ML17228B438
| ML17228B438 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/15/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17228B437 | List: |
| References | |
| NUDOCS 9603270306 | |
| Download: ML17228B438 (100) | |
Text
9603270306 96032i PDR ADQCK 05000335 P
ST. LUCIE STATUS MEETING AGENDA FOR MARCH 16, 1996 9:00 AM, SSB ROOM 2200 OPE NG E
RKS OPERATING REPORT/RECENT EVE T CEA PROBLEMS (IHE 96-20/21/24)
DIESEL GENERATOR INADVERTENTSTART CONTAINMENTRADIATIONMONITOR MISPOSITIONED VALVE B. Bohlke J. Scarola A. Pawley R. Olson H. Buchanan DIL TION E E
Department Heads A. Pell DEPARTMEN RE ORT LICENSING OPERATIONS MAINTENANCE
'UALITYASSURANCE SYSTEMS/COMPONENTS ENGINEERING CORRECTIVE ACTION PROGRAM MATERIALS SERVICES E. Weinkam B. Frechette J. Marchese W. Bladow C. Wood D. Denver B. Dawson D. Quilty C. Burton LUNCH
I
~
OPERATIC~ ~~o>>
102 Unit1 Daily CAPFAC CAPACITYFACTOR 17 Days on-line as of3/13/96 101 99 98
~O 97 96 LL C>>i 95 f1.
O 94 93 92 91 QhNP Pj f.
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nl Oi Oi R
R R
R R
R R
R R
Date CO CO CO CO CO CO CO CO CO CO CO C8 CD CO Ol O
CO CO c8 MonthlyAverage CAPFAC=90.95%
Lost Generation Date MWH Loss Reason 2/16/96 2/22/96 2/23/96 2/24/96 2/25/96 3/10/96 3/11/96
-107
-10197
-20136
-20136
-125
-149
-211 Limitation not to exceed 549 Tc.
Dropped CEA20.
'ropped CEA20 8 CEA47.
Dropped CEA47.
Dropped CEA 47.
Hot Leg Stratification Hot Leg Stratification Capacity Factor = (Net Output in MWHR)/(Maximum Dependable Capacity FactorWime Period)
Maximum Dependable Capacity Factor = 839 MW
Unit 2 Daily CAPFAC CAPACITYFACTOR 65 Days on-line as of 3/13/9 100
~~R~~~t,--<w~'l5~tcF>%<>w N'r+c-r5""~~:~'t5;.rr4vM 5 ~ri,'-5 t5 ltd>~t- >>>> oc ~'~~~r'.. ~~lzgc~~~tc5'+cg~M~'>
Cr 5'0 o<
LO 60 CJ u
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5.
tt'O CO CO or clr clr CO Cr CO CO RRPRRRRRR CO CO CO Date Monthly Average CAPFAC=100.99%
Lost Generation Date MWHLoss Reason 2/16/96 2/17/96 2/18/96 2/19/96 2/21/96 2/22/96 2/23/96 2/24/96 2/25/96 2/26/96 2/27/96
<00
-157
-167
-137
-926
-364
<83
%60
-487 06
-522 Limitation not to exceed 549 Tc.
Limitation not to exceed 549 Tc.
Limitation not to exceed 549 Tc.
Umitation not to exceed 549 Tc.
MSR TCVs MSR TCVs Holding to 100% power.
Holding to 100% power.
Holding to 100% power.
Turbine valve test.
Turbine valve test.
Capacity Factor = (Net Output in MWHR)/(Maximum Dependable Capacity Factor'Time Period)
Maximum Dependable Capacity Factor = 839 MW
AUTOMATICREACTOR TRIPS Jeff West - Operations 6-Good Legend
~Actual Target 4-Vl CL agI-at 3
0 0z 2
2 2
2 Target = 1 0-I I
Oct Dec 0
0
~~
I Jan '96 Mar May Jul Date Sep Nov Data Source: Jeff West
0
CEA ¹20 ROD DROP B~KGRDIBID.
On February 22, 1996, CEA ¹20 dropped into the core during the CEA exercise quarterly testing.
~
A4 B phase 240V 15 AMP fuses were found to have blown.
~
Upper gripper power switch was swapped with the Load Transfer Switch and power restored.
The load transfer circuit blew the suppression resistor on CEA ¹20.
II.
BDDDT D UBB:
Upper gripper power switch was found to have a short on "A"phase SCR circuitry.
III. C RRECTIVE ACTIONS:
A)
ISAAC replaced upper gripper power switch, replaced suppression resistor and fuses.
B)
INC has no previous history ofthis type ofrandom failure.
C)
The faulty power switch has ben sent to ABB/CEfor evaluation and recommendations to prevent further failures.
CEA 847 ROD DROP 0
t.
~CKGR On February 23, 1996, CEA'47 had dropped form 12 inches into the core and would not withdraw.
~
Recorder traces indicated no current to the upper gripper coil.
~
Upper gripper coil had a high resistance of30K OHMS.
tt. ~Q Cable connector adapter on the head was found to be loose.
C ACTIONS:
A.
Tighten cable adapter for CEA 047 and verified proper resistance.
B.
Verified all other CEA adapters on the head and disconnect panel as being tight.
C.
INC modified outage head cable connection PWO to include verifyingthe tightness ofall CEA adapters.
CEA N ROD DROP I.
B~AK R On March 4, 1996, during MTC testing CEA ¹1 dropped into the core.
~
CEA ¹1 was immediately withdrawn and realigned to the rest ofthe group.
~
Subsequent testing revealed no mechanical or electrical problems with CEA¹l.
IL R~DT C CEA motion inhibitbypass push-button must be held prior to rod movement.
III. CO CTIVEA TION A)
Operations MTCtest procedure revised to direct the operator to depress CMIbypass button prior to rod movement.
B)
ABB/CE evaluating the CMIcircuitry and to provide recommendations.
C)
ISAAC suggests removal ofthe CMI&om the liftcoil, circuitforUnit l.
INADVERTENTSTART OF THE 1A EMERGENCY DIESEL GENERATOR DUMNGPERFORMANCE OF PC/M 1SO-195M I.
B~C STAR 950721 identified an "Operator WorkAround" inthat the original design ofthe EDG Fne Control Panel Alarms prevented other EDG alarms &om annunciaing in the Control Room. To remedy this design inadequacy, PN prepared PC/M 180-195M to eliminate the operator work-around II.
~EHCIIIP On 2/27/96 an INC Specialist while attempting to re-route a cable as required by the modification; bumped relay K-16 located within the control cabinet.
This resulted in an undesirable idle start of the 1A EDG. Work was halted while operations secured the diesel generator..
III.
V LUATI N/ROOT CA SE
ATechnical Subcommittee was formed which identified the root causeof the event to be Faille to remove the 1A Diesel Generator &om service (Clearance) prior to working inside the 1A Diesel Generator Cabinet." An additional contributing factor to the event was a procedural oversight which excluded the diesel generator control circuitry &om the list of systems determined to be sensitive to plant operations.
C C
1.
Administrative Procedure No. 0010142 "Unit Reliability - Manipulation of Sensitive Systems", was modified to include the EDG control cabinet and is currentlyin the approval phase.
This procedure imposes multiple levels of review and additional work controls which could prevent recurrence ofthis adverse event.
2.
The IAC Supervisor, ANPS, 18.C Technicians, SNPO, and QC Inspector involved in this incident should be personally counseled by applicable Managers regarding the need to avod to the extent practical any situation which could result in an inadvertent actuation ofany Engineered Safety Feature (ESF).
3.
Department heads willmeet with employees to reinforce the expectation that performing work which may cause an inadvertent safeguards actuation is unacceptable.
4.
The Training Department will include this event in the Maintenance and Operations continuing training program.
5.
St. Lucie willinvestigate the feasibility ofusing the "Red Card" programcurrently in use at Plant Turkey Point. This is a checklist to aid the NPS/ANPS in determining ifthe NFL should be authorized forwork at any given time 6.
Consideration should be given to setting up a twelve week (quarterly) schedule to work on a systems based approach to maintenance.
This would allow the System/Component Engineers and the Maintenance Department to plan ahead and provide a more detailed review ofplanned work activities.
Licensee Event Report Number 335-S6-003 Event
Title:
Containment Radiation Monitor Out of Service Resulting in a Condition Prohibited by Technical Specifications Due to Personnel Error.
Root Cause: Personnel error through failure to followprocedure HPP-22 when performing grab sampling of RCB atmosphere.
Contributing Cause:
Procedure did not require independent verification of valve positioning at the conclusion of sampling.
Completed Preventative Measures Health Physics Supervision emphasized their expectation of verbatim compliance with approved procedures Atemporary change was made to HPP-22 to correct a procedural inadequacy on the sampling process for Unit 2 Health Physics Technician Disciplined and counseled on verbatim compliance with procedures HPP-22 changed to include independent verification of valve positions on the RCB atmosphere monitors at the conclusion of grab sampling Preventative Measures in Process Health Physics procedures that implement Technical Specifications are under evaluation to determine ifthey are written to effectively implement the Technical Specifications.
Health Physics procedures are being evaluated in the light of verbatim compliance in one of the two approved methods - Step by Step and Memorization. Factors used in the evaluation include complexity, frequency of performance, performance that is sequence critical and procedures requiring verification of performance of individual steps.
Aself assessment program specifically addressing procedural compliance willbe developed and implemented upon the completion of
'I i
DIIUTION
B N DIL TION EVENT CORR CT CTI B
D T
FNT RESPONSIBLE DEPT.
PM PM PM PM PM PM DESCRIPTION Plant Management willensure that all expectations of proper Control Room conduct are carried out by observation of simulator training exercises.
Plant Management willreiterate expectations to all Plant Supervisors for when to be notified on an event that meets a predetermined threshold. This Is a generic concern.
A review of the Turkey Point Condition Report of the 1993 Dilution Event was conducted for lessons learned and incorporated into this report.
