ML20236W118

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Refers to Public Meeting Conducted in Region IV Office on 980723 Held at Licensee Request.Discussion Focused on Performance During First 11 Months of SALP Insp Cycle,Which Began on 970803.List of Attendees & Presentation,Encl
ML20236W118
Person / Time
Site: Callaway 
Issue date: 07/30/1998
From: Gwynn T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Gambhir S
OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 9808050090
Download: ML20236W118 (62)
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Text

{{#Wiki_filter:mc, [e o UNITED STATES 1 y et NUCLEAR REGULATORY COMMISSION { j REGION IV O..'t., ,6,4 611 AVAN PLAZA DAlVE SUITE 400 ARLINGTON TEXAS 76011-8064 JUL 3 0 1998 S. K. Gambhir, Division Manager Engineering & Operations Support Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. P.O. Box 399 Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399

SUBJECT:

DISCUSSION OF LICENSEE PERFORMANCE

Dear Mr. Gambhir:

This refers to the public meeting conducted in the Region IV office on July 23,1998. This meeting was held at the licersee's request to discuss their performance at the Fort Calhoun Station. The discussion focused on performance during the first 11 months of the Systematic Assessment of Licensee Performance inspection cycle, which began on August 3,1997, and is scheduled to continue through January 30,1999. This was a very useful meeting because of the interactive discussions of Fort Calhoun's performance in the various functional areas. Strengths and areas of potential improvement were + discussed at length. A list of attendees and a copy of your presentation slides are enclosed. In accordance with Section 2.790 of the NRC's " Rules of Practice." Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room. Should you have any questions concerning this matter, we will be pleased to discuss them with you. Sin el 4. -/ \\ (' O j l Thomas P. Gwynn, 'irect j Division of Reactor s { Docket No.: 50-483 License No.: NPF-30 i l

Enclosures:

1. Attendance List

)

2. Licensee Presentation i

9808050090 980730 l PDR ADOCK 05000483 PDR G J

Omaha Public Power District cc: James W. Tills, Manager Nuclear Licensing Omaha c)ublic Power District Fort Calhoun Station FC-2-4 Adm. P.O. Box 399 Hwy. 75 - North of Cort Calhoun Fort Calhoun, Nebraska 68023-0399 James W. Chase, Manager Fort Calhoun Station P.O. Box 399 Fort Calhoun, Nebraska 68023 Perry D. Robinson, Esq. Winston & Strawn 1400 L. Street, N.W. Washington, D.C. 20005-3502 Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Cheryl Rogers, LLRW Program Manager Environmental Protection Section Nebraska Department of Health 301 Centennial Mall, South P.O. Box 95037 Lincoln, Nebraska 68509-5007 h l u

Omaha Public Power District l JUL 3 0E bec to DCD (IE45) bc0 distrib. by RIV: l Regional Administrator DRS-PSB DRP Director MIS System Branch Chief (DRP/B) RIV File i Project Engineer (DRP/B) Branch Chief (DRP/TSS) Resident inspector i i \\ ) DOCUMENT NAME: R:\\_FCS\\FC0723MS.DRP To receive copy of dgetgrnent, indicate in 5 "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:PE:DRP/BQ/ C:DRP/( J D:DRP Mf RVAzua:lat // F WDJohn%n TPGwynn ( 07M98 07/ft98 07E 98 07/ /98 07/ /98 OFFICIAL RECORD COPY \\ 1 L"sCUL5 L

J

Omaha Public Power District JUL 3 0M bec to DCD (IE45) bec distnb. by RIV: Regional Administrator DRS-PSB DRP Director MIS System Branch Chief (DRP/B) RIV File Project Engineer (DRP/B) Branch Chief (DRP/TSS) Resident inspector DOCUMENT NAME: R:\\_FCS\\FC0723MS.DRP To receive copy of dgetynent, indicate in bpm "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV.PE:DRP/BQ / C:DRP/( f D:DRP l Mf l l RVAzua:lat // f' WDJohnp6n TPGwynn ( / 07A498 07/J998 07ff98 07/ /98 07/ /98 OFFICIAi. RECORD COPY

h ENCLOSURE 1 ATTENDANCE LIST

MEETING: PUBLIC

SUBJECT:

FORT CALHOUN DISCUSSION OF PERFORMANCE DATE: JULY 23, 1998 ATTENDANCE LIST NAME ORGANIZATION POSITION TITLE %tt L $ocie. US AJAC & 2eactor Inwector ~uu.D. J M o-um An.2 1ssasm a ~T.7 duvs Akc - at bi"w I.e.Dwc Ac-42 D,J., i.; 1 Aill A. T. No' we// Niec-riv 15c.',%Rs n w-d p.swea a c - ad

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w~ G ENCLOSURE 2 LICENSEE PRESENTATION 4

I NRC PRESENTATION FORT CALHOUN STATION MID-SALP ) g

8.'

9 1 ! eene D M., g '[l !*f:$i5&k' fg.ph L Qhg. July 23,1998 Arlington, Texas i Omana Pubhc Power Distnct l

j

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".andL W $ f L M ' c ~ .nl [ I e-G 3 4-O l 4 j Ae Omaha Pubh. Power District a-c [ { 5; 2 Fort Calhoun Station l 2.~ NRC Meeting to Discuss the l -Q 9 s a-Mid-Cycle SALP p -y. f4- ) O w. ] b m h2 A= l c-a g .y...w.-------=-- r.__ 1 \\ l l l t l )

'a g ,C. 2* Agenda i t l _.

  • Openmg & Agenda Review Gary Gates

- ~

  • Six Factor Formula - Sudesh Gambhir
*
  • Operations Dave Bannister
_.
  • Engmeering - Ralph Phelps

? .~. c. e i m t.: Agenda i l ~ ~

  • t

-- ; Maintenance - Rich Clemens s 7, + Plant Support RP/EP - Steve Gebers - Secunty - Jim Tills l i ~ I

  • Quality Organizations - Dave Spires

... ~. s i .. ~.* i c-l t '. Agenda ~ ~. .~. ~. 2: !

  • Station Manager Perspective - Joseph Solymossy i

.... Final Questions / Comments =_. b 2. Closing - Gary Gates f 1 J 49* d ~ l l 1 l l l 1 l l l l i

l l i I m, -. t m l I ~. ~.:- : Critical Success Factors 1 1 .~ s, 1 I Sudesh Gambhir ~. t c t 1 l c. t* Critical Success Factors 1 .~. i !

  • Vision

- Safe, reliable and efficient operanon I. I ,.-.

  • Strategy

? - Strorig operanonal safety focus through back to basics I \\ I i g. i Six Factor Formula l ~. [ _~. i 2' *

  • Event Free Station Operation

{ l i l

;
  • Excellent Plant Material Condition

[ ~; ; - Discussed by Ralph Phelps i i !

  • Exemplary Human Performance f

~ l 2 I 1 '0

I 1 s: i l 5: Six Factor Formula i Cntical Self Assessments .~ - Discussed by Dave Spires ] C !

  • Broad & Lasting Corrective Actions j

C.' - To be discussed by individual presenten ~.. 1 -

  • High Visibility Issues i

i

4. -.

t 2: Operational Safety Focus ~ O *

  • Event Free Operations

.~a. _--o , ; Excellent Matenal Exemplary Hurnan Con & tion Performance j [* = Event Free Opersoon j \\ 1 ..eC*: Human Performance l i ~. f t -.

