00 SA 9 I Al

I xl

~ c Tl

~/

g xi lC r,'~

g g /c fi In Soups 4ISate 4WSS enxn 4IS/00 4l1ccce xntl90 4nel90 4/10I00 4h850 ldaCC007AVOI09e EAFe95.7800 Last Gene/Stion SIVVII Loss Reason 410 Vvbi>> Velve 7en

~ 177 77$ VAcccctxx ptline cepex, 4000 vcceccxx pipins ceps.

4070 Vececixxc pfpia cepex.

4101 cccxcxec pccno cepec.

4177 4107 vnceecx p'ceo cepev.

41S1 Veccctxx p'Ciine cepar.

Oeccci en 0 IxxvEcexn Pcnsedcce Cepccey ei 000 Cln/

EQUIVALENTAVAILABILflY FACTOR UNIT 2 tetccxC ~

100 ~ ~

75 Jxcactx CXLO . $ ~~~~~~~

xc 50

~n Feb

AUTOMATICREACTOR TRIPS Jeff West - Operations Legend Good ~Actual Target I 4 I-3 O

0 2 2 2 2 R

Target ~ 1 0 0 0 Oct Dec Jan '98 Mar May Jul Sep Nov Date Data Source: Jeff West

CONDENSER XATERBOX PIPING

ST. LUCIE UNIT 2 CONDENSER WATERBOX CORROSION 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 Description xxxxxmcolxxxxx xxxxxxxxxxxxxxx xxxxxxxxx Person Responsible II Date Comptete

= Scheduled

= Working

= Complete rea e pe Panel Member flock Ctmfno II Expert Panel Review Ol Perform Criterfe Cfmtno II Tees rrrrQ nants ntrfr Perform Second

.repose'rIItel felts ITR Of Mafnt Rufe 0 n fgrn emAtSt.Lucre ttntrrftl r.:.::: II JAN 10 JAg 31 FEB 16 FEB 28 MAR 16 MAR 22 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.

HISTORICAL REVIEW 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 IMPLEMENTATION MAINTENANCERULE SCHEDULE 1996 Updated 4/t7/96 LEGEND:

XXXXXXXXXXXXXXX Descrlptfon XXXOOOQOQOIXXXX XXXXXXXXXXXXXXX Person Responsible

//

XXXXXXXXX Date Complete

= Scheduled Document

= Working w Bash Ol Perform Criteria Snyder II w Complete Issue 5'I Expert Panel Qtr Maht Rute Review Of Report PCP Snydsr Snyder II II Expert Panel MR Termhofogy Program Review a(I) s Roslers Made 8, Compliance Plan-And Goals Phced Finatrze Snyder Snydsr II Cfmho II II Expert Panel Site TV For ADM 17.08 pgra e a t Increased MR Procedure Rufo Quarterly Review Perform Criteria Awareness Upgrades Report Format Walcheskl Snyder II Snyder II Walchoskl II II Site Newsletter QA Peer perl ans System Review Ol Falufe For Msinl Rute Review At Awareness SONGs Performance Bash Notebook Snyder Clmlno II Watch>>ski II Watcheskl Il II Contractor ewew oveop rogram ncorpora o Revise System Orlenlagon OIPSL For Structures Scophg Sys Engheer 4 Maintenance Rule Oescdptfon Initai Training alcheskl Contractor Snydsr II II Engineering II II Watch>>ski II Maht Rute Imput Reformat Mahl Rule ~na ITR Of Mahtenac>>

r nt DNerence ln Document Ba s For Sys Not In Create System For POD System Tralnhg For Health Oescripthn Management Rute Sys Oesaiption Maht Rule Report Contractor Welch>>ski II Contractor II Snyder II QA/Snyder II II Snyder II Snyder II Expert oot xla e Compiet e neo as s Mshlenance Rute Train/Inform Gen Per/orm First Panel Member Malnt Risk SSE For Exctuding Tie To Pop Of Pfsnt Perlodh Notebook Assess mania Scophg Systems From MR TEDB MahlRuie Assessment V/ncent Contractor Contractor Tralnhg Snyder Clmlno II II II II Cimlno II II II APR16 APR 30 MAY 16 MAY30 JUN 15 JUN 30 JUL 30 AUG 30 FaUSERSV/IAINTRU3.PRE

REMAININGTASKS FOR MAINTENANCERULE IMPLEMENTATION RESOURCES FOR FINAL MRVLE IMPLEMENTATION 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 COKIINUED IMPLEMENTATION 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 of Reviewed DME Material Removal form Site (Quilty - indicator)

LAR 4-17-96 dmesumry

NUCLEAR MATERIALS MANAGEMENT WEEK ENDING APRIL 12, 1996 14 ~

DME MATERIALREMOVED FROM SITE GOOD 4 ~

12 10 8

W 8

TARGET > ZERO DOLLARS BY IO/Se 4 ..

I I I I I I I I I I I I 1 1 m' g

GOOD 10 DME VERIFICATION REVIEW 8,8.7 8.1 8.1 7

e.

TARGET ~ZERO DOLLARS BY 10/88 I I I I I ~ I o R o o4 o o, g i3 IO UPDATED AND SUBMITTED BY: 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:

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

-The high back pressure was the result of V2382 being in a throttled position versus fully open.

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

Corrective Actions:

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

-Review plant policy on use and maintenance of valve position indicators.

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

CVCS I.ETOOWN

/SHUIOOWH COOLIHOf

~ CY 220 IP

~ CV 22010 LS TDOWH SACK fAKNUI%COHNOL VALVE f

PISVP. ILT2 II 2h U2 OHLY lOCAl flOW TPIIC IIAOLIHT WOCATNI LCV 2 I ISO ACE IS LSTDOWH ISQLAllPI NISI~ la 00 VALVSS OWKWA SYSTEM PLOW INST fITOSI f TO LASH T QSI ICS LCVSI LS TOOWH LSVSL COHThOL VALVS RGHX'. REGENERATIVE HEAT EXCHANGlIR LSTDOWII STAAWIT PUfllf LOHX: LETOOWN HEAT EXCHANGER flLTSA

$1

( lOOP l SEAL P~T5fI ~ I cI fIII e

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

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

- Nut level Increau

- Leakage ceaaed I -30 GPM.

vrL IXRS bypaaaad EX E Waiukwn Preaaure Teat RELIEF VALVEFLOW -ERDADS conltmN SPENT IN TANK DRAIN C CTION CHARGE P PACIONO Wa~

TO HUT tV2531) -2MO GPM leak OF S HEADE EDT/CDT Preaaure Teat Preaaure Teat TKRO ALL LEAKAO H ~INT Pfeaaure Teat RE VALVE S LOW Bench Teat SaUafactory PACKING GE Preaaute Teal RELIEF V LEAKAGE Bench Teal SaUafactory VGCH KAGE IN Preaaure Teat Preaaure Teat HIGH SYSTEM PRESSURE AT V2631

- OPSlog-Kl hP ION CHANGER - OburvaUon on return to aervke

- No atarm received Hlhp S INER OPS Iog

-ObaewaUon on return OPE ACR ERROR to aarvke MIS

- V2382 reported aa 2-3 turne from full open EO VALVE VALVEPOSITIONINO MECH NO - Allvatvea contlnned to cydo aat.