Plant Management willreinforce expectations that Fitness for Duty considerations are systematically implemented following an event.
In addition to specific corrective actions, Plant Management willself-assess the operation of St. Lucle Plant.
This self-assessment willinclude, but is not limited, to Conduct of Operations, alarm setpoint policy, operating experience feedback, training, procedures, corrective actions, and management policies. This review willbe performed by plant personnel augmented by experienced individuals from off-site. Recommended actions will be reviewed and statused in the monthly indicator book. Independent oversight of this self-assessment willbe provided via the Company Nuclear Review Board.
Provide, on an annual basis, a letter to each individual licensed operator of Plant Management's expectations on reactivity, reactivity control, and the importance and responsibility of the Operator or Senior Operator at the reactor controls.
The Plant General Manager has re-emphasized the reduction of nuisance alarms to all line organizations to support the "blackboard" concept for operations.
A review was undertaken to evaluate the adequacy of the existing policy and guidance involving reactivity control. Plant Management willnow reinforce expectations and the Importance of reactivity control in a personal letter from the Plant General Manager and Site Vice President to each RCO and SRO.
Plant Management has developed a mechanism for providing feedback on the understanding and implementation of all policies and expectations for all plant organizations.
(Standards Assessment Guideline by Management)
ATraining and Performance Review Board willbe Instituted to conduct a consolidated review of all performance indicators for Licensed Operations personnel who are identified as Historical Poor Performers.
The review will assess the need for additional remedial measures and/or the removal ofthe Historical Poor Performer from licensed duties.
DUE DATE Complete Complete Complete 3/15/96 7/31/96 Annually Complete Complete Complete Complete
B DILUTI N VE COR EC VE CTIO DE TMEN ITEM//
12 13 14 15 16 17 18 19 20 RESPONSIBLE DEPT.
OPS OPS OPS OPS OPS OPS OPS OPS OPS OPS DESCRIPTION Operating Crew briefings by Operations Supervision were held discussing the dilution event, Zach Pate's "The Control Room" and Management's expectations with respect to conservative plant operation. Operations Supervision also reinforced expectations in "Conduct of Operations" with respect to notification of Operations Management, log keeping, focus on reactivity changes, and the short term turnover process.
Operations Management reviewed its expectations for command and control using information obtained from other sites including Turkey Point. The implications ofthis event willalso be reviewed by a team for applicability to other Operation's activities both inside and outside the Control Room. STAR 960146B & C - Schedules due.
Nuclear Plant Supervisors have been directed to review all.new In-House Events at the 0740 meeting with Plant Management to help prioritize activities.
The procedure upgrade process willInclude UFSAR review to identify inconsistencies for correction.
Operations willrevise the "Conduct of Operations" procedure to require a sufficient level of detail in DS-7 reports so management willhave adequate Information for assessment ofthe problem.
Operations willrevise the "Conduct of Operations" to clarify"short term turnover". Examples ofwhen "short term turnover" is required willbe Included In the revision. This revision should be communicated to Operation's personnel by Night Order and discussed with operating crews. Training should reinforce these expectatlons during training sessions and Management should monitor its effectiveness Operations Supervisor expectations in "Conduct of Operations" were reinforced during the briefings.
Specifically:
~
Notification of Operations Management
~
Log keeping, focus on reactivity changes
~
Short Term Turnover process.
The Conduct of Operations Procedure was revised to include the following:
~
Board walkdown is now included as part ofthe "Short Term Turnover" process,
~
Direct supervision of reactivity changes is required by a Senior Reactor Operator,
~
Reactor Control Operator is to remain at the controls during all reactivity changes while in progress,
~
Reactivity changes shall not be turned over while in progress.
Operating Procedures 1[2]-0250020, "Boron Concentration Control - Normal Operation" was revised to be like the Unit 2 procedure which includes the manual dilute mode of operation.
Revise Operating Procedures 1[2]-0250020, "B oncentration Control - Normal Operation" to require the direct supervision of an SRO during reactivity c DUE DATE Complete 3/31/96 Complete Complete 3/31/96 Complete Complete Complete Complete
B DILU ON EVE C
EC VEACTON B
DE T
EN ITEM f/
22 23 24 26 27 28 29 30 31 32 RESPONSIBLE DEPT.
OPS OPS OPS OPS OPS OPS OPS OPS OPS OPS OPS OPS, MP DESCRIPTION Revise Operating Procedures 1[2]-0250020, "Boron Concentration Control - Normal Operation".to Identify the preferred dilution and boration flowpaths during different plant conditions, specifically during steady state operations.
For an interim countermeasure on Control Room awareness, Operations willevaluate the implementation of the use of a "Dilution/Boration In Progress" sign similar to the CVCS letdown "Divert"sign presently ln use.
Ifannunciation to help guard against over-dilution cannot be implemented, then the sign willbe considered for a long term countermeasure.
Operations has re-instituted the logging of a Boration/Dilution evolution. This Is being performed in the RCO Chronological Log. The Boron/Dilution Log Entry willaid Operators in determining how much dilution has been occurring during previous shifts, and aid In estimating over the next shift Operations willidentify all tasks inside and outside ofthe Control Room where the Operator fs not permitted to leave the area or controls until the task is completed.
These tasks should be effectively communicated to all Operations personnel with Management's expectations of performance ofthese tasks.
STAR 951118 requires the Operations Department to review all tasks ofthis type performed by Non-Licensed Operators.
STAR needs to be expanded to include Control Room Tasks.
The Operations Supervisor has discussed with each NPS the purpose and thresholds ofAppendix E, Conduct of Operations, and the necessary notmcations.
Operations willreview the current watchstanders for Historical Poor Performance, and assess need for action.
Lessons learned from this event were reinforced via supervisory expectations communicated to Shift Technical Advisors in the areas of: Sensitivity to plant events, In-House Event summary accuracy and completeness of supporting data, and 10CR50.59 reviews.
OST willsurvey the industry on the use of automatic and manual boration and dilution controls to benchmark St. Lucie and determine the best means of reactivity changes by chemical control.
The BRCO was removed from licensed operator duties.
Provide briefings of Operations Crews, by the Operators involved, of the boron over-dilution event and the NRC Pre-Decisional Enforcement Conference.
The Operations Supervisor has discussed with each NPS the'purpose and the thresholds of Appendix E, Conduct of Operations, and the necessary notification which that appendix requires.
The procedure upgrade process willconsider UFSAR to identify inconsistencies for correction.
DUE DATE 3/1 5/96 3/15/96 Complete 3/30/96 Complete Complete..
Complete Complete Complete 3/31/96 Complete Complete
B DILUT N EVE CORR C IVE AC ON BY DEPARTItrIEN ITEM f/
33 34 35 36 37 38 39 40 41 RESPONSIBLE DEPT.
OST OST LIC OST OST OST OST ENG ENG ENG DESCRIPTION Conducted a survey to assess controls at nine nuclear facilities to benchmark criteria for reactivity management which determined that most CE Plants require notiTication of an SRO prior to an RCO Initiating a reactivity change.
Surveyed other utilities to benchmark how their plants are operated with respect to T~Reactor Power and their Technical Specifications In order to help determine the best approach of operation for St. Lucie. This resulted in:
~
An immediate reduction In reactor power for Unit 1 and Unit2 to provide operating margin forT.
~
An Engineering 50.59 supporting full power operating with reduced T~,.
~
A Proposed License Amendment to increase the Technical Specification LCO for T In order to provide operating margin.
OST willrevise ADM17.02, Appendix 1 to Include prompting questions related to personnel errors.
A letter describing lessons to be learned by STAs from this event was sent to reinforce expectations in the areas of:
~
Sensitivity to plant events.
~
ln-House Event summary accuracy and completeness of supporting data.
~
10CFR50.59 Reviews.
The STAs have met with the STA Supervision to discuss the lesson learned during this event and reinforce the Importance of IHE summary accuracy and completeness.
OST willrevise ADM17.02 and In-House Event software to include HPES feedback in the first draft of human error related IHE Reports.
Evaluating methods to prevent the THighalarm from being a nuisance alarm ifthe setpofnt Is restored to 549'F.
Evaluating feasibility of installation ofa "Dilution/Boratlon"alarm In both Unit's Controls Rooms. This would annunciate whenever a dilution or boration Is In progress and help focus awareness of reactivity changes which are in progress.
Revise 10CFR50.59 training lesson plan to discuss need for 50.59 evaluations to "... conduct tests and experiments not described in the safety analysis report." (Note: Not a commitment made in the 3/8/96 presentation to the NRC but completes the 10CFR50.59 screening criteria.)
DUE DATE Complete Complete 9/30/96 3/31/96 Complete Complete 3/31/96 3/31/96 3/31/96 6/30/96 42 ENG Engineering has performed,a 50.59 evaluation dilution and boration. (This 50.59 viillbe includ ct Operation's practice of using the "manual" mode of e next annual update to the UFSAR.)
ete
B CO REC N D TtON EV CT ONS BY DEP TMEN ITEM //
43 44 45 46 47 48 49 50 51 53 55 56 RESPONSIBLE DEPT.
ENG ENG ENG ENG ENG ENG SCE TRNG TRNG TRNG QA QA QA HR DESCRIPTION Engineering has reconvened the UFSAR review team to complete the review ofthe UFSAR versus plant procedures.
Sampling Completed.
Full Scope 8 Schedule Due.
Complete 50.59 training for departments responsible for procedure changes with emphasis on the definition of
"...procedures as described in the safety analysis report."
Complete Identification and elimination of inconsistencies for Unit 1 UFSAR.
Engineering is evaluating the current Control Room annunciation for possible improvements to help focus awareness of reactivity changes Revise Engineering procedures to include documenting sections of Technical Specifications and UFSAR reviewed during 50.59 screening:
Complete identification and elimination of inconsistencies for Unit2 UFSAR.