  • Focus on Key Behaviors I

I - The orgamzanon fosten a culture that values ! g the prevenuon of events f. [! - Leaden promote teamwork to cluninate error [ ~ *. likely situations - Individual behavion of personnel anticipaung. e ( )

j error.hkely situanons t.

l. t s. I e L 4 + l l 9t

I 1 f. n E: High Visibility Issues ~ ~ [ -~. 1998 RFO _ ! Year 2000 Implementation

*
  • Maintenance of Design Basis Configuration

- Control

  • Severe Accident Management 5

~~~ Operations Trainmg Accreditation Program I t 1 i I t l High Visibility Issues t ~~ ~ _ ~. _ ~..

  • Maintenance Rule implementation l

L I Emergency Planning

  • Deregulation Work Process Control

- Effecove use of resources a. 5: 1998 Refueling Outage Results i ~ r ~.. _~. Nuclear Safety ~. l 2 ', * - Emphasis on safety vs. schedule l O* - No loss of contamment integnty - No safety system challenges 2. - No events or power reducnons due to C~

  • equipment problems

~! - No missed surveillance e 3 l 4

l _ } 1998 Refueling Outage Results .. s Radiological Safety - Met 1998 RFO goals ~ r Industnal Safety ~ - No lost.ume accidents t l _ i Operations _ f Dave Bannister i c l y l l l j i Assessment of Area L as ~ 1

  • Overall Conduct of Operations Has Been

" Professional and Safety Conscious.. " - I M 6 e aM sw-e .em i 5 i i i

Assessment of Area We Are Deficient m Some Areas: - Events

  • ContammeniSpray Event (897)
  • Reactor Coolant Pump Cavinnon Event (4.98)

- Human performance = Valve misposianneg-uggmg errors l - Procedure quahty mconsistent - Operator traming i i 1 t Areas of Strong Performance r s l l .' I = Recent Outage Conducted With No Safety System. Challenges or Reactmty Control Events sensinvity to Reacuvity Controllssues ~~ - Emergency borauon dunng the outage 1

  • Knowledgeable Skilled Operators l

- Average ter.w w,th OPPD is 10 years l f Areas of Strong Performance Excellent Response to Plant Transients'off-normal s Occurrences - TI Al transformer inadvertent deluge and subsequent t.oss of Off-site Power - Entenng mto the 1998 RFO, meal Conumnwat Purge with high anfbome actmtv ~ - Excellent response to a fire alarm m Conumment ~ * - Operator Knowledge of the Maintenance Rule e 6 s

.. - +. - i Comprehensive Corrective Actions . {

  • Measurable, Lasting Improvements Since the Containment Spray Event:

- Adopted a "Back to the Basics" philosophy with the pnmary focus on conunually T improving and evaluatmg our fundamental operational skills

  • These skills re emphasi. red m traimng and in the plant

- Formahty improvements - ~. Comprehensive CorTective '1 Actions - ShiA Tumover revised and improved ~.'

  • Noted as a strength

- Simulator Training improved. more emphasis ~~. 2 on"on the-spot" corrections !.* - Strengthen Shift Manager / Licensed Senior i operator role in re-emphastring standards

- t

- significant adjustment to the 12 hour sluft schedule ~ a Mmimizes challenges when returning to rhift ,5 Comprehensive Corrective 2 ~.. ; Actions .+ - Focusing on remainmg " Event Free" using all . --{ of our operator " Tools" ~ ' - The chanses msututed after the Contamment l ? Spray event are produemg measurable improvements m Operator performance ~

  • Reduchon m the number of sigmficant condtbon reporu

\\ 1 7 1 L..

Operations Challenges - Contmued Focus and Emphasis on Remaining " Event Free" Upgrade Procedure Quality - Trocedure quahty a contnbutor to some events Human Performance Programmatic issues in Operator Training Summary , ; Maintaining Steady improvements Utilizing , the "Back to Basics" Philosophy and Our Operator " Tools" + ~I ~

  • Continued Focus on Being " Event Free" Meeting Human Performance Cha!!enges Head-on

~. ..,(( Engineering t 2 Ralph Phelps l t -. ~ m 4 f . ~.. 8 6 k

Engineering Area Assessment ,

  • Strengths

- self Assesmient Pracuces . Thorough, with cornprehensive correcuse accons - Programs and Configuranon Controls Successful outage Pnnects

  • Spong Knowledge of Design Basis
  • Effecove 10 CFR 50 59 prograrn

- Expenenced, stable Workforce ~ 2.}. Engineering Area Assessment ~ {

  • Challenges

- Effective management of plant agmg issues

  • Achwve excellent matenal condaban s

T- - Human performance issues . Maintain high espectauons for accuracy and knowledge l l -...~ Recent Self Assessments I . Maintenance Rule Program = { Preventive Maintenance Program , :

  • Set points Containment Coatings Program (Tab No.1) l Fire Protection Program

.t > + '.

  • Flow Accelerated Corrosion Program l

i ~ 9 i i

e Comprehensive Corrective Actions

*
  • Fire Protection (Tab No 2)

~_ - Extensive analysis completed - Oil collecuon system installed

  • Flow Accelerated Corrosion Program

- Models revenfied and updated - Extracuon pipmg replaced Plant Aging Program J' _'., Tab No. 3 . !

  • Fundamental Programs

- Reactor s essel embnttlement extended past end of heense h_ - Steam Generators m excellent health, more informanon on what was done 1 4 i lt J l 2 .{ Plant Aging Program c: .,

  • Specific Equipment issues and Upgrades

- Rehabihty and availabihty goals under Mamtenance Rule l , - Electncal breakers, radianon monitors, fire detectors replaced

  • Condition Monitoring

- Presentne and Predictive Mamtenance are bemg implemented l l 10 o

O i l L l Plant Aging Program ~! [ - :

  • Safety l

- Reduce chaltenges to Operators -

  • Reliability

- Excellent matenal condinon

  • License extension 4.:
.
  • Sustained Strong Performance
  • Problem identification

- Deluge valve, pump cavnanon, turbme over speed ., f

  • Configuration Control & Design Basis
*. Maintenance

- USAR revenficanon - 10 CFR 50.59 Program

9. : Sustained Strong Performance s
  • System Engmeering

- Leadership role in system ownership - Pre-job bnefings Failure analysis ... ~

7. I a Program Management

, { - Successful SG mspecoon 2 - Effecove outage programs (MOVs. check <alves) l 1 ( i j 11

Challenges

'
  • Achieve Excellen Material Condition
  • Address Plant Aging
  • Improve Human Performance 4'f'

~ ' '.... _ _ _..

} 5 Summary

-, ;

  • Focus on Safety

- Conunue comprehensive self assessments - Broad correcuve acDons are being completed

. 1 - No events
- :
  • Improve Plant Matenal Condition

~ - Concoue aging management programs ~ - Responsive support to Operations and CI Maintenance . ~ l i j Summary . ~.. . -

  • Mamtain High Techmcal Competence

~ : - Maintain strengths and correct weaknesses - Anteipate and resolve challenges

*
  • Maintain an Intrusive Engineenng

- ; Organization '4 e* 4 es e.m e, e. g emee ..emse 12 } e L

'I r-- b {' Maintenance Rich Clemens ~ Assessment of Area l

  • Lack of Attention-to-Detail

--. ~ ~ - ; Increased attention needed on Plant 0 Matenal Condition

1 Strong, Knowledgeable, Skilled and

- - + Expenenced Work Force ~' Cntical Departmental Self-Assessments - + l .j Areas of Strong Performance -- {

  • Strong Maintenance Performance Dunng

'98 RFO 1 -Improved pre-job bnerings [.' - Overall human performance improvements .~.. ; - Equipment performance & matenal condition at start up

} l

- Industnal safety performance s 13

1 l l l 1 l Areas of Strong Performance

*
  • Strong Mamtenance Performance Dunng

'98 RFO - Control Room Deficiencies ~ = Breakm opened. 27

  • Breakm closed 4

~ - operator Work Arounds

  • Breakm opened. 21
  • Breakm closed.8 1

Areas of Strong Performance I {

  • Ongoing Self-Assessments

{

  • TrainingImprovements

- Implementanon of qualification manuals ., ? - Supervisory involvement in curriculum advisory teams I

  • Configuration ControlImprovements i

.i Areas of Strong Performance ~

  • Equipment improvements

?. I - Diesel Dnven Auxiliary Feedwater Punip (FW-54) - Condenser and CW ~ - Extraction steam pipmg and Feedwater heater rent imes replacements 14 I ) s

n n. ..n n ~~. ~~ Challenges