SYP ALVE - No credible falure mode VAL TOR PR for Hl hP

-ObaarvaUon on return to aervk>>

roeRanvacE/Faut neo os& <

6-0 E-Plan Event 1 tl Conflicting Views of the 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 it RCS leakage ifit is 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 will instill 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 EAL for 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 veriiy that 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 OUTAGE MANAGEMENT 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 4/23/96 Westinghouse SG Tube Plugs 4/23/96 Pressurizer Code Safety Valves 4/23/96 Reactor Vessel 0-Ring Replacements 4/23/96 Main Generator In@ection 4/23/96 Issue Opemtions and Maintenaiice procedure upgrades Due: 3/29/96 Maine Target: Complete 4/26/96 Improve Outage Management:

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

17APR96 Draft Outline PSL Unit 1 Refueling Outage 1996.

47 Days Span APRIL JUNE 04:00 Turbine and Rx Shutdown 16:00 Hang Turbine Clearances 624:00 HP Overhaul and Blade Rin Re iacement 112:00 Generator Disassembly 120:00 Perform Initial Generator Test 120:00 Gen, Stator Wed e Re lacement 671:00 Gen. Winding Module Installation 30:00 Generator Final Stator Testing 281:00 Generator Reassembly 12:00 LiftTest Main Steam Safety Valves Return Main Steam and Draw Vacuum 42:00 Begin Cooldown 30:00 Safeguards Test 24:00 Complete Cooldown and Depressurlze 628:00 SG Ins ection and Tube Plugging 18:00 Rx Disassembly 30:00 Polar Crane Load Test 30:00 Complete Rx Disassembly 24:00 LiftRx Head and Inspect 0-rings 67:00 Fill Cavity, Unlatch CEA's, Remove 8 Incores, Remove UGS 240:00 'A'PSI, SDC, CCW Work Window 80:00 Core Offload 240:00 'B'PSI, SDC, CCW Work Window 09:00 Remove Core Support Barrel 120:00 Rx Vessel Exam 240:00 Valve Work with Freezes 08:00 Reinstall Core Supprt Barrel 80:00 Core Reload 60:00 Install 8 New Incore Detectors, UGS and Latch Extension Shafts 16:00 Set Rx Head and Final 0-ring Inspection 66:00 Rx Reassembly, 64:00 Fill and Vent 84:00 Heat-up and Pressurize 16:00 NOP NOT, Ql-11's and PMT's 32:00 Rx Start-up 103:00 Hold In Mode 2 for Turbine Completion 01:00 Roll Tur

UNlT 1 'l996 OUTAGE 1400 1287 100%

PWO Planning Curve 1200 IQ 1000 I-Ill 800 O

U R

Z 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 NPWO's

'16-Apr-96 To Date GRAND A E U Totals TOTALS LMD Department -" APPROVED = E-WORK = UNAPPROVED After 27 FEB 96 1 MECHANICALMAINTENANCE 40 67 2 INSTRUMENT & CONTROLS 0 30 40 3 ELECTRICAL MAINTENANCE 13 10 26 C PROJECTS /MAINTENANCESUPT. 21 TOTALS 26 163 A E TOTAL EMERGENT NPWOs PLANNED (Status >=30): 92 21 113 EMERGcvn.xts No/e: EWORK requires evaluation an proval prior to betng APPROVED 4ltrvss 5.

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

68 3

Major Packages ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 1 Minor Packages ................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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:

~ REA Number W Descrlptlon M DateDue a Resp. Disc.

TT

~ Engr'd Matte. Ordered

~ Engr'd Matte. Required C3 M Orlglnal Plant Ust HW Emergent Packages EB ~ By Outage StartrDurtng Outage

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

WBhaded Box Represents

~ ---',!;:! :Completed

, Package PMAI 984I3 777 PMAI 98412492 PMAI 984I3 785 EDG COP TUBE EDG UNLD VLV EDG RAD PLNM CNTMT RNG LGT 4.19.98 4.28.98 4.29.98 4<0.98 SITE MEC SITE MEC SITE MEC PEG ELE SLN 95411 3.10 STAR951049 TAR 951 080 PMAI 964I2-148 PMAI 96.03 728 NONDERNCORE REWIND CWP 1A2 DIESEL TK RTGB GR ALRM EDG EXHAUST 1B EDG VLTREG PRESS INSL 41298 4-19.98 4.26-96 4.2948 440.98 540.98 540.96 FUELS PEG ELE SITE MEC SITE EI.E SITE IV SITEELE SITE MEC PMAI 96.03470 PMAI 96-03479 STAR 9S1283 PMAI 9603 11S STAR 95056S 24 SPOOL PCE CIAS EDG START DIG IND LIGHTS RCP SWEEPS RCP VIB PROB 1B2 ANN A 13 4.19.98 4 28.98 4 29.98 440.98 540.96 540 98 SITE MEC PEG EI.E ITE ELE/SC SITE LIC SITE ELE PEG ELE SLN 93461.11 STAR 950970 PMAI 96 03453 STAR 951136 STAR 951197 STAR950428 AIDcRNs poLAR cRANE DBL JAC BONET MV 08.1 B MTR 1A1 RCP CCW MV 09.13 ST NUT 4.15.98 4 2448 440-96 440.98 540.98 540-98 ITEMECtCI + SITECIV + SITE MEC SITE ELE SITE MEC PEG MEC STAR 951667 TAR 950323A PMAI 98 02452 PMAI 98 03 277 STAR 950582 SNUBBER CRIT CP LKOFF 480V LC LIFT MSIV BXUP LCV 11 24 A/B EXCORE POS 4 15 98 4 19.96 4.2646 4.29.98 5.17.98 540-98 SITE CIV ITE MEC SITE CIV PEG MEC SITE MEC SITE MEC +

APR MAY G.COMMONDRBSICLNESu998PIE PRE

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 UNIT I

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 UNIT 4 '96 REFUELING OUTAGE GOALS GOAL ACTUAL 1'. NUCLEAR SAFETY PROBLEM ZERO ZERO

2. PERSONNEL SAFETY

- LOST TIME ACCIDENTS ZERO ZERO

3. DOCTOR CASE INJURIES

4. MEET OR BEAT THE OUTAGE 35 DAYS

- SCHEDULE DURATION < 40 DAYS 11 HOURS 21 MINUTES

5. MEETOR BEATTHEOUTAGE

- BUDGET < $ 22.5 MILLION < 22.5 MILLION

6. PERSONNEL EXPOSURE LIMITS < 215 MANREM by dosimeter

7. PERSONNEL CONTAMINATIONS (ANY CONTAMINATIONRESULTING <10 3 IN A SKIN DOSE)

8. CONTAMINATEDFLOOR SPACE 2

WITHIN 14 DAYS POST OUTAGE <1750 ft 469 ft 3

9. CUBIC FEET OF WASTE GENERATED - <6400 ft 2400 ft

10. OUTAGE RELATED SIGNIFICANT CONDITION REPORTS <10 6 27

UNIT 4 1996 REFUELING I) 3 Loss Polar Crane Inspection/Torque Aad Ctps

2) 44 Loss Polar Crane Large Hoo'k Impacted Stops/

AHEAD OR BEHIND SCHEDULE Caused Damage

3) 14 Loss Pokrr Crane cable replacement on Ihe man hoist HOURS 4) 16 Loss Polar Crane cabte replacement/rework the 31 DAYS, 19 HOURS slack cable grist swdch 100

5) 5 gan CADM ductwork removaVcondsaals

6) 14 gain Rx vassal datensenkig set up 80 7) 5 gsn Ax head 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 60 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 40 11) Core unload progressng on schedute

12) 6/G lube ptuggingis crit+a(path

13) S/G tube plugs ahead ol schedule/

20 CADM canopy seals have Iha crdrcat path

14) 5 gain canopy seal clamps on crilioal path

15) I galri csnopy seatclarrps ahead 2$ tdta27 16) 4A RHR Hx repair now has crilrcsl path 23 17) 4AAHAHxoncrdicalpath 2$