System and Component Engineering is developing an Event Response procedure.
The procedure willinclude or reference:
Root Cause Analysis techniques, event severity classitlcations and resources required for analysis.
This procedure willalso include expectations for the team to include cross functional membership from: SCE, Operations, Engineering, Maintenance and QA. Turkey Point's Event Response Procedure is under review for incorporation at St. Lucie.
Human Resources and Training are developing an assessment and remediation plan for possible return ofthe BRCO to licensed operator duties.
AllDS-7s and Operational Events willbe transmitted to the Training Department for lessons learned to be included in the training program.
Training Department willimprove the self-assessment techniques and personnel error analysis taught to all Operations Crews.
QA should evaluate performing a performance based audit on the adequacy and effectiveness of the corporate program fortransferring lessons learned between Turkey Point and St. Lucle for events which occur at the other site, and for events which occur in the industry.
QA should evaluate procedurally defining the role ofthe Quality Assurance organization with respect to industry trends identification and benchmarking.
Willimprove the process for utilization ofindustiy benchmark information within Quality Assurance evaluations.
Evaluate the Operations career path and candidate selection criteria for potential improvements.
DUE DATE 3/31/96 3/31/96 12/31/96 3/31/96 3/31/96 9/30/96 Complete Complete Complete 7/1/96 3/15/96 3/15/96 3/15/96 7/15/96
BO DJLUTIO EVE CO RECT V C
BY DE RTMEN ITEM f/
57 59 60 61 62 63 64 65 66 RESPONSIBLE DEPT.
HR IS IS IS IS IC MAINT CA CA CHEM, HP;SEC, QC, OST, OPS, QA, Services DESCRIPTION Review recent discipline in the Operations Department for consistency and appropriateness.
Operations personnel should be anonymously surveyed to validate perceptions on discipline. Refer to STAR 960080.
Improve the procedure review process to include feedback for UFSAR update for inconsistencies between procedures and the UFSAR.
For the balance of plant procedure not captured in the upgrade process, Information Services willensure that the UFSAR is examined during the three year procedure review process and that inconsistencies are noted and corrected.
Revise the procedure update process to include, within the body ofthe procedure, the applicable UFSAR sections.
Revise Plant process to include documenting sections ofTechnical Specillcatlons and UFSAR reviewed during 50.59 screening of new procedures, PCRs and TCs.
Completed Nuclear Plant Work Order 6055 to repair the deficiency forAnnunciator "E-9."
Other Maintenance Departments willidentify tasks (ifany) which could impact nuclear safety and where the individual performing the task is not permitted to leave until the task is complete.
An HPES Evaluation of this event was conducted.
Corrective Action Group willrevise the HPES guideline to define timeliness of report generation and expected audience forthe report.
Identification of other critical tasks which require continuous oversight Is a generic concern which is applicable to other departments.
DUE DATE 3/$ 5/96 3/31/96 Complete 3/31/96 3/31/96 Complete 3/30/96 Complete 3/15/96 3/30/96
OUTAGE PREP TIONS
IMPROVEMENTS/ACTIONS 0
yemen Complete Unit 2 Refueling Outage Self-Assessment/Critique and identiTy additional improvement actions Establish contingency plans for significant outage activities:
Core Barrel Examination Westinghouse SG Tube Plugs Premrizer Code Safety Valves Reactor Vessel 0-Ring Replacements 4/23/96 Issue Operations and Miintenance procedure upgrades 3/29/96 Improve Outage Mariagement:
Complete the addition of Schedulers for future outage planning Re-Establish use ofCritical Maintenance Management Process Institute outage work scope controls for Unit 1 1996 Outage Assess other plants'M processes Upgrade site-wide scheduling system Complete Complete Complete 4/20/96 8/30/96 16
ST. LUCK1996 SHING REXVKUNG HIE allTAGL' Complete Complete Complete Complete Complete Complete Complete Complete Complete Due 2/28/96 Target 3/28/96 3/29/96 3/29/96 3/29/96 Due 3/29/96 Ops Target 4/22/96 4/29/96 Basic Work Scope Identified Plant Reorgaruzation Initiated Unit 2 Outage Critique Complete Project Lea& Assignments Fixed artment Head Approval ofOutage Work Surveillance, Inspections &Testing Scope Identified Resource'&, Crew Sizes Set Work Scope Frozen/Emergent Work Controls Implemented Parts Identified (Original Scope PWQs)
Non-Emergent Work Engineering Packages Delivered Original Scope PWO Planning Complete Original Scope Activities Submitted/Schedule Freeze Clearance Requests Submitted to OPS - Originals Scope Outage Procedure Revisions Reviewed by FRG Unit 1 Outage Begins 17
13MAR
"'Span"
~'2.00 APRIL
'28
'u In l5 ine and Rx Shutdown poet RCS Nozzles Draft Outline PSL Unit cling Outage 1996 1996 MAY
"'12'
'19"
""" '"K" "I
JUNE 1
Generator Disassembly
-"-.-. -.-- -.-.t Perform Initial Generator Test
....--..-..:.-..-gGen. Stator Wedge Replacement
-I HP Overhaul an Blade Ring Replacement 824 00 24.00 24.00 24.00 Begin Cooldown Safeguards Test Complete Cooldown and Depressurize Gen.
inding Module Installation Generator Final Stator Tasting Generator Reassembly
.ISG Inspection and Tube Pluggi g 24 00 24.00 092.00 18.00 16 00 srm 1
IBl Rx Disassembly Polar Crane Load Test Complete Rx Disassembly LiftRx Head and Inspect 0-rings Fill Cavity, Unlatch CEA's, Remove 8 Incores, Remove UGS 3;~
..t 'A'PSI, SDCCCW Work Window Core ONoad PSI, SDC, CCW Work Window
- l 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 Sha s
Set Rx Head and Final 0-ring nspection Rx casse mbly Fill and Vent Heat-up and Pressurize NOP NOT, QI-11's and PMT's Rx Start-up Roll Turbine
I ICENSxNG
IMPROVEMENTS/ACTIONS I
vement Ams Improve Support to Operations in the Use and Interpretation ofthe PSL Technical Specifications:
Further evaluate cost/benefit ofimplementation ofImproved Standard Technical Specifications (ISTS).
Improve the Technical Specifications'BASE'S:
Submit PLAs to remove the BASES fiom the 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 Eqxxience Feedback (OEF) Program.
3/31/96 Determine the need to track both 10 CFR $50.72 and 10 CFR $50.73.
Reportable Event notifications.
19
NRC VIOLATIQNS Ed Weinkam - Licensing 35-30
~
v) 25 C0 20-o 15 0
10-(4) Potenlial Violations for Feb.
~ ~ 0 Legend
~Actual Vlolatlcns
~Actual NGV's Jan Feb Mar Apr May Jun Jul Aug
'96 Date Sep Oct Nov Dec Date Source: E. Wetnkam
LICENSEE EVENT REPORTS Ed Weinkam - Licensing 20 15-Good Legend Actual
. ~10CFR00.72 Reports 0
02!
10.
~. ~ O.
0-Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'96 Date I
I Data Source:
Ed Wetnkam
OPERATIONS
IMPROVEMENTS/ACTIONS i
OPERATIONS Major Improvement Areas:
Reduce the number ofOperator Work Arounds S
- Reduce the number ofOWAs to less than 15 by December 31, 1996
- Currently working oFas per target goal
- OWA's requiring engineering assistance have been reviewed for inclusion in Unit 1 outage.
- Otage Scope currently under review to ensure PWOOWAs are inclluded in outage scope.
Improve Operator Log Keeping
- Detail in Operator Logs has increased significantly
- Contine OPS Mgmt emphasis on expectations on operator logs especialHy in area of detail on ofF-normal conditions
- Improvements in the administration ofoperator logs have been implemented to improve quality and attention to detaiL
- Removed redunduncy
- Eliminated un-necessary logs
- Used tools built into log systems to aid in review
- OPS/MIS team visited two plants to review and integrated log system foruse at PSL.
This sytem provides ties between various logs and watchstations to eliminate redundancy, provide consistency and reduce a manpower burden. Report due out by end ofMarch. Implementation likelyto be delayed until after Unit 1 outage.
R Improve Operating 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.
Emphasis being placed on procedures to support Unit 1 outage.
- Unit 1 procedures are under review to support Unit 1 outage.
- Operations Manager reviewed three ofthe Phase 1 procedures to ensure expectations of procedure upgrade are on track. Most significant comment is to ensure more adequate flexibilityis built inot procedures to handle a greater variety ofplant conditions.
22
MPROVEMENTS/ACTIONS OPERATIONS
- Have commenced an upgrade ofthe Annuciator Summary Of-normal procedure to a format that is similar to Turkey Point's.
23
OPERATOR WORK AROUNDS Jeff West - Operations 120-100-Operator Work Around: Aprob/em that Impedss end Operator h performtna duttss wkhtn the approved procedures or In accordance weh the htended design.
Legend
~Actual 80-Target 60-0 0K 40.
20 Decrease due to separation of OWA's from Operator Inconventencee and
.OWAs completed ln Jan 1998.
~I
~ Year End Target 16
~aeyyg
~\\eel 0
I~I I
t Oct Dec Feb Apr Jun Aug Oct Date Dec Date Source: P. Frrrord
OPERATOR WORK AROUNDS WORKING LIST Up
~s~<osT PMAII STAR NO.
9642411 9642~8 9&02%64 0-960091 9602%12 Needs PMAI 1-94120512 1 950925 9642-228 1 951080 1-951784 1-952142 1 952143 9602<03 1-950252A 1 95t504 9603032 144110439 1~120513 1441 20538 1-94120549 9643066 1~0123 9643456 1-951413 9602QOO 1%52221 1-960172 9603423 2-950344 2-951340 2-951799 2~0181 2-960336 2-950167 2-950252B 2-960061 2-960334 2-951779 2-960346 2~0169 2-950325 9602-287 9643-149 9642-301 2-950179 DESCRIPTION Puihto-hck PCM defeats SIAS on ICW/COWhcally RCGVS leak-Replace Urfit1 (V1441~)
SB21165&SB21211, provkte posibon indication LvlCntrl Vlvs posMon indicators destroyed during maint.