  • ;
  • Contmuing improvements m Human Performance Age of FCS Represents Matenal Condition
Challenge

- Increased emphasis on PM efforts - FAC/SGs/ Condensers /CCW Piping Coanngs Challenges ) 1 I

  • Backlog Reduction (On-Line Corrective)

- Post-1996 RFO > 470 - Pre-1998 RFO < 210 - Current - 403 ~. )

-
  • Planning & Scheduling improvements

- Correctis e maintenance backlog post 4utage - Source term dictates planning improvements i l i

  • 'e l

=j Summary j 5 s i .,. ;

  • On-gomg Cntical Self Assessments and Corrective Actions
;
  • Operational Safety Focus i

, !

  • Continued improvements in Human j

f.' Performance ~ Improve Plant Material Condition - Backlog reduction - PM Program improvements l i 15 i

l l 4 9 Plant Support '~ RP/EP - Steve Gebers s Secunty JimTills .~ t t l 1 ~ 1 . +- I b l Radiation Protection l _~ l .~., Steve Gebers, CHP ~~ ~ 1 1 i \\> lL i Assessment of Area s .. One Annual Program Self Assessment j completed during this SALP period - Anotheris Planned for September 1998 Six Program Element Self Assessments l ,; during this SALP period. Examples include: l - Contaminated Control ~I - ALARA Program ~~.' - General Employee Traimng Program 4 ee p== .ee.-en e. .-4 ,s4 I 16 \\ a \\ r I l. J

j Areas of Strong Performance
  • Decontammation of Auxiliary & Radwaste

- 95 2% of the buildings are contammanon free

  • Exposure Control Operations and RFO

~ ~ Extensive use of shielding (27 packages) - Locahzed source term control _ ~. ". - Radiation worker education { ~, - Detailed briefmgs - Management Support

j Areas of Strong Performance

. I

  • Critical Self Assessment Program

- Radianon Protecton has been performmg self assessments since 1990. Three Program Assessments C -

  • Excellent (Radiological /ALARA) Job Planning

- Reduced Steam Generator collecuve dose by 2 50% despite a 30% increase in source term and

  • {

expanded work scope ~ WMw N +hm. reed

  • WW*'+-eee

^~.j Areas of Strong Performance 7,,

  • Highly Qualified Staff

- 27 of the RP Techmeians are NRRPT (89%), more than 40 on rCS staff - 1 GIP (Radianon Protecton),5 total on FCS C staff _. I

  • Excellent Radioactive Material Control

- No release of radioacuve matenal above Mmimum Detectable Activity (MDA) . + \\ i 17 e_________-_----_-___-_

-e - l Challenges Decime in Radiation Worker Performance - RWP violacons - Failure to follow postmg requirements

  • J Timely and appropriate update of
  • radiological documentation

~ Continued High Source Term t . l .b Emergency Planning

^ :

Steve Gebers, CHP m i!- <t o 7: Assessment of Area ~! {

  • One Quahty Assurance Audit utilizing four

-- ; industry peers - included observation of a training dnll ) ~ i,',

  • Emergent Dose Assessment Surveillance

^~.' ! - Management requested based on poor I performance dunng an unannounced drill l T. : - +

  • Quanerly Drills 18

Areas of Strong Performance Mamtaining a High Level of Emergency { } Response Facility and Equipment Readtness ',. Excellent Working Relationship with _.. Offsite Officials (States and Counnes) L'".'. Weekly Simulator Dnll with Operations 2: Crews '1 - Recognized as an indur y strength by both 1! NRC and INPO

- : Comprehensive Corrective Actions

.. s .~ 2 . Maintaining Emergency Response .'. I Organization Proficiency [ [. Started monthly drills, based on quarterly

f. I drill performance
7.,'

- Use ofthe Systematic Approach to Trainmg 3: (SAT) for key positions _^ ! Facility Communications 1 '- Review industry procedures on rapid } { deploymentofrepairteams C.

  • Summary L*

Radiation Protection Emergency Preparedness - !

  • Usmg SAT to target
  • Increased drill Radworker Trammg frequency J -

.

  • Standardize

. Usmg S AT to target .7, Radiological Postmg ERO Trainmg -l ! = CnticalSelf . Weekly Simulator

' Assessment Program drills j

. ;- Highly Quahfied Well maintamed ,, ; Personnel emergency facihties .. ~ .w ..g.- a .s. 19 l k_______.___________

( = I t l 1 l s l '- I _ } Security ~ Jim Tills s ~. - tl Assessment of Area Strengths - Testmg & mamtenance of secunty equipment - Secunty event reports program ! - Vital area bamers & assessment aids , ~. - Compensatory measures program - Secunty tratnmg program - Fitness for duty - Secunty personnel amtudes & expertzse - Audits & self assessments r. E: Assessment of Area .. s . -. Weaknesses ~. ! - Access Authorization 7.' + Handimg of derogatory information ,, [

  • Informahrv of adjudication process m

W w b .an W 20

a Comprehensive Corrective Actions

  • Security & QA Audits

- I - August 1996, January 1997, August 1997 and November 1997 } ;

  • Improvements to Access Authorization

- Incorporated industry best practices e - Orgamzational changes

  • July 1998 QA Results

~ - 45 files reviewed (8-97 to present). No l problems ideaufied following implementation of correenve aenons Sustaining and Improving

[

Perfonnance

;
  • Enhanced Measurements of Human

' Performance - Tracking of non-loggable events ~ ~ ~ - Development of Access Authonzation indicators - Improv ed logging and trending of human performance errors

  • Improved Surveillance Process

- Scorecards for performance based observanons

^ 2

- Expanded comphance based reviews & audits ! 2; i Sustaining and Improving c; Performance

  • Benchmarking Activities l

- Technical assist visits - Observanon of 0SRE at other sites - Industry meenng involvement

  • Other Changes

~ 1 - Shift change bnefings i 1 - Additional Shift Secunty Supervisor l. ~ ' - Expanded use of CR system - Vehicle barner, bomb blast analyses revahdated 21

Challenges ',

  • Continued Improvements to Access Authorizapon

- Procedural clanfications - Developing desk-top mstruccons 7 - Other process changes .. Human Performance Improvement - Operanonal field trammg officer program - CAS/SAS training & OJT program h{ Challenges

-- ;
  • Revalidation of the Response Doctrine

- Benchmark OSRE - Revisit weapons nux and defensive positions .~ as ~* bl Summary ,

  • Str ngths Have Been Maintained L 2 Marked improvements m Access

.' ! Authorization '; I r !

  • Enhancernents to Monitoring Process

.: [

  • Continued Challenges for the Future L

22

e ?- Quality Organizations Dave Spires .~ r+ ? ;> Assessments

  • Two Fundamental Weaknesses Identified:

- Unclear management ovenight and expectauons + ..~~ I Clearly dehneated espectanons [. Audit and assessment performance espectauons l .~ 1 - Need for more enocal assessments , i ? L 5: Assessments: Critical i Assessments and Audits

  • Assessment and Audits Lack Depth j.

! '.

  • lategrated Assessment Schedule l
. ;
  • Department Depth Enhanced j

, *

  • Audit Guidelines Developed l

l

  • Trainmg k

e 4 4 e 23 i m __ ___ __ _ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _. - - - _ _ _ _

Strong Performance I

*
  • Management Expectations Clearly Delmeated and Enforced
  • Self-assessments, Evaluations and Audits

- More Critical

i. _ _.

Strong Performance: %i Audits . ~ ~

;
  • Cntical Audits

.. ~ .. 2 - Operator Training - Operanons T. { - Nuclear Fuels ~ t: Strong Performance: 7 Self-assessments - *

  • Line Seif.n.cssments Considered to Be

{~ Cntical [.,,. - 30 program review" [' - Pneurement self-assessment - Maintenance Rule self. assessment l P. - Scorecard concept for specific tasks l

  • ~

- Focus Manager concept for entical activines 7 ... ~. i 24 i

e 4 Challenges -t ~

  • Sustained Cntical Assessments and Audits
  • Contmued Broad, Lastmg and Prompt Correenve Actions 1~:

5 i Challenges: Sustained Critical 1i Assessments

  • Use of Technical Experts and Personnel Rotation Program Vital to Maintaining a Cntical Depth of Review I

~ '

  • Use of Our Trainmg Program to Enhance the Auditor's Knowledge l

6 i Challenges: Broad, Lasting and

i Prompt Corrective Actions

~ ~