18) MOV.750packng gland damage and (20) movals lasting has crdical path

19) 24 gain commenced core on load/bvtk work activities (<rushed 1220 21 20) cora on load progressing (40) 32

21) core on load progressing 31

22) Ax cavdy dian/Rx head seVrx cavity decon 6 paint 7 23) Rx head stud hold plug removals cteanng (60) 6 15 Ie 1215 Sel vp (or lensiolng 10 11 It 13

24) 7 gain Ax head stud insenion 6 tansiorung 5

25) On schedule (80)

26) Gn schedule

27) On schedule

28) 8 loss Sslegusrds lasting ~ Bus cles my relay (aded (100) 1112 212121 I~ 29) 4 loss Sategusrds lasting/MG 6 relay/Kesavi relay (sited ovrxos I I 5 I ~ II 1$ II 21 2$ $1 $$ $$ $$

1112 e e e e.e~~e'e~e

+>+>+v @>@>@-@-@>@>@-@>@>gg e'e eve.emcee e e e e e ~

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/

rb ~0 ~+ ~b ~co ~rb (0 ~2)r ~Tx ceo ~rb ~0 w 152 43 TE432 ACS TC reptacemenl

32) 4 gan Aeschedrda Rx protection teal 5 RCP cossl down data OUTAGE DAYS 33) (7 toss CV 2908 pdot valve tailed

34) ~ 1 loss API'5 K 8/D 10 signal condikoner/connector ACTUAL ctearxng delayed start o( lower power physios

35) 29 loss lvrbna tube od system msllunction 6 repair

36) UNIT Otd LIRE 0 Cue JILVLIIIJI WIAtNrrr sr

SHIFT DIRECTORS SHIFT DIRECTORS DEPUTIES DIRECTOR JEFF WEST FRANK McGLYNN CHRIS BURTON JOHN BRADY DONNA CALABRESE BOB FRECHETTE LEE LARGE TONY MENOCAL TS HARRY BISHOP ROBIN MIXON

• UNIT2- FRED GIGELE, CARL CRIDER

Outage Projects - SL1-14 Project Lead/ Responsible Task Manager Manager 10 Year Reactor Vessel and Core Barrel inspections K. Mayhew March ese Contingency plan for repairs (Supv:G. Pustover) Denver Pressurizer Code Safety Valve replacements C. Ward Denver Flange work/mods RPS NIS Upgrade Repair detector positioning devices G. Pustover Marchese Hardware replacement (detectors, drawers, etc.) R. Olson Steam Generators(Overall) R. Ball Marchese Westinghouse SG Tube Plugging 8 PAP (Supv:Flowers)

RWI bottom inspection R. Frechette H. Johnson water management plan RCGVS Valve replacements and piping modification G. Rodgers Marchese Incore Instrument Assembly replacements R. Olson March ese V07161 and bypass replacement G. Rodgers Marchese Polar'crane load test D. English Marchese TCV-1~B replacement H. Fagley Marchese 1A 81B LPSI common piping valve work N. Motley Marchese EDGs overall McLaughlin/Ware Wood Charging header isolation valves repair T. Sanders Marchese SE-02-1,2,3 FCV%7-1A/1B maintenance T. Sanders March ese Springs, Air press s.p., elastomers SIT valve maintenance Quantify leakage pr~utage '.N. Motley Fulford N. Motley Marchese V3634 stem replacement ICW piping at intake structure external corrosion inspection R. Ball Marchese Repair contingency (Supv: Yates)

Purge Valves C. Swiatek Wood RCB permanent A/C modification, H. Fagley Marchese H JTC replacements R.'Olson Marchese HP turbine 8 seal ring replacement R. Ball Marchese 30

a Condenser Tube Cleaning System and Debris Filter installation Atmospheric Steam Dump valves seat repair D. Sipos N. Motley D. Sipos Marchese Main Generator R. Ball Marchese Maintenance/ModiTication Nichols/Wolaver Turbine turning gear auto/remote engagement repair Wolaver Wood RCPs (all issues) B. Haines Marchese ESF testing P. Fulford H. Johnson SIT dump testing J. Hallem H. Johnson ECCS full flow testing P. Fulford H. Johnson OPS-reduced inventory/mid loop mgr R. Weller H. Johnson OPS-refueling R. Weller H. Johnson Clearances R. Lamb H. Johnson OPS procedures R. Weller H. Johnson OPS-vent and drain hoses C. Johnson H. Johnson MOV Coordinator-Ops A. Haii H. Johnson Pressurizer(Overall) C. Ward Marchese Reactor Maintenance B. Haines Marchese Pre/Early and Post RCS 8 RCB Inspections R. Riha H. Johnson Relief Valves N. Motley Marchese Cranes English Marchese RCB Cleanup M. Goodiel Marchese Reactor Cavity Seal Ring T. Kreinberg Dawson Maintenance Procedures Menocal Menocal Engineering Packages Denver Denver NPWO Planning Menocal 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 LAN support 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 SG4-1 B.WPD 32

ST. LUCIE STATUS MEETING APRIL 18, 1996 STEAM GENERATOR INSPECTION II MECHANICAL8 WELDED TUBE 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 of the 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 SG4-18.WPD 34

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 of Tubing.

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 for Temperature 8.Locked Support Plates Bladder Installation to Mitigate Leakage during Test Bladder Tested for Extrusion Through Fracture Face If Tube Burst Occurs:

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

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)

SG4-18.WP0 36

~ VESSEL SUvvonz s COpp INSPECTzo

0 REACTOR VE SEL EXA1VHNATION TOTAL SCHEDULED DURATION: 144 HOURS ( 6 DAYS)

EXAMSERVICES PROVIDED BY: SOUTHWEST RESEARCH INSTITUTE

~ EXAMINATIONS OPE:

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

- CIRCUMFERENTIAL,LONGITUDINALAND MERIDIONALWELDS

- INLET AND OUTLET NOZZLE TO SHELL WELDS

- INLETAND OUTLET NOZZLE INNER RADIUS

- INLET AND OUTLET PIPING WELDS

~ EXAMINATIONMETH D

- ALLEXAMINATIONSWILLBE PERFORMED FROM THE ID OF THE VESSEL

- EXAMINATIONEQUIPMENT: " PAR DEVICE" OPERATED BY SWRI

- SUSCEPTIBLE AREAS WILLBE EXAIVQNEDFIRST (IE NOZZLE TO VESSEL WELDS)

~ PREVIOUS ULTRASONI EXAMS PERFORMED:

- BASELINE KDQdINATION(PRIOR TO OPERATION)

- FIRST 10 YEAR INTERVAL(APtuL 1983) 37

e CONTINGENCY PLANNING

- SWRI EXAMINATIONEQUIPMENT FAILURES / CORRECTIVE ACTION

- FLAW EVALUATIONS(FRACTURE MECHANICS):

JPN: SUBHASH KURANA TRIICtUI Itlll!GRI ROC O APtBCH

~ KNO INDICA

- A PREVIOUSLY UNRECORDED ASME SECTION IIIREJECTABLE FLAW HAS BEEN DETECTED DURING A REVIEW OF RADIOGRAPHS.

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

ADJACENT TO THE CORE BARREL LUG@60 DEG.

- FLAW HAS BEEN CHARACTERIZED,BY CSI AND IDENTIFIED ON STAR 951893.