HVA3A/ACC3Acan'tbeusedinhotweather Lrg Pp starts cause btry chrgr 8 hstr buss to alarm Turbine htch pushbutton on RTGB is not operable.
Turbhe turning gear vrifinot engage fiom control room I/O pressure control vlvs are notable to control press Spurious RTGB gmds have caused many annuncators GEARS indicating wrong positionduring dwnpwr causing akm Eberline CT-1 8 CT-2 akrrm momentarily and chars frequently Rad mon pwr failure"alarms frequently 1B fire Pp start causes battey chrgr to alarm PCM to rotate LCV11-24A&Bvlvs 90 degrees SB 13306 is ibrating, this wifienlarge keyway again ACntmt spr hdr vtv (07161) leahng by seat SB 21234 harxfie is not accessible HP stub shaft has a bow. causing eccen to be beycnd design Pressurizer code salties have leaked frequently DEH filters do not renain fullduring normal ops. Vented 1/shft PCV-12~ does not workacconfing to pmcedure 1A Cond Pp is leaking motor bearing ofi Cntmt spray hdr vlvs leak by seat whle on SDC Au~no feature of DEH is inadequate CST hop seal gets pushed out w/no figin progress. Alarms Annun ghnd seal strn press hi/lo"comes in frequenfiy Root cause ofgas surge tk moisture trap faihre 2A&2B D/G tachometer provide unrefiable read'egs TVEVEV-REFchart has become Inaccurate Numerous problems with Rad Moniteing system D/6 pyrometes 8 thermocouples have chronic loose conn.
Cntrl rm press cntri system does not cntrl press, nuisance alrrns PC-11 hop 3 comm failure causes faire ofaudible alarms SR-14350 fitted while testing CCW N hdr isoktticn vlvs Rotate LCV-11-24 A/Bvtvs 90 degrees PCV%$4I79 gland seal reg does control pressure DFS debris filtersystem alarms need standardizing V4111, iso fuel transfer tube. leaks by seat Failure ofTCV0804 has created OWAduring plant S/U Restore PIA-1140 to original configuration when RCGVS is fixd 2B LPSI Pp has expeienced air bindhg VC217 is leaking by the seat causing the 2A2 Sl hdr to press.
RCP oil fiftPps tripwhen start or stop at RTGB MFWPp sucdon reliefvtvs fail repeatedly Exuaehn sun trap bypass vlvs witinot dose e 100% pwr IC IC IC IC IC IC IC IC JPN SCE SCE SCE SCE SCE SCE IC IC IC IC IC SCHD SCHD SCHD SCHD SCHD NONE NONE NONE NONE WKG SCHD SCHD SCHD SCHD SCHD SCHD SCHD SCHD SCHD SCHD SCHD NONE NONE NONE SCHD NONE SCHD SCHD JPN NEED PCM JPN JPN JPN Mht OST PM SCE SCE SCE SCE SCE NONE NONE NONE SCHD NONE NONE SCHD SCHD SCHD SCHD SCHD DEPT STATUS SCHD SCHD SCHD NONE WKG SCHD SCHD START 5/1/96 SCHD COMPLETTION 5/11/96 4/29/96 6/l9/96 5/31/96 7/31/96 7/30/96 8/31/96 4/12/96 6/30/96 5/30/96 6/30/96 7/1/96 NEED MRB 10/30/96 9/30/96 9/30/97 8/30/97 9/30/97 9/30/97 25
St. Lu nt Procedure Upgrade Project Procedure Status Procedure Title Reactor Startup Reactor Startup Reactor Shutdown Reactor Shutdown Reactor Plant Heatup Reactor Plant Heatup-Reactor Plant Cooldown Reactor Plant Cooldown Turbine Startup Turbine Startup Turbine Shutdown Turbine Shutdown Pre-Start Checkoff Pre-Start Checkoff Reactor Operating Guidelines Rreactor Operating Guidelines Unit Draft Complete Complete Complete Complete Complete Complete Complete Complete Complete Complete Complete Complete Complete Complete Complete Complete Operations Subcommittee Complete Complete Complete Complete In Progress(80%)
In Progress(80%)
In Progress(60%)
In Progress(60%)
In Progress(40%)
In Progress(40%)
Complete Complete In Progress(90%)
In Progress(90%)
Complete Complete ross Functional Review In Progress ln Progress Complete Complete ln Progress ln Progress ln Progress In Progress FRG In Progress In Progress Procedure Distribution Training
- 1. Completion Date for Phase I of project is 17 May 1996.
- 2. Project highlights:
- Procedure enhancements for Unit 2 startup 1 additional outside resource is on site,
- 4 additional outside resources are on site
- 3. Competing for resources:
- Procedure 3 year reviews
- Conversion of large number of temporary changes to procedures
- Unit 1 procedure enhancements to support Unit 1 outage
- Procedure support emerging Issues
CHEMISTRY PERP 0 ANCE EX
CPX WHATIS IT?
- 1. WANO/INFOCOMPARISON OF US /INDUSTRYMEAN ON SECONDARY CHEMISTRY
- 2. S/G: CL,NA,S04 - CONTAMINANT FEED: FE, CU - CONCENTRATINGFACTORS COND. DISSOLVED OXYGEN:FE GENERATOR/EROSION CORROSION
- 3. CL/1 6+ S04/1,7+ NA/.8+FE/5 0+ CU/ 2+ DISS. 02/33 6
- 4. BEST IS 1.0
- 5. PSL ALLPARAM'.TERS ARE< 1.0 EXCEPT DISSOLVED02 AND CONTAMINANTS1-2 WEEKS AFTER REFUELING OUTAGE COSTS:
- 1. RESIN - CATIONANDMIXEDBEDAT SGBDTF MIXBED -NO REALCOST SINCE ITIS REUSED AS RADWASTERESIN CATION - 115 CU. FT./TRAIN
- $ 10,000 NEWAND$50,000 BURIALCOST
-NH3 CAUSES EXHAUSTION(N2H4 BREAKDOWN)
-20 GPM B/DPER SG YIELDSABOUT 10-12 WEEKLIFE
- DOUBLEB/DOR DOUBLEHYDRAZINEREDUCES LIFE BYABOUT 1/3
- USE OF OTHER AMINESDECREASES LIFE
- 2. CHEMICALS - USE HYDRAZINE-S60,000 - $80,000 ANNUALLY
- COULDUSE CARBOHYDRAZIDE- $240,000 - $320,000 ANNUALLY
- COULDUSE OTHER'AMINES-COST OF CHEMICALANDINCREASED RESIN USE
- USE BORIC ACID-NEGLIGIBLE
- 3. WATER-RECOVERED IS CHEAPER THANMAKINGNEW
- 4. BLOWDOWNRATE-60 GPM 1 MW
$500 PER DAYLOST HEAT
- 5. DISSOLVED02 - MANHOURSFOR SEARCH
- MA1NTENANCE
- CLEANINGOF WATERBOXES
- TOO LOWINCtu~ES EROSION CORROSION
- DECREASE BYMORE CHEMICALADDITION ALITTLEMORE ABOUTDISSOLVED 02 ATPSL
- 1. CONDENSER PERFORMANCE POOR NEGATiVE'.STRETCH - TITANIUM-HOTWELLLEVEL-FOULING POSITiVE: TAPROGGE ANDAIRE3ECTOR SPLIT SUCTION
- 2. POOR PERFORMANCE FOR 02 STRIPPING IS APLUS FOR ERROSION CORROSION (AMMONIARETENTION)
- 3. VACUUMDRAG CST/ MST HAS NO EFFECT ON DISSOLVED 02 NO MATTERWHATTHE 02 LEVELIS INTHESE TANKS
- 4. MANYFOSSIL UNITSARE ADDING02 TO REDUCE ERROSION CORROSION 27
HOW DO WE BALANCEABOVE?
- 1. MNIMIZEB/DAS LONGAS RATIOOF CONTAMINANTSIS GOOD (HA/CL~.3 -.7 YIELDSNEUTRALCREVICES) ANDCPIFROMNA,CL, SO4 IS( 1.0 I
- 2. KEEP HYDRAZINE/02AT5 TIMES TO 6 TIMES DISS. 02 WHICH HELPS KEEP FE, CU DOWNANDMNIMZERESIN COSTS
- 3. KEEP DISSOLVED 02 BETWEI2T4 AND9 PPB.
- BEST FOR ERROSION CORROSION
- CPI OF 1.05 - 120
-MNIMZERESIN COSTS
-MNIMZEA1R SEARCH COSTS
- 4. REUSE ALLMXBED RESIN FOR RADWASTE
- 5. REUSE ABOUT 10% OF CATIONRESIN FOR PLANTRESIN SHIPMENTS 28
Unit 1 CPI (Chemistry Performance Index)
~
~
CO I
12000 IL O
0
~r
\\
~
~
~
~r INPO GOAL~ 12$
1.1000 DAILYCPI
QTR AVGCPI
~
Q S
g S
S g
8 g
g S
ol Fl cl DATE 5m I555RSS UNIT 2 CPI (Chemistry Performance Index) 0 CO I
12XO CL O
~~ INP0 GOAL> 1 25 I
t
"DAILYCPI I
QTR AVGCPI I
A Ot A
6 CV DATE 29
1996 MAN REM TARGET 400 300 E
200-Unit 1 Refueling Outage Outage Budget~ 310
~ ~ ~
~ ~
~Actual
~
~ - Target 100 3~23 2 Jan Feb Mar Apr May Jun Jul
.Aug Sept Oct Nov Dec Time (Month) 1996 PERSONNEL CONTAMINATIONSTARGET 80 70.