  • Management Attention to This Facet of the Six Factor Formula-

- Improvmg trend m open condition reports . 2 - Improvmg trend m duration of open condition reports - Improvmg trend m repetmvc condition repons ( 25

i i Station Manager Perspective l Joseph Solyrnossy i l I }

  • An Operational Focus

-- '

  • Excellent Materia 1 Condition

~ = A Learning Organization ^ Final NRC Questions / Comments dr 9 e b o e r i 1 1 '( i )

,w------ e,, -6 w 1e r: Closing W Gary Gates = I e e e O O" ,e ,.,,. = = = * * * * *

  • 1

~7 ) m--_ _-__m.--__.__m_. _ - - - m_-_-

CONTAINMENT COATINGS ACTIONS TO DATE: Procedure SE-PM-AE-1000, " Containment Protective Coatings inspection" conducted o during the 1998 Refueling Outage. Included visual inspection of coatings by a qualified Nuclear Coatings inspector and ultrasonic (UTj testing of CCW pipe wall thickness. The inspector commented that FCS Containment coatings are generally in above average condition for the vintage of plant. Found no pipe wall degradation below code allowables. Removed indeterminate coating material that had been applied over portions of the CCW piping and was flaking / peeling off. Formulated plans for Containment coatings work during the 1999 Refueling Outage. ACTIONS IN PLANNING FOR 99 RFO: Prepare surface and coat with nuclear qualified materials, CCW piping and valves in Containment that were scraped and pre-prepped during the 98 RFO. Estimate 700 to 1000 linear feet of 2" to 10" diameter piping. Prepare surface and coat with nuclear qualified materials, the remainder of CCW piping inside and outside of Containment Cooling & Filtering Units VA-15A and VA-158. Prepare surface and coat with nuclear qualified materials, Containment liner plate from el. 1045' to el.1055', Columns 3 to 6, and Columns 8 to 12. Prepare surface and coat with nuclear qualified materials, readily-accessible areas of failed coating on Containment liner plate at various locations on walls and dome. Prepare surface and coat with nuclear qualified materials, concrete surfaces (walls, columns, & beams) inside the steam generator bays to cover graffiti. Replace specific CCW piping in the Steam Generator bays (basement el. 994') and Reactor Coolant Pump Bays (el.1013'). Piping replacement selected versus re-coating due to economic and ALARA considerations. i LONG TE8M ACTIONS: Develop a nuclear coatings program basis document that delineates program purpose, scope, qualifications, and responsibilities (CR 199700968, Action item 2). Review and revise existing protective coating procedures to incorporate comments of e nuclear coatings consultant and acceptance criteria for coating inspections (CR 199700968, Action item 4). Use procedure SE-PM-AE-1000 inspection results each outage to establish scope of e Containment coatings activities for the following outage (CR 199700968, Action item 5). NOTE: Newly issued EPRI Document TR-109937, Guideline on Nuclear Safety-Related Coatings, will be used as a guide / reference during many of the above activities. j \\ MWPFILES\\ COATINGS \\CONTCTGs WPD J

Fire Protection Ongoing Action Plan Engineering & Operations Support Plan Goals: To provide assurance through Defense-in Depth of Fire Safe Shutdown and contribute to a SALP 1 Rating for Plant Support. The Plan was developed to address issues from selfidentified findings and inspections. Actions To Date: OPPD has completed major corrective actions related to past violations which include: Modification completed for diesel tachometer isolation AOP-6 Fire Emergency procedure reviseo to include Control Room evacuation criteria A Fire Protection Program Self Assessment completed i Completed installation of collection system on GE motor ports & drains. Completed installation of collection system for potential leakage sites from unpressurized lube oil system. { In receipt of NRC SER exempting the installation of collection systems for specific sites 1 on RCP motors shown not to be potential leakage sites. I FP Procedures were revised to station a Dedicated Operator when the Fire Pumps are in Pull-to-Lock. Additional Corrective Actions: I Completed QA Audit Fire Protection FunctionalInspection. Installed a sparger on FP-1B Fire Pump to improve reliability FP Self Assessment: The OPPD conducted a Fire Protection Program Self Assessment which focused primarily on the Appendix R ponion of the FP Program The assessment was completed in June 1997 and based on NRC Inspection modules. The assessment identified issues to be re-evaluated based on today's industry expectations, current NRC scrutiny and interpretation of requirements. The fmdings were divided into three categories to prioritize the issues and are potential concerns, general concerns and general observations. The Self Assessment report was provided to the NRC with a scheduled completion date of December 31,1998. Positive Results: Centralized FP Document Records l Excellent housekeeping Management Involvement 3 Frequently updated Fire Hazards Analysis i Corrective Actions Completed:

7 i i Several corrective actions have been completed including the following major accomplishments: o ( Review of Fuse Pulling and Emergency lighting for III.G.3 areas (Alternate Safe a Shutdown Procedure AOP-6) Associated Circuits Analysis update (added 155 cables to cable worksheet analysis). Hi/Lo interface valves HCV-347/348 breakers opened in Modes I and 2. l Safe Shutdown Analysis documentation deficiencies corrected. l Structural Steel protection l AOP-6 Alternate shutdown basis document developed l Revised Combustible Control Program for Cable Spreading Room Revised GEI-4 Instruction for improved breaker / fuse coordination review during modifications impacting Appendix R. RW Strainer, Intake Screens and Sampling line operation incorporated into the Functional Requirements Analysis QA FPFI: OPPD conducted a Quality Assurance Fire Protection Functional Inspection which focused on the NRC FPFI Inspection Module and FP areas not included in the Self Assessment. The QA Audit was completed in November 1997 and the areas reviewed included: Fire Protection Systerns a Transient / Combustible Loading Hot Work procedures Surveillance testing Response activities Positive Results: FP Program is propedy implemented in accordance with commitments. Communication within program is open and positive Corrective Actions Completed: Fire Damper Labeling & Documentation Upgraded Combustible Loading Calculation Revised Completed upgrade of calculation demonstrating adequate hose coverage. Updated FHA to describe Containment fire hose staging. Upgraded Hose Station Hydraulic calculation. 1998 NRC FP Follow-up Inspection: The purpose of the Inspection was to review corrective actions for previously identified items in fire protection. { f s

Positive Results: No violations of NRC requirements were identified. Self Assessments & Audits were effective in providing a critical evaluation of the FP Program. Efforts in FP improved since the previous inspection. One weakness identified: Reliance on cable qualification fire tests weakly supports 10 minute response for a cable spreading room fire. Corrective Actions: Completed App. R Transient Analysis. Initiated Modification to address IN 92-18 "MOV Hot Shorts" w/o crediting flame tests by 99 RFO. Initiated Independent Verification of Appendix R Analysis. Initiate Modification for remote position indication for HCV-347/348. Committed to I hr Fire Watch of CSR until 99 RFO mod completed. Revised procedure for limiting transient combustibles in CSR. Schedule: NRC Commitments: Complete Self Assessment Corrective Actions by 12/31/98 Self Assessment Corrective Actions on track except one item:. NFPA Code Compliance Evaluation has larger scope than anticipated. Complete IN 92-18 Hot Short Mods by 1999 RFO Major Actions in Progress: The major action in progress are the higher priority selfidentified findings from the Self Assessment, Q.A FPFI and inspection findings. Review ofIII.G.2 (Non Control Room Evacuation) Safe Shutdown Actions. Review of plant automatic functions for safe shutdown. Pressurizer Spray Spurious operation. 7alidation & Documentation Upgrade of Penetration Program. Updating Breaker / Fuse Coordination Study. These actions encompass the Self Assessment Findings 1 Engineer attended NFPA/ Appendix R Training and 2 others scheduled for August. i Summary: The current FCS Fire Protection Program assures Fire Safe Shutdown and corrective actions will f elevate the FP Program to contribute to a SALP 1 Rating. { J l