- WELD AREA CONTABKMGFLAW WILLBE 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 LIMITING PLUGS 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 VISUAL EXAMINATION USE OF ECT AND/OR UT FOR FURTHER CHARACTERIZATION OF INDICATIONS D BL

~ CSB PER ASME SECTION XI VT 3

~ REPAIR CONSISTENT TO 1986 VISUAL

INITIALENGINEERIN EV LUATI N ATI

~ 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 WILL BE ON SITE MOST CONDITIONS CAN BE EVALUATED FOR 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 EVALUATION INCLUDING FRACTURE MECHANICS. REPAIR MAY BE REQUIRED

~ PHYSICAL REPAIRS THIS OUTAGE NOT REQUIRED UNLESS EXTENSIVE PROBLEM DISCOVERED.

~ REPAIR BY WELDING NOT LIKELY-I REMOVAL AND REINSTALLATION OF 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 of GeneratorfExciter (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 it is recommended to reduce power until vibration levels go below 20 mils, which could be approximately 1 to 30 percent power reduction.

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

~ We are only monitoring 6 Coil Ends on each end of the generator out of a total of 42 coils or 84 End Turns.

Qgtions:

~ Install RF Monitor per Factory Mutual ifwe do nothing (Cost Approx. 100K)

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

~ No one has had success doing a partial

~ Westinghouse has never performed a partial of this 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 for what 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

~ ABB wanted a 6 month lead time

~ ABB has 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

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PRESSURIZER CODE SAFETY VMVES

ST. LUCIE UNIT 1 PRESSURIZER SAFHY VALVE SPRAY UNE V.1200 PRESSURIZER CUBICLE V-1202 V 1201 PRESSURIZER ]

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 AMBIENT AIR TEMPERATURFS AT TEST STANDS TEPI'ATCZKD 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

l S VALVE BODIES- 1630 LBS TO 10000 LBS PURCHASED NEW BLOCK VALVE BODIES TP~'ED FOR THERMAL EFFECZS TFATK) FOR TAIL PIPE LOAD EFFECIS

PZR SAFETY VALVE NOZZLE LOADS 14000 MY Mz M x 12000-m 10000 IIz- 8000 6640 5867 eooo-0 4033 4000 3112 2914 2507 2000 168517631803 981 992 753 693 790 763 456 357 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 20164.1 W 17301.4 14438.8

'555 11675.B 5" W 871S.08 gc cc5~

5850.30 5~WM~',

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46

IlNPROVEMENTStAGTIONS V

Strengthen the Management Skills of our Supervision:

Include the following attributes in personnel performance appraisals:

- Adherence to procedures

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

if Evaluate and modify, necessary, 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.

Interview forenoon and supervisor incunkents to ensure they '/30/96 are willingto meet the eyectations of the position in handling employee performance issues.

Improve Labor Relations:

~ Reduce number of union 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 Te>sel 1905 eas 810 811 I 800 802

~ 790 780 Tarsat 1000 710 770 . 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 26 25 20 18 15 14 12 10 10 28/96 3/8/96 3/18/96 3/25/96 4/1/96 4/8/96 4/15/96 4/17/96. ops MM TRNG Oate Data aubmlted by: CD Scott- HFt Download Population 340 320 300 280 260 240 220

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

~ 9 8

q6

>. 5 >. 5 4 4 O 3 O3 62 82 1 1 12 months endtn A M J J A 6 0 N J F 12 months endln A M J S 0 0 J B STAFF 2.74 2.80 2.68 2.59 2.57 2.57 2.61 2.49 2.04 1.98 1.91 1.78 JB STAFF 6.85 6.51 6.56 6.57 7.24 6.21 5.93 5.64 5.95 5.16 5.45 6.37 SL 2.01 2.07 2.03 1.95 1.84 1.89 2.01 2.13 2.25 2.15 2.13 1.99 PSL 2.48 2.30 2.07 2.02 2.03 2.04 2.32 2.57 2.78 2.71 2.87 TN 1.93 1.88 1.79 1.90 1.?7 1.83 1.92 1.90 1.77 2.13 2.14 1.99 PTN 4.41 4.69 4.71 4.67 4.41 4.49 4.68 4.69 4.46 4.60 4.55 4.40 NUCLEAR DIVISION BARGAINING UNIT ABSENTEEISM 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 PSL 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 OPERATIONS STAFFING COMPLEMENT 40 II COMPLEMENT Q CURRENT 35 3t 3p

~0 30 28 0

I-u20 0

EL 12

~ 10 7 7 t

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

OPERA TlONS STAFFING

~P OF POSITIONS

---.-.MIN

.. MAX 145 144 W ~

143 140

.136

~ ~

~

.'3' H

~ ~

136

'36

~

135 '

134 0 131 130

~

~

\

127

.~'

0 ~ 124 \

124 0 125

~ 124 0

0 120 l 120 1

\

115 115 \ *115 1

112 110 Jan.90 Jan.91 Jan.92 Jan.93 Jan-94 Jan.95 Jun-95 Jan-96 Mar-96

.YEAR

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

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

OPERATIONS IMPROVEMENTS/ACTIONS OPERA'HONS r vement Reduce the Number of Operator Work Arounds:

Reduce the number of OWAs 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. Will be on track as of 4/19/96.

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 79 98 103 101 41 55 47 44 TARGET 45 48 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 OPEN rs 60 ~

% ~ TARGET

~ -l.-- ~ ~

40 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 PROCEDURE¹ XXXXXX DESCRIPTION XXXXXX DATE OUE XXX RESPONSIBLE SHADED BOX REPRESENTS 1.0030121 COMPLETED PROCEDURE Rx Plt Heatup UPGRADE

~o D. Wislams 2-0030121 S D DRAFT S SUBCOhllMITTEE Rx Plt Heatup R INDEPENDENT REVIEW D. Wilsams F FRG APPROVAL heccrieieXeo S D1 DISTRIBUTION 14I030122 Rx Stertup M. Koeebchetc IND REVIE R 2-0030122 Rx Startup IL Koyebchetc 1k 1-00301 27 1.0030120 1 0030124

. '8 Rx COOIBown Pre ebii Chock&a Turbtne Starlup O. Williams D. Brown D. Brown 50.59 Req. F DRAFT D ~eo S 2.0030125 2 ON0127 2.0030120 2.0030124 rorhrrre axeman RX COOI5OWn PlosQrr Chechorl Turbtne Startup D. Brown D. Witsams D. Brown O. Brown FRGApprov F IND REVI R DRAFT D hcbcccrneee S 3I22I9B 4I4/96 4I19196 513195 . 5I17IBB opERAtloxs pRocEouRE upoRAoE PHASE 1 JKS e/rrrre

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

XXXXXXXX PROCEDUREB XXXXXX, DESCRIPTION XXXXXX RESPONSIBLE XXX STATUS SHADED BOX REPRESENTS COMPLETED PROCEDURE UPGRADE/REVISION D DRAFT COMPLETE 1-1800024 Dl DISTRIBUTION Fa S Dice Cevay P P/ocessfng Kogefschatz F T FRG Processing P S SUBCOMMITTEE 1-230020 1.0120023 N2 Sys Normal RCP Normal Bonsag Lorentzen FRG F Draft D 1.01 20021 1.080050 1.0700028 Drain RCS MSIVTest FdrwbTeel Kogelschatz Scott Lorentzen Processhg P FRG . F Draft D 1.0210021 14410021 1.0210020 VCT H2/N2 SIT Normal Chg-t/D Normal Bonsatl Pennenga Patterson Processing P svbeeeeii/see D Dratt D 141 10022 C 1-1010020 1 0700021 Eiden esca Inst Alr Sys OP Cond/Feed Norm Kogefschatz Lorenlzen Pennenga Processing P FRO F Draft D 1-081 0021 1-1210051 a/cede X Se WR Nl Func WEEams B. Scott Draft D Draft D 1.0910024 D 14120020 Bus Removal FIB & Vent RCS Pennenga D. Brown seeeeeiersee S Dra/t D 3/16/98 3/27/98 4/6/98 4/12/98 4/19l98 4l28//98 OPERATIONS PRE4WTAOE PROCEDURE REVIEW OIITAOE