60 o
50 40 8
30 0
20 10 0
2 3
Unli1 Refueling Outage
~ ~
~Actual
-- ~
~ - Target Jan Feb Mar Apr May Jun Jul Aug Sept Oct Nov Dec Time (Month)
ST. LUCIE PLANTCONTAMINATEDFLOOR SPACE 4000 3500 3000 2500 2000 1500 1000 500 haccessibte area frgewhp Berrchrrreikhe wires Trrrkey Poht eird keephy wtas hrsrrsrry pracrhes.
Post outage recovery of contaminated floor space.
280
~ ~
~ ~ ~ ~ ~
~ i
~
~
'I
~
s Unit 1 Refueling Outage
~AGIUSI
Target Sep-Oct Nov 95 Deo Jan-Feb Mar Apr May June Jul Aug Sept Oct Nov Dec 95 Time (month)
0
N'AINT CE
IMPROVEMENTS/ACTIONS r
vemerrt Pro
~
Mamtenance Procedure Upgrade Pxoject
~
Prograrrm/Procakzes Group
~
Work Pxocess Changes Plant Material Condition (Key Performance Indicator):
~
PWO Backlog
~
Control Room Green Tags (C-Tags)
~
Aged PWOs (>12 months - Golden Oldies)
~
Leaks (Pron~/Secondary)
~
Temporary Leak Repairs On Going Issues:
~
Insulation Pxogram (4/1/96)
~
Consolidation ofTool Rooms (7/1/96)
Opportunities for Improvement:
~
Planning (Backlog APriorities)
~
Process for Handling PWO's in Field Relations/Teamwork
Work Process Simplification Team PIN/PSL Report ofProgress 33
Level 1 Implementation Schedule for March 1996 i
I i
Mngmt. Rev. 8 Appvl.
Devlp. Instr. To Add Develop Database i-I I
I i
I I
i i
I I
I I
I
~
~
i i
i i
Staffing I
I I
I I
I I
I I
i I
Develop Answering Sy Advertising Bulletin i
I I
I I
I I
I I
I Formal Plant Notific Temp. Post Impl. Tra I
I i
0 14 21 28
NF "CANDO"IT-
- NO PAPER REQV RED FOR MANYTASA'S:-
C5 Ac/net and Tllhten
- Manual Valve Packing
- Bolts and Connections
- Non S.R. Pump Packing.
Q 'llrouhlo IhootlnI Cl Stuaee and Luhrleatlon C! Light Nalntananea.
l5 )nsmeator LIIhte Cl CoInyonent Claanlnl C} met aalu)Itutant PR D AIBA:
OU'XSSM THE FR D AREA R5 One number for ail Maintenance Shops l8F Leave your name, phone number, a description of the problem and specific location.
IBF Normal res nse time wB) be 3-1 0 days LInless a higher levei of concern is communicated.
I8r Safety concerns should be communicated directly to a supervisor.
RENEMBER... Emergencies can be repoitet the Shift Nanager at Extension 7501.
ST. LUCI NT MAINTENANCEPROCED PGRADE PROJECT TASK 1T1: DEVELOP PROCEDURES/GUIDELINES FOR FREQUENTLY PERFORMED MAINTENANCEACTIVITIESWHICH CURRENTLY EMPLOYTHE USE OF VENDOR TECHNICALMANUALS tV)acr'r,
'>vaI/c's'-::>!':,,
lac Opera Fuel PB LeVel Swilehea mt/90 i&C fisher level Confro!era 1/31/90 ukC srsaNe Cbl Bdlodcators 6/St/90 MC Msgr>ctrd Level Swhches 6/Sf/90 I&C 1400069; Add Ncw Eqt/pmcrl Iac Rosemounl Trsnsm'hers 9/X/98 I&C Bench Cslbraaon 1 I/X/90
.Cc'nd Ak'Epct,"
> s>>>>'x>>>>> ".8 eTIIVaf/w~~;.~
c'II&tcfRCsL;rA...,
Iac Ul Cat of CNMT Process Monit I/29/90 Iac Ul fasrl Vert, FH E>fk ECCS. PINS I&C Ul Cal SGBO Red Montors OX/96 Iac Ul Cel olCCW Bad M<<Nore f/XI90 Iac Ul lcldown Process Mornors I/9luge MECH Orsgcn Vakres 1/St/90 I&C V2 Cen. Alorric PIC Proc Moril
&ISI/90 MECH Borg Warner
~ares 6/31/90 Iac U2 Cen Atorrfc GM Moritor 9/X/98 Iac V2CenAtonfc SSL Proc M<<N 9/x/96 Iac Vgcalnraaneae Oar. La&at,uvRCM
'lg/St/90 I&C Vs Roc>oic Cp dec AlomProc Mon 10i&I/90 Iac V/fl2 LPM tf/X/90 I&C Vl 8 2 Co<<el of Pros MorN Rdny II/X/90 MC Tec Isotators Catbrsacn tgrgt/90 I&C Ofhng-I600029 I&CProcedure I/St/97 I/SPBS~';:;4k SS~Mi.'<%~+&>/sr MECH lasts Vat/as MECH Pa<<he
~tres I/91/90 MECH Tergal Rock elves I/St/90 MECH Ysrwsy Valves MFCH c sangh<</re elves SIXI90 MECH MECH cstcn Hydraulc
/smash<<y Valves elves ICV91/90 II/X/90 Iac V2 Safe guards Met<98>>"":.">>%4 MECH ctanVaf/es MECH MECH Cont Coup.
Letdown Vtvs 1/H/98 MECH H<<vyP/aa
~IvesVstves frat/90 MECH Orader (Cons of dated) 9/X/90 MECH akor Eny
~ares 1001/90 MECH ale&Inc elves II/X/90 MECH 0eveh>p I2/SI/98 af/>9 PSL-2 Ptact SpecMe Procedures
,">F'IIB""";UTIL.iN '"'
>0
- >k>I@M '
'ru ya>dkInjb>(gy gj>>QQ "".ijt'II 8'"
.-".l %%toNtklF::iINoktnf'IIbN~>Iggjggjr@'I'J""
'i%5 SP
ST.. LUCIEPLANT MAINTENANCEPROCEDURE UPGRADE PROJECT TASK¹2: REVISE AND ENHANCE EXISTING MAINTENANCEPROGRAM AND EQUIPMENT PROCEDUREs KNOWN TO REQUIRE IMPROVEMENTS
'o Coincide with DivisionWork Process Revise Senstllve System Procedures Oevetop WIN Team Gutdet/ne ELECg~g',jr'"K<)jPq Revlso dumper and Ulled Lead Procedure Revise NPWO Procedure AP-00100432 3/29/96 ELECT 990060 Metering Equtp 3/29/96 ELECT/NC Raychem Proo 3/29/98 Revlso Conduct ofMaintenance ADM08.02 mNo9iRb5iN ';88iCefiibif'-.", R9'ifiU8'.;i"i':4I-".5bNN'.'4 NMN4liV.:.'FACFA l,il%~~52 /gag>KMjj~ )~N?r'.g cQ0@i<cJgQ:s~+r%j
'ST. LUCI NT MAINTENANCEPROCED UPGRADE PROJECT TASK¹3: CONVERT NON-SAFETY RELATED PROCEDURES INTO MAINTENANCE GUIDELINES fr'll@+g@k$4y')
Bee,alt:Sa:,'":m=;
INt88e'W~
(SNl8 eA~~
MP,, VgiMiabtPP
)> t) tStSStli~N~<<4 hctBQ$,8y'4~@
)
tt.,'Ge'n't'tM!aihr<
WcCgv+5'>f
+>>'>>P
,'-'eye;:retnpj@
3NNI.SN/SR'I l88(k's%~~pR" liiglltf?Cc't'mgP 4lSÃ~5'%%c OW?88+%m%
QPfPg<Rjjg I'0
- .. OVBm re 4'. BCBN
'Bl'>%
POWER BLOCK PWO BACKLOG Joe Marchese - Maintenance PWO Backlo:
PWO backlog are non-outage corrective work orders (Work Type 5 status 22-48) on components/equipment in the power block. Total includes all Work Type 1, Work Type 3 &Work Type 5. (ail hold co 900 800 700. ---....
600 0
500.
400 300.
200 t00 TOTALss 4920 Good
~unit 1
~VNT2
~Common
X To!el
" ~ ~ Terpet Tespel ~ 550 Tolel 176 Mech 155 Iac 20 Eteo
)PTtt-260 tt/P5)
Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'95
'96 Date Oato ecosoc:
pessport
SUMMARY
STATUS Discipline Mechanical Electrical t&C ProJects Total Vnlt1 128 82 219 Unit 2 141 16 83 241 Common 28 15 44 Total 297 24 180 504
~c-Ta s:
CONTROL ROOM DEFICIENCIES C-TAGS Randy Olson - 1&C
- The number of Control Room/Board Green Tags.
It provides an indication of the attention given to maintaining control room instruments ln an operable condition.
60 70 60
~......
OUTAGE-9.
UNIT1 =6 UNIT2 = 3 legend Qccd
~ken.Outage
X Totsl kon-Outage Torgot cn 50.
ro
~
~o 0
>o 30 0
H II 20 10.
0.
I I
0 0 h
~ ~
~
kon.oulsgs Target ~5 Sep Oct ttcv Dec Jan Feb
'85
'88 Mar Apr May Jun Jul Aug Sep Oct Ncv Dec Date Data: M. Willis
SUMMARY
STATUS Ready to Work or Workin Engineering/RTA AWP Other Holds Total Non-Outage 28 Outage Total 18 37 Oldest Discipline 10/2/94 EM (OUTAGE) 5/4/94 I/tC (OUTAGE)
AGED PWOs > 12 MONTHS GOLDEN OLDlES Joe Marchese - Maintenance
~Aed PWOe:
Non-oulage corrective maintenance work type 5 PWOs older than 12 months.