Revised 7/17/98 Plant Material Condition and Aging hjanagement Prograans at Fort Calhoun Station Pumose Provide an integrated compilation of the programs and activities that contribute to managing plant aging issues at FCS. These same programs support maintaining FCS in excellent material condition. Obiective To summarize the activities that are in progress at FCS that directly or indirectly measure and mitigate the changes to plant equipment or performance that result from the affects of aging. l Through these activities, we can help maintain safe and reliable operation and preserve the Life i Extension option. Method Current ongoing programs are described for their applicability to manage aging effects. These 1 programs are also assessed for their effectiveness and any particular strengths or weaknesses identified. j l An essential element of any aging related program is continuous incorporation ofindustry experience and new research results. It is our intent to review and update the study after each refueling outage to ensure actions completed are incorporated and to re-assess the affectivity of programs from an integrated aging perspective. Where applicable, programs incorporate information from EPRI documents, INPO PM guides and operating experience reports. Basis The programs are general and specific and approach aging management from an analysis and/or a monitoring standpoint. For example, the thermography or vibration monitoring programs measure the current condition of equipment and trigger a reaction, or MWO, to negative trends. These are monitoring approaches. - The reactor vessel management program relies heavily on analysis to find ways to minimize I vessel material embrittlement. i Some programs are heavy in both areas such as the SG Management Program (SGMP) and the Erosion-Corrosion program. Others are more generic in nature, and are intended to ensure that consideration of aging effects is incorporated into plant improvements. These include the modification process and Maintenance Rule implementation.

Details A listing of the programs encompassed by the Plant Aging Program Basis Document (PBD) is enclosed. . A. There are many ways to measure and maintain reliable plant operation, and as a plant ages, more attention must be given to identifying and predicting mechanisms that can affect material condition. For purpose of discussion, the world of plant reliability at Fort Calhoun Station (FCS) can be characterized into three broad categories: 1. Fundamental or Maior Programs These are generally large equipment, long range management plans, designed to anticipate aging effects. These may have low visibility, but form the essential foundation for continued successful operation. They tend to be generic concerns across the industry. Example: Steam Generator Management Program 2. Specific Equioment Issues and Replacement / Upgrade Programs These are generally activities performed to mitigate aging effects and to enhance normal operating reliability and are readily monitored using the Maintenance Rule process. Example: FW-54 Availability (Diesel AFW Pump) 3. Eauipment Condition Monitoring supoorted by Preventive and Predictive Maintenance Programs Provide the activities which address ag,i g and anticipate reliability issues. n FCS has taken aggressive action in each of these categories, and continues to upgrade our l programs and respond to challenges. B. Fundamental or Maior Programs If managed well, these rarely become crisis activities, seldom get a lot of Regional Inspector attention, yet 'nevertheless require ongoing dedication of resources, both - manpower and professional services. Problems with this equipment, if allowed to develop, could have severe consequences to continued operation. OPPD has consistently l-made sufficient resources available and such activities make up a significant part of our l resource loaded business plan. In addition these programs frequently require participation in activities with the CE Owners Group (CEOG) and EPRI. l l 0 L______.______.__________________._

_ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ - _ - - _ - _ _ = -._ i This maintenance of fundamental material condition has also shown us over the years that FCS is a very " robust" designed plant; that is, we have benefited in many cases from ruggedness of equipment and good design; this contributes to safe management and control of aging mechanisms. Example: RCP Cavitation, FW10 Overspeed, Seismic Analyses (SQUG) The following discussion provides a representative overview of the activities we have recently accomplished at FCS: Regarding the NSSS, refer to the following sketch. The (P) designatorrefers to an on-going program. 3:S r G -} ' 9 2,tB,9 I Q N 7 1. Leaking Westinghouse fuel a. Intense redesign effort I b. Substituted burned CE fuel for leakers I Result: All vibration susceptible fuel bundles were removed for Cycle 18. 2. In-core detector failures a. RCA revealed manufacture defect Result: Currently installed replacement in-cores are performing well. 3. CEDM shroud weld cracking a. Not a FCS design issue t o JL

4. RV Embrittlement (P) a. CEOG Tasks better define weld properties b. Extreme low leakage cores c. Revised analyses Result: FCS RV safe for current EOL with margin to about 2016. R.G.1.99 Rev 03 analysis will provide margin for possible license extension. 5. RV head penetration cracking (P) a. CEOG susceptibility study Result: FCS ICI nozzles are among the lower susceptibility and will not require an inspection for many years, if ever. 6. RCS nczzle cracks / Pressurizer heater sleeve cracks a. Inspections Okay Result: FCS has not had the need for complex and costly nozzle replacements. 7. RCP motor aging (P) a. CHAR Testing b. Rebuild data c. Spare Motor Result: One motor replaced. Rebuild showed condition to be very good with one spare now, future rebuilds will be on an as-needed basis. 8. RCP Pump aging (P) i a. Enhanced vibration monitoring l b. New seal parts I c. Spare rotating assembly Result: Have procured spare parts for rebuild. Condition monitoring will determine need. 9. Steam Generator Tube Inspections (P) a. Approximately 1% plugged b. Low T hot (593-4*F) Chemistry Control c d. Copper removal l Result: Best performing SG of CE fleet. Approximately 1% plugged. SG Management Program being implemented. 10. Core barrel baffle bolt cracks a. Different low stress design Result: FCS not susceptible to failures in Westinghouse Plants. I I

11. Thermal shield vibration a. Repaired l l Result: Degradation resolved. Regarding the BOP: 26,3 j / Mwe I l-D +J 33 I, & ,/ 1-o l 1. Condenser tube leaks l a. Backwash and inlet valve repairs b. Eddy current inspections - c. Tubesheet coating (1999) d. Intake tunnelleak repair e. Tube staking Result." Condenser reliability improved. Tubesheet coating scheduled for 1999 RFO. I 2. Stator cooler tube leak a. SS tube bundles Result: Reliability improved. More copper removed from feedwater. IL 3. MS drain piping stress Replaced with bellows a. Result: Restored to code requirements. l-t.