1996 lIAN REM TARGET 400 Unit 1 Refuegng Outage Outage Budget~ 310 ~ ~

~ r 300 5 ~Actual 200 ----- 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 Unit 1 Refueling Outage 70 60 o 50

~Actual

~ - Target 20 10 0

~ ~

2,r 2

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

ST. LUCIE PLANT CONTAIIINATEDFLOOR SPACE 4000 Post outage recovery of 3500 contaminated floor space. \

~Actual

~ I - - - - - Target 3000

~ ~

~ ~

2500 Unit 1 Refueling Outage 2000 1500- f~

Inaccessible cree BstÃtÃlserhs wrrh Twkey PoH end '

1000 ksspksa wkh 250 280 12 kskssky preclksss.

500

~ ~ ~

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

Unit 0 CPI (Chemistry Performance Index)

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IMPROVEMENTS/ACTIONS r ye ment 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 LUCIE PLANT MAINTENANCEPROCEDURE UPGRADE PROJECT TASK N: DEVELOP PROCEDURES/GUIDELINES FOR FREQUENTLY PERFORMED MAINTENANCEACTIVITIESWHICH CURRENTLY EMPLOY THE USE OF VENDOR TECHNICAL MANUALS 4C V<<$ SUC Cht Bd tndcuas s0ugs 1&C 4C SPC/t FI>d PS Magneecl Level Swlkhss Level Swschcs mugs S0ugs 4C 4C 4C 1&C richer Level HO0085: Add Roscmcurc Bench Co/Craters Rcw Ec&rprnc/C Trsnsntscrs Calhrascn 101/gs $ 01/98 t00/$ $ 1100/gs

&Cc px U~xwo<<% 14C 4C 14C IS,C 14C I&C Fo>d><<o Pneu &cher o0 V2 Ccru Atontc Setup Rod Crop V I 4 V2 Rchdrdn CEOM Cahle C<<trot<<s Press Swschcs SSOP/co M<<>ta Computer TCV 12 I Regal/

t0t)tds@i.;,w C00/gs muss S0I/gs S00/gs 1001/gs I t00/CS 4C 14C 4C 4C 14C MC

,,@ltd+/I/tt;"; Ul Cat SCBO Ut Letdown V2 Ccru Alom/c V2 Can Alon/C Vt Cd Oeckrecrce Unit 2 LPM 4!'cs')'LIc&<<t,"":'.:.>~ Rad Mo/Rota Process Men\ore PIO Proc MCCR CM M<<tror 4cs. IS& el,vv&0M S00138 101/td 10108 S0008 '0010$

MECH MECH 1&C 14C 4C I&C ICC I'Ugt!/'Ss'T(CIsc VICalofCCW Oregon Vaue s Borg Warner V2 Cen Atcntc ul Scone Op 0 ca V142C<<rcLol tcc Is/yaI<<s OP.K-ISCOO23

,'kO'OS";ALII) "2;"'&C Rad Montors clues SSL Proc Mont <<n Proc Mcn Proc Mont Rct>y Cathreson 1&C Procectce

""K~c 10008 mms &0108 t/3008 I00ugs Iu3008 120 ugs 101/ST

&C K@>@cK;mc MKCH MECH MKCH MKCH MECH 14C I&C Tergal Rodr ye/wsy Vsuca Wcssnghcusc Wc 51<<l IIScg cute /amc sbury U2 Safeguards IT T Baden Vel/es Valves Vat/ca Vahres Mere/a CSL Irycl Aclual as SSCc,.,.cw >un 'g '

101/$ 8 S010$ S00/3$ 10010$ It0008 12010$ I/3ugt hlECH MECH MECH MECH MECH MKCH Ocrtng Coal Cony. Herry Pran Cress<< Vaka &y Val sir tac ~ cry/amah>/ng PSL.2 Plant Spe circe Procedures Psgccssd s(u Leldownulvs Vst/esVCI/ca (Ccnsotdatedt Vahras Vnucs'1/3008 1010$ &0108 &00/38 100108 1201/gs

<<Mcc'JSIUta  % dcdtcFOII SS<<CK$ >$ 0'~S .!F!S Jt'I'nU~W> wcc>.$ >dtt cu.AT $ IScuALI

" Oltl 8 dttt5$ ?:>>-<<"'Octobey>EK "-">togsr'ii5eTS ODUSO'11USdtc <<<Bsris 'l4 IIIFOb

ST. LUCIE PLANT MAINTENANCEPROCEDURE UPGRADE PROJECT TASK ¹2: REVISE AND ENHANCE EXISTING MAINTENANCEPROGRAM AND EQUIPMENT PROCEDUREs KNOWN' REQUIRE IMPROVEMENTS To Cofncfde viith DMslon Work Process Rafts'e':;:,,":,.g':,,'!,.

tfftff4'>>ff2ftf&~4 eiivc)oillINga'a>

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

f/8]f88<;::-".,~"-":;.if'~

Ef,BCT,';:-::,"";':,;:;";," -" Rb'dsd'Jfrrtt fry(.-'w.. Re~ac'pPWQi!,.0 0'nylon'-2:"'.020067;:@ aiid* f;f(e'dlgidPjy Timp'.F)vi/Jiimjyery Pi'o'ci'lfiirej<~';yoii'",.<~ 0,,'00)'0'0%pi) '~<~<

1A1f88KCP~%kf ffXGTjij$$+g~ KCG<TR v~~~'~

082007ff,! i<g",;'

f81/tiff!.".">>"-'-""-%%4 Sit Nff8K.";;~;~'f,hCTi<f4Gg",,'>>

~ Revhe Conduct of Mafntenance ADM.08.02

POWER BLOCK PWO BACKLOG Joe Marchese - Maintenance PWO Backio

- PWO backlog are non-outage corrective work orders (Work Type 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 TOTAL 2030 RR end -

~urtttur5 t.

1 800 Good ~urrit 2

~Corecn 700 X Total 600 Terrtet O

0 600 400 0 Tergel ~ 350 Totel trSMech 300 .

155 taC 20 Efect 200 100 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 Unit 1 Unit 2 Common Total Mechanical 71 117 13 201 Electrical 10 17 I&C 80 110 14 204 ProJects Total 160 239 27 426

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

- The number of Control Room/Board Green Tags. It provides an tndlcatlon of the attention given to maintaining control room Instruments in an operable condition.

80 ".OUTAGE 11.

UNIT1~7 UNIT2cn4 70 4Oed ~raneocdnge Bo-x regni Nnccecgn rncgcl 50 Cg c) ao O

>o 30 20 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 Non-Outage Outage Total Ready to Work 12 or Workln Engineering! RTA AWP Other Holds Total 20 Unit 1 Unit 2 Oldest 10/2/94 5/4/94 PWO ¹ 0137 3017 Discipline EM (OUTAGE) 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 Good ~

~ urrtt 1 unit 2

~Common 0 X Total 530 Target q 20 0

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 0 Electrical I&C Construction 0 Total 17 Oldest 8/11/94 7/25/94 PWO ¹ 2093 0562 Discipline Mech Mech

LEAKS N. Motley Leaks:

- Active leaks (primary and secondary) 70 OUTAGE

~

Legend 60 UNIT 1 = 25 UNIT 2 = 10 Good Non.Outage 50 Non.Outage Target J

rrr 40 V

30 As of 4/6/96 2:

20 a 0 8 $ *$ 0 0 P P P 8 0 . Non-Outage Target~10 10 0 ~

Sep Oct Nov Dec Jan Feb Mar Apr May Sun Svt Aug Sep Oct Nov Dec

'95 '96 Date Data Source: passport

SUMMARY

STATUS Unit1 Unit 2 Total Non-Outage 21 29 Oldest (Non.outage) 2/9/95 12/5/95 PWO¹ 4560 5730 Status AWP ENG

LEAK REPAIRS FITTINGS Greg Pustover - Programs Leak Re airs:

- Leaks that have been temporarily repaired.