50 40.
O 530 eT o 20.
0Z 10 Good Legend
~untl1
~unI(2
~Common XToraI Targe(
Sep Oct
'95 Targe( ~ 0 (PTII - 3 III95) l~
I I
I I
I Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'96 Date cela Source: paedport
SUMMARY
STATUS Unlt1 Unit 2 Common Total Mechanical Electrical I&C Construction Total 10 0.'
15 Oldest PWO
//
Discipline 10/15/92
- 0786, Projects 8/4/93 0562
Leaks:
- Active leaks (primary and secondary) 140 120-100
~ -. ~.-..
g 80.
60 0R 0
~
s s
s s s s
~ se 4
OUTAGE
. UNIT1-"16 UNIT2-"4 Legend
~ Non.Outage I
X Total Non.Outage Target 20 0.
Sep Oct Nov
'95 s s s
s s s s ss s s s s s s s s s s s s s s s s s s s
s NonOutageTargets10 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'96 Date Data Source:
Passport
SUMMARY
STATUS Unlt1 Unit 2 Total Primary - Outage Primary - Non-Outage Secondary Total 13 13 28 15 15 10 18 43 Oldest (Non-Outage)
Status AWP AWP 12/10/94 6/14/95
LEAKREPAIRS FITTINGS Greg Pustover - Programs Leak Re airs:
Leaks that have been temporarily repaired.
55 50.
45-Lo 40 H. 35 IY 30 25-ao 0z 15 - --
~ ~ -- ~ --
~ -
~
~ ~ ---------~--
0 -.
~
~ --..---..--
1 5-0 LegendD
~ Unit 1
~ Unit 2 l
I l
l Sep Oct Nov
'95 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'96 Date Oala Source:
Joel Kagan(SCE)
SUNIMARYSTATUS Unit 1 Unit 2 Total Total 17 21.
A Bar Code Tool Control Program Project Scope Bar Code for Tools and Consumables Team Member 2-FPL Exempt 1-Crew Leader 4-UtilityWorker Schedule In Service with Tracking System for April Unit 1 Outage
QUALITY ASS CE
~
QA AUDITS/PERFORMANCE MONITORING Audit finding documenting the use of vendor technical information in an unapproved manner illustrates the need for continued improvement in maintenance procedure technical content.
Observation ofinadequate cleanliness. controls in fuel storage areas indicate the need for increased management attention and interdepartmental cooperation INDEPENDENT TECHNICALREVIEWS Assessment ofPSL EDG Maintenance Program Five recommendations resulted
~
Require root cause investigation for in-house events in "condition reports" procedure.
~
Duties, responsibilities and accountabilities should be accurately assessed and communicated for system engineers.
~
Provide additional OPS personnel training re: EDG Operations problems.
~
Develop mid-cycle PM procedure.
~
Improvements to GMP 1/2 00180 (Safety Related PM Program)
TECHNICALSPECIALIST INVOLVEMENT Security Audit (1)
Diesel ITR on Maintenance Program (1)
Conduct ofOperations Assessment (3)
. ~
QC INSPECTION PROGRAM Continue to combine the best of maintenance/construction programs under one program and a single supervisor.
~
OTHER QA ACTIVITES Participate in a plant initiated self-assessment ofmajor aspects ofplant operation during the 2nd quarter.
~~~T E
COMPO EN'GINEZRZNt
IMPROVEMENTS/ACTIONS ENGH%5322NG Ma r yement Improve Equipment Reliability:
~
Emergency Diesel Generators (Unit 1/Unit 2)
~
Reactor Coolant Gas Vent Valves (Unit 1)
~
Pressurizer Code Safeties (Unit 1) 6/96 6/96 6/96 Strengthen System Performance Monitoring.
~
Complete Maintenance Role Implementation Complete PM Basis Program 4/96 12/96 46
EQUIVALENTAVAILABI FACTOR - UNIT 1 100 75 50 uO 25 88.9 1 ~ ~ 0 ~
0 ~ 0
~ ~
' OJ Target ~ 78.5 Le end
~Aclual Target Good 0
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'96 Date EQUIVALENTAVAILABILITYFACTOR - UNIT2 C$
rrr o>
100 75 50 25-78.7 87.9 Target ='95 Legend
~Aclual Target Good 0-t E
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
'96 Date
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 P ant initiated 6 year Allunit 2 actuators overhauled Nov-95.
failures identified fatigue due to length o erhaul Preventative Maint Unit 1 actuators scheduled for May 96 outage.
service; recommended 6 year periodic factory overhaul STARS 950059 & 950529 it m.
Unit 1 EDG Governor unstable Older design electronics
- 1. Replaced all suspect iectronlc components and endor rep support "NOISY"inputs identified.
PWOs:
1A: 95026166 B: 95026332 Vendor design: governor wiring during surviellances (tied to grid) very susceptible to "NOISE" ptlmized alignment with Engineering evaluating upgrade of governor system to more current design (Woodward 2301A) with proven noise rejection features.
Unit 1 & 2 EGG Governor Actuator Wiring grounds Raychem sleeve covering for abrasion concern:
rough surface; vibration induced abrasion.
brasion protection Unit 1: May 96 STARs 951062 and 951055 PWOs 95024478 95026057 Unit 2: April 97 harness wires ln contact with ompleted repairs and added Engineering developing improved design to eliminate Unit 2 Control Relay sockets failures Pins relaxatlon and soider
'oint failure due to cracks.
suspect sockets replaced.
NPWOs: 1A: 95031756 Removal / Insertion (PM) and 1B: 95031676 Two failure modes identified:
Allfour EDGs inspected and Engineering Is evaluating design change options; ie, new relay base or change relay to one that does not require base/ socket.
vibration. STAR 951721 2A: 95031265 Report JPN/CSI MET 95-223 2B: 95032588 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 NPWO: 6035 visual exam of fuel line components at least monthly.
Pipe replaced: others inspected System engineer monitors engine piping closely; Unit 1 Radiator performance Identified during trend analysis Radiator replacement Is of engine jacket water temp.
scheduled as an outage job STAR 951575 provided safety assessment to operate until May 96 outage replacement.
System engineer monitors and trends performance.
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 flowstream (leaking)
Unit 1 outage Units 1 and 2 diesel fuel transfer pi ilures Underground piping; corrosion PC/M implemented on 1A, 2A, New design piping incorporates stainless steel guard pipe.
ofunprotectedcarbonsteel.
and2B:92-225
-096.
2/19/96
LEMENTATIONSCHEDULE 1996 THE MAINTENANCERUL Updated 3/12/96 LEGEND:
xxxxxxxxxxxxxxx xxxxxxxxxxxxxxx XXXXXXXXXXXXXXX XXXXXXXXX II Doscrtpt ton Person Rosponslblo Dalo Complete
= Scheduled
= Working
= Complete T~Aft,.o/(
E G'!Peart(g
<~ALII,I Ana'lyze Untt Perf, Serums,'Outage Delays To IDa(1)s Clmlno II Evaluate Potenltal a(1)s 8 fssue To STARs Clmlno II Procedurallze Shutdoviii Safety Assessments Korth II Create ale Rbot Cause Piocedure Snyder II Provkle Ttatntng To New Expeit Panel Snyder II Place MR.Flow Charts In Slrategtc Spots alcheskt II Revise NPWO, STAR, FOP Procedure's WalchesM II Comp Htstortcal Revfew For Determlnlng a(1)
Snyder II Document e(1)s I/Ia PMAI Snyder II Standardize SSC lridlcators Walcheskl II Peer Revfew AtLlmertek Snyder II Propose Goals, Corr Acllons 8 Mongor For a(1)s Owners II Attend NEI Conference Snyder II Program Compttance Plan-Flnatlzo 8 DtsUib Swlatek II Expert Panel Revkrw AllSSCs In a(1)s Owners II Coordinate PSL Mafnt Rtsk Assessments Snydsr II Comptto SSC Inrgcators 8 Start Quarterly Dhlrlb Clmlno II Develop Perlodfc Assessment Repor I Format Watche ski II Host NEI Peers Crlllque Of PSL Malnt Ru!e Prog Snyder II Incorporate Peer Critique Items Snyder II Perform Second ITR Of Malnt Rute Impfem AlSI.Lucte QAII JAN 10 JAN 31 FEB 15 FEB 28 MAR 15 MAR22 MAR 31 APR 7 APR 30 JUL 10 FaVSERSIMAINTRVLPRE
ENGINEERING
I ENGXNEEKING IMPROVEMENTS/ACTIONS r
yement Improve Configuration Management Controls:
~
Implement Temporary System Alteration
~
Reduce Open TSAs
~
Reduce Age ofOldest PCMs 3/31/96 6/30/96 12/31/96 Improve FSAR
~
Assessment Team Effort Corrective Actions Unit 1
~
Complete identification
~
Disposition of inconsistencies Submit update to NRC Corrective Actions Unit 2 Complete identification
~
Disposition ofinconsistencies Submit update to NRC Maintenance Procedure Review:
~
608 Prouxhzes targeted to be reviewed
~
Presently 192 have been completed
~
Scheduled to complete February 1997 SLl-14 Outage Modifications
~
53 PC/hh approved for Outage
~
30 PC/Ms issued by Engineering
~
23 remaining PC/ill to be issued Complete 12/15/96 9/30/96 50
PLANT CHANGE/MODIFICATIONS Kris Mohindroo - Engineering 150 125-100 75-0 0
50-Good Open PC/M Target ~ 80 Legend
~Unlt1
~tJnlt 2
~common
X Tolel
-- Target 5
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~
~
2 Oct Dec Feb Apr Jun Date Aug Oct Dec Dala Source:
Kris Mohlndroo
SUMMARY
STATUS Disci line 0 enPC/M PC/Ms >24 Mo.
Unit1 43 12 Unit 2 61 Common Total 113 23
TEMPORARY SYSTEM ALTERATIONS TSA Kris Mohindroo - Engineering 50-45 40
~
35 30.