4. Condenser air in-leakage a. Installed accurate monitors Result: Better control of feedwater chemistry. 5. Turbine a. Replaced HP diaphragms Result: Improved thermal performance. URGE rating achieved. 6. Generator a. Re-wedge b. Partial discharge monitors Result: Preventive and predictive maintenance actions improve material condition. 7. Extraction steam piping replacements (P) Result: Improved material (stainless clad) resists corrosion. The bottom line is that for this category of material condition, many of which directly affect safety, OPPD has consistently stayed abreast ofindustry experience, done the analysis and implemented the programs to successfully address the issues. We also have anticipated future needs and are budgeting resources accordingly. C. The second category is directed more towards the visible, shorter term reliability and availability goals tracked with the Maintenance Rule. These issues often involve modifications or substitute replacement parts and are monitored by action plans. Some of FCS recent accomplishments in this category are: 1. 4160 Volt breaker replacements - procured and installed ABB breakers. 2. 480 Volt breaker refurbishment - refurbished GE KK series. Transient protection from changing susceptible RMS-9 units to Amptector style. 3. MCCB testing program - prioritized testing and replacement where necessary. No failures affecting safety functions have been identified. 4. Fire detection system upgrade - addressed reliability and obsolescence of old style detectors. 5. Radiation Monitor upgrade - new monitor installed for critical process applications. 6. FW 54 vibration reduction - soft monitoring of diesel engine completed in 1998 RFO. 7. RCP Lube oil heat exchanger replacements - Completed in 1996 RFO to resolve aging concem.

l 8. Raw Water Pump Improvement Program a. Spargers to reduce sand build-up - b. Improved flow instruments c. Hardened impeller material and increased size This multi-year program addresses both reliability (sand build up) and availability (more margin for ST and longer time between rebuilds) 9. Emergency D/G improvements a. Diode sizing for exciter circuit Resolved a design issue affecting reliability. l 10. Resolved long standing maintenance issues on HCV-347,348 and 2987 (SI System) These valves were refurbished during the 1998 RFO. I1. Charging pump improvement program This is an operational concern associated with positive displacement pumps. Availability improvements are being defined. 12. ' MOV Testing GL-89-10 work has resulted in improved reliability and safety. l FCS is continuing to make the Maintenance Rule a way oflife by integrating its use into the operating organization. A recent NRC inspection resulted in positive feedback on our progress. I The resources necessary to sustain performance criteria on these critical MR Systems can be focused and prioritized, and upgrades or Substitute Replacement Items can be prioritized to l support MWOs or modifications. We also currently utilize PRA insights for scheduling Maintenance through use of the Work Authorization Matrix (WAM). The MR performance criteria are supported by the PRA. t A performance based measure of material condition is our two most recent URGE Tests, where 1 we measure FCS electrical output against our optimum defined capability. In September,1997 we met our rating and in June,1998 we beat our rating by 1 Mwe, the best performance exhibited in the last 10 years. (476 Mwe in 1997 and 477 Mwe in 1998). 1 i D. The third category is the execution of the daily activities which directly influence material condition, aging and obsolescence-the preventive and predictive maintenance programs. The last INPO assessment concluded that there were weaknesses in the implementation of PMOs at FCS. FCS is currently implementing an extensive Preventive Maintenance j Improvement Program, which started in December,1997 and will be integrated into plant ~ operations by the end of 1998.

Taking as age of the recently formed Reliability Engineering Group with dedicated supervision, the PMIP is integrating a review of PM tasks on a system performance basis to ensure that the critical work is done in a timely fashion. In addition, the Reliability Engineering Group provides trending data from PMOs and MR failure analyses to System Engineers to maximize plant reliability. The PMIP has accomplished the following: 1. Issued PED-SEI-15 on a trial use basis to incorporate feedback prior to release. This describes the detailed process to verify PM content and adjust procedures and intervals. 2. Developed a computer based trending and reponing program for SE use which utilizes failure history, MWO history, work plans and equipment data. ] 3. Scheduled an Equipment Performance Assist Visit led by experts from INPO for week of 7/20/98. The PMIP is also expanding our Predictive Maintenance capabilities. Currently, w l monitor component vibration levels, take lube oil samples, perform thermography and do CHAR electrical testing for specified equipment. This data is trended on the local area network. The engineers for the PM Program have already visited several utilities to obtain data on new equipment and techniques to expand our capabilities. Several recent activities resulting from PMO reviews are: - Preventive Maintenance Non-CQE instrument and controller calibration interval extension project: 225 PMO's reviewed 41 PMO's extended. Some were changed to perform on-line. This directly helped lighten work during the 1998 RFO. - Preventive M_aintenance Electrical Breaker PM task extension project: 86 PMO's reviewed 36 PMO's were extended based on EPRI PM standards and equipment performance. Some were changed to perform on-line. - Maintenance Rule: New PMO's created to test 5 CQE MCC overload relays. Testing is scheduled during the next 2 years in accordance with the MCCB Testing Program. ) - Maintenance Rule: Functional testing of risk significant MCC's (Molded Case Breakers). j Approximately 165 new breakers were added to the PM program. This is an example of ongoing l programs to maintain excellent material condition.

- In response to a System Engineer request for refurbishment ofimportant steam traps, new PM l tasks were generated to perform periodic overhauls of trap internals. Additionally new PMO's j were also created for periodic blowdown of auxiliary steam system traps. ) - New PMO's were created to inspect the internals of critical Gas waste disposal system diaphragm valves. 1 I - System Engineer identified the potential for low voltage problems on the Diesel driven Feed I pump battery. PM task was createto perform periodic battery inspection. - Per System Engineer request, new PMO's were created to perform Thermography of safety I related battery charger cabinets. - Maintenance Rule: New PM tasks to inspect CCW valve operators were generated to address l performance problems. Existing ST stroke test did not detect intemal performance problems (diaphragm degradation). l -Initiated new PMO's to perform periodic inspection of Turbine EHC system relief valves. A failure anaylsis of one relief valve revealed excessive internal corrosion. E. In Summarv l 1. We are very aware of the challenges posed by aging equipment on overall plant reliability. 2. We are allocating resources to both major, long-term industry concerns and emergent equipment issues. 3. We are integrating the Maintenance Rule into our aging management and reliability goals. 4. Preventive and predictive maintenance is a critical part of plant support. 5. ~We are committed to program improvements through self assessments and use of industry operating experience. New challenges will always arise, and our goal is to foresee and prevent as many of these as possible. As described in the preceding discussion. FCS has already made significant progress in addressing and managing aging issues: the reactor vessel and intemals are analyzed for end of life, the steam generators are performing exceptionally, the RCPs and motors are sound, the l turbine has new high pressure disphrams, the generator is re-wedged, the condenser valves are overhauled, significant portions of the extraction steam lines are replaced, electrical breakers at all voltage levels have been overhauled or replaced, major instrumentation systems were upgraded such as fire detection, radiation monitors, and wide range excore detectors, with several more planned. We are getting a new switchyard, and we will be upgraded to be Year 2000 s