55 tegend 50 45

~

Good

~ Una1

~unlt2 Ln 40

a. 35 "30 25 o 20 0

15 10 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 (Unit 1/Unit 2)

~ Reactor Coolant Gas Vent Valves (Unit 1) 6/96

~ " Pressurizer Code Safeties (Unit 1/Unit 2) 5/97 Strerg6~ System Perfonnance Monitoring

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

~ System & Component Engineers Trained Complete

~ Event Response Guidelines Complete

~ Root Cause Analysis Guidelines Complete 69

Plant St. Lucie Emergency Diesel Generator Reliability improvement Plan Matrix Problem Root Cause Corrective Actions Status and Long Term Notes Units 1 & 2 Governor Actuator Vendor teardown: report Plant initiated 6 year All unit 2 actuators overhauled Nov-95 failures identified fatigue due to length overhaul Preventative Maint Unit 1 actuators replacement and set up May 96 outage.

service; recommended 6 year item.

periodic factory overhaul. NOTE: EDG's are in MAINTRULE "A-1" due to governor STARS 950059 & 950529 actuator failures. This is the get well item.

1. Replaced all suspect Engineering evaluating upgrade of governor system to Unit 1 EDG Governor unstable Older design electronics electronic components and more current design (Woodward 2301A) during surviellances to (tied grid) very susceptible to "NOISE" optimized alignment with with proven noise rejection features.

"NOISY" inputs identified. vendor rep support.

NPWOs: 1A: 95026166 1B: 95026332 Vendor design: governor wiring Unit 1 8 2 EDG Governor harness wires in contact with Completed repairs and added Engineering developing improved design to eliminate Actuator Wiring grounds rough surface; vibration Raychem sleeve covering for abrasion concern:

induced abrasion. abrasion protection Unit 1: 97 outage STARs 951062 and 951055 PWOs 95024478 95026057 Unit 2: April 97 outage Two failure modes Identified: All four EDGs inspected and PC/M 030-196M Issued for unit 1. New design relay and Unit 2 Control Relay Pins relaxation and solder suspect sockets replaced. sockets. Work will be accomplished during the May 96 sockets failures 'oint failure due to cracks. NPWOs: 1A: 95031756 outage.

(Unit 1 has similar design) Removal / insertion (PM) and 1B: 95031676 Unit 2 PC/M to be issued and work accomplished vibration. STAR 951721 2A: 95031265 during the April 97 unit 2 outage.

Report JPN/CSI MET 95-223 2B: 95032588 Fatigue due to vibration; Pipe replaced: others inspected System engineer monitors engine piping closely; Unit 1 fuel oil piping failure this engine had underwent NPWO: 6035 visual exam of fuel line components at least high vibration during 8-31-95 monthly.

valve fail event. STAR 951322 Identified during trend analysis Radiator replacement is Unit 1 Radiator performance of engine jacket water temp. scheduled as an outage Job System engineer monitors and trends performance.

STAR 951575 provided safety assessment to operate until All four PSL 1 EDG radiators to be replaced during the May 96 outage replacement. May 96 outage.

Unit 1 cooling water relief valves Vendor design; valves PC/M implemented on 1B1 Other three engines valves to be completed May 96 weeping and not seating. placed in flow stream. (leaking) Unit 1 outage (PC/M 171-195 issued)

Units 1 and 2 diesel fuel Underground piping; corrosion PC/M implemented on 1A, 2A, 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 .

3.22

OST AVAILABILITYDUE TO EQUIPMENT PROBLEMS - UNIT 1

~ ~MTLYAGTUALS

~YTD AVERAGE TARGET

>. 2.5 .

D 1.67

~ g g 1.64 1.3

~ I ~oog Q g ~o%  % ~ 0 8 ~  % % ~ g g ~ Q ~ + oo 0.5 0.11 I I I Jan-96 Feb-96 Mar-96 Apr-96 May-98 Jun-96 Ju!.96 Aug-96 Sep.98 Oct-98 Nov-98 Dec-98 LOST AVAILABILITYDUE TO'EQUIPMENT PROBLEMS - UNIT 2 3.5-3-

2.53

~ MTLYACTUALS

~YTD AVERAGE TARGET th

>.2.5. -- ~

D V

1.28 a a ~ & W ~ W H ~ W W ~ R  % ~ W W ~  % W 0.85 0.5 0.03 0

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 Complete Reduce Open TSAs 6/30/96 Reduce Age of Oldest PCMs 12/31/96 Improve FSAR:

Assessment Team Effort Complete Corrective Actions Unit 1 12/15/96 Corrective Actions Unit 2 9/30/96 Maintenance Procedure Review: 2/97 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 LEFM 72

TEMPORARY SYSTEM ALTERATIONS TSA Kris Mohindroo - Engineering 50 Good Legend 45 ~unit t

~untt2 40 X Total 35 Target 30 v- 25 20 .Verget ae- ..--.

15 10 Oct Dec Feb Apr Jun Aug Oct Dec Date Data Source: Kris Mohtndroo

SUMMARY

STATUS Disci line Unlt1 Unit 2 Total Mechanical Electrical I&C 14 En Ineerln 0 Bratlons Health Ph slee 0 0 0 Construction SCE Total 14 21 Oldest TSA 3/4/95 5/10/94 Disci line I&C I&C

PLANT CHANGE/MODIFICATIONS Kris Mohlndroo - Engineering 1 50 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Good Legend 125 ~unit1

~unlt2

~Common 100 X Total g

O Target 75 0 Open PCrM Tergal ~ 80 0

50 25 0

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

SUMMARY

STATUS-WORKING Disci line Unlt1 Unit 2 Common Total 0 enPC/M 55 20 81 PC/Ms >24 Mo.

0 ST. LUCIE PLANT - 10 OLDEST OPEN PC/M's SCH PC/M DATE DATE DESCRIPTION CLOSE STATUS AND ACTIONS REQUIRED TO CLOSE NUMBER ISSUED FRG'D DATE 193-189 Open Blowdown Cooling Water Heat Exchanger 2/I I/89 12/11/89 5/30/96 PC/M implemented. Action plan to resolve slight periodic leakage Vacuum Breaker Valve Changeout problems with permanent drain catcher. Engr PC/M planned for 4/19/96 276-189 ICW Isolation Valve V21165 Relining 12/6/89 2/7/90 UNIT I 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.

335-190 Check Valve Hinge Pin and Bonnet Modifications 7/18/91- 4/13/93- UNIT I PC/M implemented on valves V14147 and V14151. Modifications to on CCW pump discharge check valves V14143, Sup 0 Sup 0 OUTAGE V14143 planned for next refueling outage. Willclose PC/M upon V14147 and V 14151 3/25/93- 4/13/93- completion of the work activity Su I Su I 171-191 Resizing and replacement of MOV '11iermaI 7/17/91 9/19/91 UNIT I PC/M implemented on 122 valves. 15 valves remaining to be modified.