25 0
o 20
~
15-10
~
Good Legend
~unlt1
~unlt2
X Total Targel
'farget= to.. -.
Oct Dec Feb Apr Jun Date Aug Oct Dec Data Source:
Krts Mohtndroo
SUMMARY
STATUS Dlscl line Mechanical Electrical l&C En Ineerln 0 eratlons Health Ph slee Construction SCE Total Unlt1 12'nit 2
Total 16 Oldest TSA Disci line 12/13/94 l&C
/94 I&C
. ST. LUCIEPLANT-10 ST OPEN PC/M's PC/M NUAIDER 02I-184 DESCRIPTION RAB High Pressure Sodium Lamp Replacement DATE DATE ISSUED FRG'D 2/23/84 3/23/84 SCH CLOSE DATE 6/30/96 S rATUS ANDACTIONS REQUIRED TO CLOSE As-fail PC/M. Completed scope needs to be documented, then closure paper can be processed.
245-284 RAB High Pressure Sodium Lamp Replacement 12/17/84 6/30/96 As-fail PC/M. Completed scope needs to be documented, then closure paper can be processed.
114-985 193-189 Goulds Centrifugal Pump Oil Seals Open BIowdown Cooling Water Heat Exchanger Vacuum Breaker Valve Changeout 12/31/85 2/I I/89 12/11/89 6/30/96 5/30/96 As-fail PC/M. Completed scope requires documented, then review for paper closure.
PC/M implemented.
Action plan to resolve slight periodic leakage problenis willipermanent drain catcher. Engr PC/M planned for 4/19/96 276-189 335-190 ICW Isolation Valve V21165 Relining 12/6/89 2/7/90 Check Valve Flinge Pin and Bonnet Modifications 7/18/91-4/13/93-on CCW pump discharge check valves V14143, Sup 0 Sup 0 V14147 and V14151 3/25/93-4/13/93-Sup I Sup I UNIT I OUTAGE UNIT I OUTAGE PC/M work activities placed on hold U194 fall outage due to required duration-work scope needs to be reviewed and planned for the upcoming U196 outage or PC/M cancelled.
PC/M implemented on valves Y14147 and V14151. Modifications to Y14143 planned for next refueling outage. Willclose PC/M upon completion ofthe work activity 171-191 186-191 086-292 203-192 l<csizing and replaccmcnt ofMOVThermal Overload Devices on 137 MOV's Intake Cooling Water Support Modifications Radiation Monitoring Computer Replacement Replacen>ent of95 Sigma Meters in thc Control Room and Flot Shutdown Panel do to obsolesence Issiles.
7/I/92-Sup I Not FRG'd 4/22/92 5/7/92 12/21/92 4/6/93 7/17/91 9/19/91 UNIT I OUTAGE UNIT I OUTAGE 5/24/96 5/24/96 PC/M implemented on 122 valves.
15 valves remaining to be modified.
EM needs to schedule remaining work. Willclose PC/M upon completion ofthe work activity Sup 0 Complete.
Sup. I was budget approved at the MRB I/30/96 for implementation during thc 1996 Unit I outage.
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 upon completion ofthe work activity.
PC/M partially implemented with 15 instruments installed. Recommend as-building what work Iias been completed and close PC/M. New PC/M's can then be generated based on planned work activities.
ST. LUCIE NUCLEAR ENGINEERING UNIT 1 1996 OUTAGE SCHEDULE BASELINE SCHEDULE JAN. 2, 1996 UPDATE AS OF MAR13,1996 R. ENSLEY LEGEND:
ENGINEERING DELIVERABLESNOT SCHEDULED:
<<REA Number
<<Description
<<Date Due
<<Resp. Disc.
STAR 950252A LCV-11-24 A/B SITE CIV STAR 951827A AUTOXFR S SITE ELE FUELS PEG MEC SLN 954II 3 10 STAR 950794 ONDEPL INCOR LPSI MINPRESS FUIU(0 ac(A ~
C3
+
C Engr'd Matls. Ordered
<<Engr'd Matls. Required
<<Original Plant List
<<Emergent Packages
<<By Outage Start/During Outage
<<PC/M Not Required
<<Capital
<<Shaded Box Represents Completed Package STAR950970 POLAR CRANE 32896 SITE CIV STAR 951 491 STAR 94110378 LCV11-18B1 HCV08.2A&B 3.28-98 3 28.96 SITE MEC ~
SITE MEC SLN 94-012-10 AOVDESIGN 3.28.96 PEG MEC +
SPEG 944I42-1 0 AIR LOCKJLL 3-28 96 JUNO LIC STAR 951136 MV08.1B MTR 4.30.96 SITE ELE SLN 934!61-11 A/DCRNS 4-15-96 ITE MEC/CI SLNBl:
!qadi&::::I PEG ELLE Krf%:9ii 8B708 00 884 LVV
- 811!PII::::::
PEG!MED FiÃli::etl!055oitent'N 84 8IK RELL 8::W4$,':,:I
.:'EG MEOI I 8L'NN'68::tt88!
gihP'ILL'/'dGI 9!1 96! ii i i i STAR
'SIN 6LN 95.001-1 0 CNTMTA/C 3 25.96 PEG MEC SE 02.1.4 FAILEDST TIME 3 22.96 SITE PRC bb
'.tlN IV 6'ti608 LKl&is
SITE MEC STAR 950925 TURN GEAR 328 98 PEG I&C SLN 95-048.11 COMITPRO VLV 3 28.98 SITE MEC SLN 95 008-10 STM BYPASS 3 28.96 SITE MEC STAR 960075 CME PG-57 3 2848-PEG ELE SLN 944I29-10 GRAF GASKETS 3.28.96 SITE MEC STAR 951783 HPS!/LPSI IND 3-28.96 SITE I&C STAR 952202 SLN 95.048-10 ED/G RELAYS COtTT PRG VLV 3.28.96 3.2848 PEG ELE Q
SITE MEC STAR 960122 RX ALRM74-1 3.2846 SITE ELE STAR 950725 INSP 8/G PLUGS 3.28.96 CSI
+
STAR 952162 BE PLUG 89-01 3.28 cI6 CSI
+
STAR 951615 RX VES EXAM 3.28 96 CSI
+
SLN931.10 CEA MG SET 3.2846 SITE ELE STAR 951667 SNUBBER CRIT 4-1 5.96 SITE CIV STAR 951089 13306 KEYWY 412-96 SITE MEC STAR 94110486
~ RWT INSP 4.12 96 PEG CIV UI RELOAD 4.8 96 PEG FUELS STAR 951885 DEH D/P SWTCH 44!.96 SITE ELE STAR 951197 1A1 RCP CCW 540.98 SITE MEC STAR 950565 1B2 ANNA.13 540.96 PEG ELE +
STAR 950428 MV09.13 ST NUT 540.96 PEG MEC STAR 950882 EXCORE POS 540 96 SITE MEC IIIIAR WEEK BEGI APR GICOMMONIDRBSKYLNE$1996PIAPRE MAY 0
CO CTIVE ACTION PROQ
IMPROVEMENTS/ACTIONS ACDON PROGPAlVC rIm vemexrt Improve Analysis Capability:
~
Obtain 1995 data Rom other plant departments to combine with STARs Obtain analysis methodology Born industry best plants (Turkey Point/Callaway)
Produce 1995 Summary Report Critique Summary Report
~
Present conclusions to FRG/CNRB Standardize Corrective Action Process withNuclear Division Implement PMAIDatabase Implement PMAIPronxiure FRG approval ofCondition Report (CR) Procedure Training on new CR process Convert STARs to CB/PMAI Complete Complete Complete 6/96 Complete Complete
-Eomgkete-
. 4/96 55
. OVERDUE STARS Priorit 123 Bob Dawson - Corrective Action Program 100-90 80-70.
60-vl 80.
40.
30.
20-10 0
~
I l~
~ ~ 0 0 1 ~ ~ ~ ~ ~ 0 J 0 0 I P
\\
~
0 1 J J J
~
\\
0
~
~
~
-X-Total Dec Feb Apr Jun Date Aug Oct Oec Data Sourco: Bob Oawson STATUS
SUMMARY
Discipline Chemistry Const Services Elect. Malnt.
Englneerlng I&C Mechanical Operations OST Reactor Eng, SCE PM Prot Serv TOTAL No. Overdue 0
0 0
0 0
0 0
19 Note:
Conversion to CR system is ln progress. As of 2/29/98 there were 783 STARS remalnlng to be converted.
M'ATERIAT.S
IMPROVEMENTS/ACTIONS MA'DREGS r
vement Outage Material Availability:
~
Have all identi6ed material available for the outage 3/29/96 Reduce the Cost of Carried Inventory:
Reduce value ofinventory to $38 million Reduce the, value ofovermax inventory to $2 million 12/31/96 12/31/96 Increase Spare Part Availability:
~
Reduce the number, of~ks to 500 6/1/96 Reduce the number an age ofnon-outage work order AWPs to 7/1/96 70 Reduce the number ofpurchase requisitions older than 30 days 7/1/96 to 20 57
INVENTORYVALUE Dan Quilty - Nuclear Materials Management ro r0 1 00
~ ~ ~
~
~ I 0 0
~
\\ ~ ~ ~ ~
\\ 0 0
~
0
~ ~
~
~ \\
75
~
Legend Good I
~ACtllal Target re 0
.O 50 25 44.2 43 1 39 4 42 42.3 Target = 38 0.
Oct Dec Feb Apr Jun Date Aug Oct Dec Data Source:
Norman Quesada
OPEN REQUISTIONS OVER 30 DAYS 250.
200
~-
150 100 C
o 50 111 126
~Aclual
Target Good 0
~
Jan Feb Mar Apr May June July Aug Sept Oct Nov Dec Date NON-OUTAGE AWP (STATUS 45 &48) 160.