compliant. As always, new aging related challenges will emerge, especially in the area of smaller electrical equipment, and our programs are designed to mitigate these issues. D l i l l I l

PL' ANT AGING PROGRAM BASIS DOCUMENT Pumose Provide an integrated compilation of the programs and activities that contribute to managing plant aging issues at FCS. These same programs support maintaining FCS in excellent material condition. Obiective ( To summarize the activities that are in progress at FCS that directly or indirectly measure and j mitigate the changes to plant equipment or performance that result from the affects of aging. ) Through these activities, we can help maintain safe and reliable operation and preserve the Life l Extension option. Method Current ongoing programs are described for their applicability to manage aging effects. These l programs are also assessed for their effectiveness and any particular strengths or weaknesses identified. An essential elemem of any aging related program is continuous incorporation ofindustry experience and new research results. It is our intent to review and update the study after each refueling outage to ensure actions completed are incorporated and to re-assess the affectivity of programs from an integrated aging perspective. Where applicable, programs incorporate information from EPRI documents, INPO PM guides and operating experience reports. Basis The programs are general and specific and approach aging management from an analysis and/or a monitoring standpoint. For example, the thermography or vibration monitoring programs measure the current condition of equipment and trigger a reaction, or MWO, to negative trends. These are monitoring approaches. The reactor vessel management program relies heavily on analysis to find ways to minimize vessel material embrittlement. Some programs are heavy in both areas such as the SG Management Program (SGMP) and the Erosion-Corrosion program. Others are more generic in nature, and are intended to ensure that consideration of aging effects is incorporated into plant improvements. These include the modif'ication process and Maintenance Rule implementation. Details A listing of the programs encompassed by the Plant Aging Program Basis Document (PBD)is enclosed.

FORT CALHOUN AGING PROGRAMS i 1 POTENTIAL FOR DISCOVERING AND PLANT PROGRAM DESCRIPTION RESPONDING TO AGING Observation of ur. usual wear, corrosion, clearances, Preventive Maintenance - routine, periodic misalignment, etc. can point to aging mechanisms. maintenance regardless of equipment condition, Root cause of degradation could be aging mechanism. Modifications - maintenance on equipment that has failed or is not performing to requirements. l Check Valve Reliability - a combination of p'iedictive Valve condition monitoring detects the effects of aging and preventive maintenance practices to monitor and on performance or condition and can indicate that wear or erosion has occurred. test check valve performance to improve reliability. Design, performance, and monitoring data are used for I reliability and failure trending and establishing ] monitoring frequencies. i Detection of wall thinning or tube wall defects by l Eddy Current Testing - used for heat exchanger tube comparing with past readings to provide a trend of NDE. aging effects. Electronic Equipment Degradation - a combination of Diagnoses equipment condition makes comparison ) with baseline values to assess the change in investigation techniques to determine equipment conddons. condMon. Focuses tests for situations in which material Engineering Test Procedures - one-time procedures for trouble shooting, performance testing, and special degradation is a consideration; the results can directly or indirectly indicate an aging issue.

tests, Surveillance Test Procedures - performed at specific When test results indicate deviations or trends towards deficient conditions or performance,the root cause in intervals to satisfy technical specification requirements some instances may be effects of aging.

that specify tests, calibrations, or inspections. Environmental Qualification (EQ) - addresses electrical Evaluation of actual operating conditions relative to equipment that has been qualified for certain operating qualification basis can lead to extending or shortening environments. Determines if and when replacements replacementintervals. If actual conditions or projections for the future are less severe than needed based on these conditions, qualification basis, the potential exists for avoiding replacement of some cable altogether. Direct indication when an aging mechanism is known Erosion-Corrosion - systematic inspection for wall to affect equipment, such as with piping; a model of the thinning of pipe in high velocity fluid system piping; e.g., operating conditions and materials can lead to steam systems. predictions of the effects of aging. Control of plant and chemical additions to systems Chemistry - provides safe environment for operations minimizes wear and maximizes efficiency. and plant lay-up. Gives information from other plants that may be OER Program - review of industry information from indicative of future problems in aging effects. INPO Nuclear Network, NRC Generic Letters, Bulletins and information Notices and Vendor Technical l Notices. ~ 9

FORT CALHOUN AGING PROGRAMS 1 l PLANT PROGRAM DESCRIPTION POTENTIAL FOR DISCOVERING AND RESPONDING TO AGING Fatigue Monitoring - keeping account of plant Fatigue is an effect of aging. Knowing criticallocations transients and cycles to evaluate fatigue usage in within a system for fatigue, combined with a set of critical areas of the NSSS. projected transients, allows for monitoring transients in a few locations to account for fatigue of the system. In-Service inspection (ISI) - Inspections, usually inspection results can indicate trends in the effects of performed during outages, to meet requirements of aging, or that correction is necessary. f 10 CFR 50 and the ASME B&PV Code. Loose F6 Monitoring - on-line detection of abnormal Loose parts can be an effect of aging mechanisms. f noise in the reactor coolant system. Lube Oil analysis - samples from various equipment Metal filing can indicate wear in the equipment. I are periodically analyzed. Material Testing and Evaluation - conducted on special Can be used to analyze for the occurrence of various aging mechanisms. request. Motor Operated Valve Program - created in response Provides performance and condition information to to generic letter 89-10. Verifies design bases. support review of valves for effects of aging. Performance Evaluation Program - Routine Routine tests and inspections by operators detect operational checks of equipment during normal plant trends and changes in performance, which can be a symptom of aging. operation. Post-Maintenance Testing - tests on plant equipment When test results indicate maintenance is not effective, after maintenance and before retuming to service. the root cause in some instances may be effects of aging. Pressure Test Procedures - system hydrostatic and Ruptures or leaks can be symptoms of the effects of leak testing. Used when pressure boundaries are aging. repaired or when required by code. Protective Coating and Painting - visualinspection Preparation for re-coating and visualinspection have along with initial and subsequent application to protect the potential to reveal corrosion, spalling, etc. equipment and surfaces. ReactoI Pressure Vessel Management -integrated By its very nature, this program is focused on the program to keep track of the condition of the RPV, effects of aging. primarily for embrittlement. Steam Generator Management -integrated program to As with RPV management, the nature of this program is focused on the effects of aging, among other gain maximum performance and life from PWR steam degradation mechanisms. generators. Thermography -infrared scanning to locate hot spots Hot spots will degrade insulation more rapidly than exposure to the surrounding environment. in electrical equipment. Vibration Monitoring - monitors critical rotating Symptoms may be the result of the effects of aging on bearings and rotating elements. machinery. 10 {