Overload Devices on 137 MOV's OUTAGE EM needs to schedule remaining work Willclose PC/M upon corn letion of the work activity 186-191 Intake Cooling Water Support Modifications 7/I/92- Not UNIT I Sup 0 Complete. Sup. I was budget approved at the MRB I/30/96 for Su I FRG'd OUTAGE im lementationdurin the1996Unit I outage.

086-292 Radiation Monitoring Computer Replacement 4/22/92 5/7/92 5/24/96 PC/M implemented. ICM has 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 of the work activity.

203-192 Replacement of 95 Sigma Meters in the. Control 12/21/92 4/6/93 5/24/96 PC/M partially implemented with 15 instruments installed. Recommend Room and Hot Shutdown Panel do to obsolesence as-building what work has been completed and close PC/M. New Issues. 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 11/3/92 6/30/96 Partial implementation - Final scope to be reviewed and completed fiber o tio cables 235-992 Su . I -U adin of Communication 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, EMT forcondenser 5/17/93 6/15/93 6/30/96 Replace incorrectly sized thermal overload (TOL) heaters for Condenser sam ling um s 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:

W REA Number W Descrfptlon M Date Due W Resp. Disc.

TT FUhNOrrOAl A~ Engr'd Matls. Ordered

~ Engr'd Matls. Required 0M Orlglnal Plant List HW Emergent Packages

~ By Outage Start/During Outage

+W PC/M Not Required C W Capital MR lll@Qilrr MShaded Box Represents IF!%lot  !

Completed Package SLN95413 10 PMAI 9843.777 PMAI 9642492 PMAI 9843 785 NONDEPINCORE EDG COP TUBE EDG UNLD VLV EDe RADPLNM CNTMTRNe LeT 4-1S48 4-26 98 4-29 SB 440.96 4.12.98 FUELS 'ITE MEC SITE MEC SITE MEC PEG ELE STAR 951089 STAR 951049 STAR 951080 PMAI 9842-148 PMAI 96-03.728 B13308XEVWV REWINDCWP 1A2 DIESEL TK RTGB GR ALRM EDG EXHAUST I B EDG VLT REG PRESS INSL 4.12-98 4.19.98 4.28-98 4.2948 440-98 540.96 5404S SITE MEC PEG ELE SITE MEC SITE ELE SITE CIV SITE ELE SITE MEC STAR 94110488 PMAI 96-03470 PMAI 98.03479 STAR 951283 PMAI 98.03.115 STAR950585 RWT INSP 24" SPOOL PCE CIAS EGG START D/G INDLIGNTS RCP SWEEPS RCP VIB PROB 1B2 ANN A-13 41298 4.1946 4 2848 4.29-S6 440.98 540 98 540.96 PEG CIV SITE MEC ITE ELE/SC SITE UC SITEELE PEe ELE +

SLN 93461.11 STAR 950970 PMAI 98.03 453 STAR 951138 STAR 951197 STAR950428 A/D CRN'S POLARCRANE DBLJACBONET MV08.1BMTR 1A1 RCP CCW MV 09.13 ST NUT 4-15.98 4 2448 440-98 440-98 54046 540.96 O.'F.UEL'tt!i!$

ITE MEC/Cl + SITE CIV ~ SITE MEC SITE ELE SITE MEC PEG MEC 35 5 STAR 9516S7 AR 950323A PMAI 98.02452 PMAI 98.03.277 STAR 950882 RPSWtG SNI/BBER CRIT CP LKOFF 480V LC LIFT MSIV BXVP LCV-11.24 A/8 EXCORE POS Jlf'lilt ll I 4.15 98 4 19.98 4-28 98 4 29.98 5.17-98 540.98 SITE CIV ITE MEC SITE CIV PEG MEC SITE MEC SITE MEC +

APR MAY 0:COMMCNIDREISKfla!ESIISSBPIEPRE

CO PROG

0

'7

IMPROVEMENTS/ACTIONS ACIIONPROGRAM r "v nt Standardize Process:

~ Implement PMAI process Complete

~

Implement CR process Complete

~ Transfer all STARs to CR process Complete Status as of 4/15/96:

~

Only 5 original STARs remain (none are overdue)

~ No overdue CRs

~ 120 overdue PMAB ACIIONS

1. PMAI procedure (AP0006129) lacks

• Training conducted.

instructions necessary for successful use by

'* Procedure revised.

plant personnel/training not corxhctaK

2. STARs were closed without initiating

• Licensing/QA/PGM/ corrcurrcn~e departrrrerrt concurrence. mallltalIled.

• Inrleperrdent Review substituted.

• PCR was never approved.

• Con!roHed copy distribution of CR/PMAI procedure.

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

3. Technical issues requiring near term

• Technical issues identified have been corrective action are currently documerded on corrected.

PMAZs with extended due dates.

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

77

CORRECTIVE ACTION coI PROGRAM TR 1996 REPORT

CRs Generated By Quarter 1,200 1,073 1,000 800 600 565 480 400 374 329 200 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 57 45 40 36 36 27 27 26 22 2P 20 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

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

7 4 4 4 1 1 taCp VC 0 J K L M N 0 P Q A B C D E F G H I g A~Writ Comm g B*Work Practices 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 Lrg JiEqutp 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 140 124 120 100 78 80 69 60-45 40 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 50 48 40 Written Communication 30 100 20 10 80 75 10 4

'0 60 A B C D E F 40 34 I=A~Inadequate Oocumenl ProvtstonsR8~Techntcat Inaccuractes D=lmproper Chg Implementation g NC~Other E~Omfssion of Relevant Info QF~tnsufttctent Info 20 inadequate Documentational Provisions A B C D E F OPS 32.6%

+A=Procedures QD=PWO g

gE=Other g

8=Engr Docs (Dwg, PCM, TEDB) C=Regulatoy PSiF SAR) gF=PO SCE 14.9%

P 1.6%

IC 11.9% Chem 3.0%

OM 4.6%

OST 4.6%

MP 9.0% EM 4.6%

MM 76% IS 6.0%

1QTR005.pre

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

A B C D E F Technicai inaccuracies gA-"Procedures QD=PWO g B~Engr Docs (Dvttg, PCM, TEDB) pc=Regulatory (TS/FSAR) gE~Other Q~F=PO Drawings 50.0%

TEDB 26.5% PCM 23.5%

1QTR006 re

Work Practices Trend 1st QTR 1996 80 60 48 44 39 40 24 20 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 Documents Not Followed Correctly Work Practices 50 OPS 273%

40 38 IC 15.9%

30 PLT 2.3%

20 LIC 2.3%

MPRJ 2.3%

MM 11.4% MP 2.3%

10 HP 45 0 SCE 9.1% NMM 6.8%

A 8 EM 6 8%

EQG 9 1%

gA=Docs Not Followed Correctly g

'8g D=Up-To Date Documents Not Used Req'd Vertf Not Performed pc~Other 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/PMAI transition 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 relief valve lift.

Ongoing assessment of OEF program compliance and effectiveness.

Facilitating plant self-assessment with support from outside PSL technical specialist, A series of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Conduct of Operations 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 of the PSL Technical Specifications:

~ Further evaluate co.benefi of implementation of Improved 6/30/96 Standard Technical Specifications gSTS).

~ Improve the Technical Specifications BASES:

Submit PLAs to remove the BASES &om the 6/30/96 PSL Technical Specifications Index Use the ISTS BASES for PSL BASES On-going improvements. (post-PLA approval)

~ Evaluate the need for Technical Specifications position 6/30/96 statements.