140 120 100 80.-
50.-
40
~
20 0.
Jan 135 154 Feb Mar Apr May June July Aug Sept Oct Nov Dec Date
~Ac/uai
- - ~ - -.Target
SLM4 OUTAGE WORK ORDER AWP'S 200 150 8
100 50 0
0.
Jan 4e 154 Feb Mar Apr May June
~
July Aug Sept Oct Nov
=
Dec Date
~Actual Good OVERNlAXlNVENTORYVALUE 3.5
~
3-.
C)
C) 2.5 C)
CI 2
(g 1.5 0
0.5 -
~
0 2.B
,g 3.3 II
- -% -.Aclual
'Target Jan Feb Mar Apr May June July Aug Sept Date Oct Nov Dec
WAREHOUSE RESTOCKS 3000 2500 2572 2000.-
1500 ~-
3 1000 1280
~Actual
Target 500 0
Jan Feb Mar Apr May June
. July Aug Sept Oct Ncv Dec Date
NUCLEAR MATERIALSMAN ENT 10 OLDEST AWP'S WEEK ENDING MARCH 8, 1996 UN ORIGINATION DATE COMPONENT/ASSOCIATE/NAME TITLE WORK ORDER SCHEDULE STOCK CODE P.O./P.R.
ACTION COMMENTS 11/29/91 CW-99/BACKWASHOUTLET FROM SS-21-1A LINE 1-8-CW-99 HAS SEVERE PITS 9103615801 SL1-14 30916-1 33870-1 33878-1 185970-3 PR 25515 PR 22486 PR 22487 PR 25516 PUR PE PE PUR QUOTE DUE 3/8/96 RESOLVE EQUAL //041734 RESOLVE EVAL//041735 QUOTE DUE 3/8/96 1/14/93 V14143 CHECK VALVEFOR COMPONENT COOLING WATER PUMP 1A DISCHARGE IMPLEMENTPCM
//335-190M.
9300144401 SL1-14 177522-1 PR 25881 PUR QUOTE DUE 3/12/96 3/18/93 SR-07-1B/SAFETY RELIEF VALVE FOR LPSI 1B 8 HPSI 1B PP SUCTION PERFORM IST INSPECTION 8 RPR FLNG LK.
9300864501 SL1-14 37251-3 57194-1 57594-1 PO 14283 PO 13496 PO 11942 PUR DELIVERYDATE 4/5/96 DELIVERYDATE 5/10/96 DELIVERYDATE 3/1/96 5/14/93 AFW PP 1C GOV/GOVERNOR/AUXILIARY FEEDWATER PP 1C GOVERNOR REPLACE VALVE BONNET NEXT OUTAGE IAW 9301401901 SL1-14 183264-1 PO 94934 91034 REF. W/R //95014323 8/4/93 J5-1 GRAPHITE ANODE FOR INTAKESTRUCTURE REPLACE TRAVELLING SCREEN ANODES 9302132001 SL1-14 21776-4 PR 25012 PUR QUOTE DUE 3/15/96 8/4/93 ICW PP 2B/MOTOR FOR INTAKE COOLING REPLACE MOTOR HEATERS 9302131801 SL1-14 203502-2 PR 26093 PUR QUOTE DUE 3/22/96 3/19/94 SR-14-8D/SAFETY RELIEF VALVE FOR CONTAINMENTFAN COOLER HVS-1D CCW OUTLET INSTALL REPLACEMENT VLV DURING SL1-14 9400644401 SL1-14 34213-1 PO 14069 PUR DELIVERYDATE 3/15/96 4/13/94 7/14/94 9/26/94 LCV-900SNALVE/LEVELCONTROL VALVEFOR FW REG STATION (FCV.9011) 15% BYPASS V18191 ISOLATIONVALVEFOR INSTRUMENTAIR SUPPLY HEADED TO RCB FCV-24-107 CONTROL VALVEFOR ESDRAIN TO CNDSR1A BODY EROSION/FLOW CAGE GASKET LEAKAGE PIPING NEEDS TO BE STRAIGHTENED DISASSEMBLE AND INSPECT REPAIR AS NEEDED 9400856501 SL2-10 191603-4 PO 12576 9401747201 SL2-10 34625-4 PO 14273 9402439601 SL1-14 59567-4 PR 24642 PUR PUR PUR DELIVERYDATE 7/2/96 DELIVERYDATE 3/29/96 QUOTE DUE 3/1/96 UPDATED ANDSUBMITTEDBY: MATERIALSMANAGEMENT-N. QUESADA.
0308OLD.XLS
4
SERVICES
IMPROVEMENTS/ACTIONS or vement Improve the ProcedLue an n Pl P.
B QdhyP Mh nv Reduce the number ofactive TCs prior to placing Unit 2 in service - 90% reduction accomplished.
Clarify definition ofTC versus PCR.
Consolidate TC and PCR process.
Revise QI 5-1 to clarify process and accountabilities.
Benchmark process against other utilities.
t t
artment del Complete Conxplete Conxplete Complete Each department head has an identified scope ofprocedures to Complete address.
ImIprove the Safety Focus ofFRG and Ihorougbness ofReview:
Submit Tech Spec amendment to delete need for FRG to see non-nuclear safety procedures.
Review need for detailed agendas and meeting minutes.
Benchmark process ag unst other utilities.
Achieve routine Operations participation in FRG.
Reql'ure sponsorship ofnon-routine items.
Establish FRG subcommittee to pre-screen submittals and reduce FRG volume.
Revise FRG process and proexhre IAWnew Tech Spec.
6/30/96 Complete 4/1/96 Complete Complete Complete 10/30/96 63
TEMPORARY CHANGES TO PROCEDURES Jim Holt-Information Services 350 300 250-200-0 o
150-Good Legend
~Unitt
~unlt2
~common
X Total Target 100 50 0-Oct Dec Feb Apr
- Jun, Date I
Il~
Aug Oct Dec Data Source: Jlm Holt
SUMMARY
STATUS Oldest TC (days) 89 89 89 89 67 68 Discipline 0 erations Mechanical Electrical I&C Reactor En SCE HP Total Unlt1 24 28 Unit 2 21 12 41 Common 12 Total 45
INDUSTRIALSAFETY - RECORDABLE DOCTOR CASES Kim Heffelfinger - Protection Services 35 30 25 g
-20 15 K
10-15 22 Target ~18 Good Legend
~Actual 1995
~Actual 1998 Target Oct Dec Feb Apr Jun Date Aug Oct Dec Data Source: Nm Heffelflnger
ST. LUCIE PLANT BUDGET PERFORMANCE INDICATOR 1696 06 M BUDGET PERFORMANCE ACTUALSTHRCVGH FKBRVARY1996 O
10 I8
~tt CL' 6
O C2 6
0X t
'1 4
'I 2
Cp TO 60 B
60 0O 40 5
~BUDGET (MONT16.Y)
~ACTUALS (MON(HIT)
~FORECAST (MONIHLY)
~BVOGET gVMVLATWE
~ACTUALS gVMVLAT(VE
~ X FORECAST gVMVLATIVE 2
~ C
~ ~
6 0
C I
4 C
L C
(
C'0 1SS6 CAPITALBUDGET PERFORMANCE ACTUAISTHRCVGHFEBRUARY 1996 14 O
2 OO EO 0
12 10
~BVOGET (MONR6.YI
~ACTUAIS (MON(HLYI
~FORECAST (MONIHLYI
~BVCGET (CVMVLAT(VEI
~ACTUALS gVMVLATIVEI X
.FORECAST (CVMVLATIVIB CL' 5
OO 2
t JAN FKB MAR AFR MAY JVN JVL AVG SKF CCT NOV CFC 2e~eeteteeFyeluds SUMMRC42$ L921209 66.
100%
90a/a 80e/e tL 70e/o g
60/a 50'lo 40%
30%
C 8
20/e
~ PTN
~PSL 10%a
~4l%t I
92/o 85'/e 92'la 65%
100'/a 35%
0%
2e/a 67
RESOURCES
IMPROVEMENTS/ACTIONS or vement Amm Strengthen the Management Skills ofour 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 personnel on assessing employee performance.
Evaluate and modify, ifnecesmy, accountabilities offoremen/
supervisors to amre handling employee performance is a key responsibility.
Ensure these accountabiHties are clearly identified in the forenun'upervisor selection process.
Interview foreman and supervisor incumbents to ensure they are willingto meet the expectations ofthe position in handling employee perforumce issues..
Complete 6/30/96 Improve Labor Relations:
~
Reduce number ofunion grievances not handled within 10 days.
Include indicator for review.
Tracking Implemented Process On-gong 68
ANNUALIZEDVOLUNTARYEXTERNALTURNOVER ST. LUCIE PLANT Lynn Morgan - Human Resources V)
CL 0)
C c5Q th Cl 0
Q E
Lll 0
~O 0
0 of people Leaving 10 9-8
~
7 6
5-4 3-2-
Mar 3.88 Apr 3:42 May June July Aug Date 3
Sept Oct X28 291 2 78 2.69 2.-57 2.46 Nov Dec Jan-96 Feb DEFINITION: Turnover - the total number of people leaving site. (direct reports to Site VP)
Percentage calculated by number of people leaving site over the total number of FPL, St. Lucle, employees on site.
ST LUCIE PLANT Total Employees Lynn Morgan - Human Resources 830 826 827
.83 820.
810 A
Ez 800 0~
790.
Targat 1995 828 811 802 780.
770 Targat 1998 Tro 760
~
Sept Oct Nov Dec Jan Feb Mar Apr May June July Aug Sept Oct Nov Dec
'95
'96
~Employeee Target
ufGrievances >10 Da s
30 Overdue Grievances - Total 28
'i6 By Department 26 25 14 14 20 20 12 10 10 2/19/96 2/26/96 2/28/96 Date 3/8/96 OPS MM lSC TRN8.
Data submitted by C.D. Scott/HR