Address and improve the implementation of the 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)

HEALTH PHYSICS/RADIATION PROTECTION: 2-26-96 to 3-1-96 (1 inspector)

SPECIAI INSPECTION - UNIT 1 DROPPED CEA AND 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)

PHYSICAL SECURITY 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 of March 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 of Technical 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 of specification 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

~Actual Vtotettons ur ~Actual Has 10 S~

O o 5 X

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

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

~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 Good 17 28 20 10

h. 15 ~Actual o

10 0

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

FOP's IN REVIEW 25 20 12 12 Good 15

h. ~Actual 10 0

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

FOP's TO BE CLOSED (CLOSE-OUT

SUMMARY

)

35 31 30 ~Actual 27 Good 25 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 Complete

~ Convert Procedures to Guidelines Complete Improve the Safety Focus of the FRG:

~ Tech Spec Improvement 6/96

~ All other items Improve Training Dept Contribution to Conservative Plant Ops

~ IHE Training Review Team 4/25/96

~ Nuclear Policy 914 implementation 4/25/96

~ Enhance L.O. Requal Exam Practices 4/18/96 Improve Plant's ability to implement the E-Plan efBciently

~ Upgmde and Revise the ERO 3rd Qtr/96 More &quent limited scope drills ,

7/96 ValidattJUpdate EP Training Content 9/96 Implement Configurafion Control process

~ Reestablish Configuration ManageLna)f Group Complete

~ Revise AP 0005745 "Request for Engineering Assistance" Complete

~ Initiate Real Time List for Minor Modifications 4/15/96 Develop 20/30 Lists

~ 1996 Top 20 list Complete

~ 1996 Top 30 list 4/18/96

~ 1997 Top 20/30 list 5/5/96 94

l 0

TEMPORARY CHANGES TO PROCEDURES Jim Holt - Information Services 350 Legend 300

~Untt1

~Vntt2

~common 250 X Total Target 0 200 0

cr 150 R

100 50 Oct Dec Feb Apr Jun Oct Dec Date Oata Source: Jtm Holt

SUMMARY

STATUS Oldest TC Dlsclpllne Unit 1 Unlt2 Common Total (daVs) 89 0 eratlons 23 18 50 89 Mechanical 89 Electrical 89 ILC 67 Reactor En ~

68 SCE HP Total 26 25 25 76

INDUSTRlALSAFETY - RECORDABLE DOCTOR CASES Klm Heffelflnger - Protection Services 35 Legend Good ~Actual 30 1996

~Actuat

~ ~ ~ 1996 25 ~ ~

22 23 Target 5

nI 20 16 Target ~18 15 ~ ~ ~ 4 ~ \

11 X

'to 3 3 4 Oct Dec Feb Apr Jun Aug Oct Dec Date Data Source: Ktm HeffeNnger

t ST. LUCIE PLANT BUDGET PERFORMANCE INDICATOR 10v 1996 O626 BUDGET PERFORMANCE 100 ACTUAISTHROVCH MARCH 1000 M

O 10 I

0 0O O O

Z 0 O

10 1996 CAPITAL BUDGET PERFORMANCE ACTUALS TTNOVCH MARCH 1010 20 IMONTNLV)

XX'8VCCET 20 2A

~

~ACTUAIS IMONAC.YJ FORECAST (MONKEY)

~SVOCET gUMAATIVQ X

4 Q ~ACTUAlS 0 FXRRAAmg

~ X FORECAST (CVUAAATIVE)

E ~>

IC 5

O O

~I

'X E I 12 X

0 ~

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

PSL TRAINlNG OBSERVATIONS 100'/o 80/o

~Actual 70/o 80/o 50'/o J2 0

c 40%

30o/o 20/o 10/i

~Wgp~

i&%Actual~

0i/o

~ y832 ~8M yeats~

1IXr/o "1885'~

35i/i 0i/o

~$

2/o

~95%

4088 ~' 7/98 'oI88 9N881 Aluaa". 55jw'2/38 Data Source: P. Fincher 98

N'ATERIALS 1

INIPROVEMENTS/AGTlONS r ye ment Outage Material Availability:

~ Delivery of material has been expedited for 90 Pcs

~ No PWOs have been canceHed for lack of parts Reiuce the Cost of Carried Inventory:

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

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

C INVENTORYVALUE Dan Quilty - Nuclear Materials Management Legend 100 Good

~Actual Target 75 ro O

42.3 43.5 50 42 45.2 44,2 ~

Target ~ 38 O 39.4 l5 25 Oct Dec Feb Apr Jun Oct Dec Date Data Source: Norman Quesada

WAREHOUSE RESTOCKS 3000 2672 2500 2000 n

E

8. ~Actual 8

1500 1280

---

Target 1000 Good 500 116

~ ~ ~ ~

0.

Jan Feb Mar Apr June July Aug Sept Oct Ncv Oec Date OVERIWAXINVENTORYVALUE 3.3 .~ 4.0

~ e 3.5 2.6 ~ L'

~

Lr 2.s

- Actual

- - - ~ Target

~

1.5 0.5 0

Jan Feb Mar Apr May 'une July Aug Se pt Oct Ncv Oec Oate

NONUTAGE AWP (STATUS 45 8 48) 188 180 160 135 140 ~Actual 120 ----- Target 80 60 Good 40 20 Jan Feb Mar Apr May June July Aug Sept Oct Nov Dec Date OPEN REQUISTIONS OVER 30 DAYS 250 200 150 111

~Actual 100 126 ----- Target C

50 e

Jan Feb Mar Apr May June July Aug Sept Oct Nov -

Dec Date

l NUULhAM MAI EHIAI.S MANAGEMENT 10 OLDEST AWP'S WEEK ENDING APRIL 12, 1998 UN ORIGINATION COMPONENT/ASSOCIATE/NAME TITLE WORK ORDER SCHEDULE STOCK CODE P.O./P.R. ACTION COMMENTS DATE V14143 CHECK VALVEFOR IMPLEMENTPCM 1/14/93 COMPONENT COOLING WATER 9300144401 SL1-14 177522-1 P 015383 PUR DELIVERY DATE 5/6/98

¹335-190M PUMP 1A DISCHARGE SR-07-1B/SAFETY RELIEF VALVE PERFORM IST 37251-3 PO 14283 DELIVERY DATE 4/5/96 3/18/93 FOR LPSI 1B & HPSI 1B PP INSPECTION & RPR 9300884501 SL1-14 PUR 57194-1 PO 13496 DELIVERY DATE 5/10/96 SUCTION FLNG LK.

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

D SUBMITTED BY: MATERIALSMANAGEMENT~ N. QUESADA

SL1-14 PURCHASING BACKLOG SL1-14 PWO'S WITH A DELIVERYDATE PAST 429 267 REVIEWED BY MAINTENANCE 240 350 g 300 ACCEPTABLE DELIVERY 148 250 NUMBER TO EXPEDITE 92 200 150 OP's REVIEW "MUSTS" TO WORK 82 PWO'S CANCELLED

~ 4 0 FOR FULL EXCEPTION LISTING REFERENCE 0 C4 tA CD h FILE F:tCOMMONWMMPSL'KXCEP483(LS

~TOTALBACKLOG ~ LINE ITEMS ORDERED 4/09 4/10 4/11 4/12 4/15 4/16 4/1 7 4/18 4/19 4/22 Previous Da 's Backlo 235 208 196 146 119 124 Incomin P.R.'s 44 43 13 24 30 22 Line Items Ordered 71 51 61 50 25 40 Line Items To P.E. 4 2 Total Backlo 208 196 146 119 124 106 PURBKLOG.XLS