FORT CALHOUN AGING PROGRAMS POTENTIAL FOR DISCOVERING AND PLANT PROGRAM DESCRIPTION RESPONDING TO AGING Thermal Performance Monitoring - measures the Degraded performance and efficiency may be a result of the effects of aging on heat transfer surfaces. performance and efficiency of heat exchangers and the plant. Cathodic Protection System - ensures integrity of sub-Will ensure no degradation of suHround structures due to corrosion will occur over time. ground structures. Ufe cycle Methodology for I&C System - tailored Addresses aging and obsolete l&C equipment. collaboration with EPRI. Maintenance Rule Program - monitors effectiveness of Addresses structures, systems, and components at FCS with rega:d to reliability and per se due to aging. maintenance. 8-l f M d 11

iW ] l 9

SUMMARY

OF '98 REFUELING OUTAGE MODIFICATIONS AND FACILITY CHANGE ECN'S MBf DRIVER TELf. I N MR-FC-92-043 D DC Manual Transfer Switch Replacement % MR-FC-92-046 D MCC-4C2 Feeder Cable Sizing Deficiency N MR-FC-95-003 C Replacement of bad actor relays for DG-1 and DG-2 m MR-FC-95-018 O Upgrade of the DC Bus Feeds to Al-41A/B MR-FC-95-024 O/R Steam Trap on FW-10 Steam Chest MR-FC-96-003 C/R Prevention of HCV-348 Bonnet over Pressurization , MR-FC-96-007 O/C Resolution of RMS-9 Concems for GE Type Ak-50 Circuit Breakers MR-FC-97-001 C DC Ground Detection improvements MR-FC-97-004 CID Manual Reset of PCV-2909, PCV-2929, PCV-2949 and PCV-2969 N MR-FC-97-005 E/O Steam Generator Orifice Plate Removal MR-FC-97-006 - E/O Improvements in the S/G Platforms MR-FC-97-007 C Correction of CCW System Deficiencies MR FC-97-011 O Modify Hi Pressure Alann on RCGVS { MR-FC-97-019 C Reactor Coolant Pump Motor Lube Oil f Collection System l N MR-FC-97-025 R Raw Water Header Flow Instrumentation ) Upgrade j MR-FC-97-028 C/R/0/E LPSI Header Vent Valves l i A % gud A4% MRs 3 I c= L

SUMMARY

OF '98 REFUELING OUTAGE MODIFICATIONS AND FACILITY CHANGE ECN'S ECN# DRIVER TITLE ECN-94-440 R MTSV Test Circuit Upgrade ECN 95-133 O Balancing of the Control Rod Drive Ground Detection System ECN 95-249 IS Grating Extension in RC-3B and RC-3C Pump Bay ECN 95-263 C Waterproof HCV-383-3/4 Junction Boxes ECN 95-296 R FH-3 Cam Tack-Weld j -ECN 95-330 R Door Latches for Panel Al-3 ECN 96-082 R Heater Drain System Relief Valves i ECN 96-255. O Heater Drain Pumps FW-5A, SB and SC Flushing Unes % ECN 96-295 R Add Temperature Indication for RCP Motor ARD ECN 96-408 O/D Replacement of 43/742-3A and 43/742-38 Switches ECN 96-438 O Replacement of 43A/CIAS and 43B/CIAS with Spring Return to Normal Switches ECN 97-019 O Additional 480V Power Feed into Containment % ECN 97-064 O MOV-CV isolation Valves % ECN 97-181 R/O Condenser Air in-Leakage Measuring Device N ECN: 97-266 R Moisture Separator Drain Piping N ECN 97-349 R Condenser Tube Staking C - Commitment Driven R-Reliability Improvement E - Economic Improvement. O - Operations Improvement D - Design Basis IS -Industrial Safety n-w-______-_-_

) = FORT CALHOUN AGING ASSOCIATED MODIFICATIONS MOD NUMBER TITLE FC89-076 Boric Acid Concentration Reduction FC89-077 Control Room OPS /Maint Work Center FC89-081 FW-10 Steam Supply Line Break Prot. FC89-082 OSPDS Communication Priority Change FC89-083 DG 480V PNL DP-1 Ckt. Bkr Mech. Interlock FC89-084 Steam Generator Overfill Protection FC89-086 Mounting of DG-1 Annunciator Horn FC89-087 F.O.-139, F.O.-14ITSample Line and Valve FC90-002 Backup Heaterless Air Dryer - FC90-003 TE-601 Containment Sump Penetrations FC90-004 Auto Closure Interlock Removal FC90-005 DG Instrumentation Upgrade FC90-013 DG-1/2 Fuel OM Tank Access FC90-014 Fire Protection Jockey Pump Replacement FC90-015 13.8KV/480V Emergency Transformer FC90-022 Flow Orifice / RW Disch Piping CCW HX FC90-023 161KV System Modifications FC90-024 LPSI Pump Low Voltage Trip Interlock FC90-025 Charging Pump Coolers Relief Valve Unions FC90-026 , R.W. Discharge Valve Replacement FC90-031 Diesel Generator 10 Sec. Start Recorder FC90-038 Main Feedwater Supports Room 81 FC90-041 DG Voltage Regulator Replacement FC90-042 Fresh Air intake for Diesel Generators 28 l

FORT CALHOUN AGING ASSOCIATED MODIFICATIONS MOD NUMBER TITLE FC90-044 AC-7 Vent Line Strainer FC90-046 Elimination of Xenon Gas Problem, RM 6 FC90-047 Pipe Restraint RCH-32 and RCH-33 FC90-051 WR Log Channel, Power Indicators, CB-4 FC90-052 Cage for Boronometer/ Failed Fuel Mon. FC90-054 Replace Limitorque Oper on HCV-1385 Etc. FC90-055 Al-100 Telephone FC90-057 Water Plant Sampling, Phase ll FC90-058 CCW Relief Valve Threaded Unions FC90-059 Al-31D-DW2-PS3 Deactivation FC90-061 On Line CECORE FC90-062 Thermal shield Locking Collar REPL FC90-063 Diesel Generator Room HVAC Control FC90-064 Correction of SEC System Deficiencies FC90-065 Containment Roof Crane FC90-066 CCW Make-Up indic. (LCV-2801 Position) FC90-067 FW-8C Loadshed Following OPLS FC90-068 Ni Cable Separation l FC90-069 Mounting of FP-1B Fuel Oil Day Tank-FC90-070 ILRT Vent PASS FC90-071 CEA Change Machine Removal FCPD-072 Repair / Replace Fire Barrier Seals / Dampers FC91-002 HG-104 Flanges FC91-003 Spent Fuel Pool Suction Break 29

FORT CALHOUN AGING ASSOCIATED MODIFICATIONS l MOD NUMBER TITLE FC91-004 DG Cooling System Enhancement ) FC91-006 Single Indication Lamp Modification FC91-007 Aux. Bldg. Truck Bay Overhead Door Replacement FC91-008 Under Voltage Prot. For 480V SG. Motors FC91-009 Spent Fuel Pool Re-Rack ~ l FC91-010 ~ Relief Valve Unions FC91-011 Flow Indication for Charging Pumps j FC91-012 - Va-Aux. Additional Filtration FC91-013 RPS Delta T Power Fluctuation FC91-014 Replacement of YCV-869D FC91-015 Press. Loop Seal FlangeNalve Leakage ~ FC91-016 Elimination. Of Old Elect. Cable in Cont. Rm. FC91-018 Door 1007-19 Inter Lock f FC91-019 Warehouse X-ray Machines FC91-020 120VAC Instr. Bus Coordination Concern FC91-021 ERF Indication for 480VAC Breakers FC91-022 Chem. Lagoon /Ph Neut. Enhancements FC91-023 Explosive Detector Gas Generators FC91-024 Raw Water Header Annubar Replac'ement FC91-025 Rept. of Valves LCV-383-1 & LCV-383-2 l FC91-026 Station Battery Replacement FC91-028 Change to RC-2B insulation Support Ring FC91-030 Replacement of Charging Pump Discharge Valve FC91-001 DG Radiator Damper Upgrade 30 L---

~~ FOR_T CALHOUN AGING ASSOCIATED MODIFICATIONS MOD NUMBER TITLE FC91-032 Installation of Tendon Testing Platform FC91-033 Sand filter Backwash Tenk Installation FC91-034 AFW Test Line Removal I FC91-035 VA-68 Duct Access Port FC91-036 Feedwater/ condensate Pump Operation - FC91-038 Containment Pendant Light Replacement ~ FC91-040 Liquid Abrasive Deconning Sys. Hook-up f FC92-001 SIRWT Filtration FC92-002 PAL Equalizing Valve isolation FC92-003 .-_4160 & 480V Breakers. Close Circuit Super. FC92 005 FW-6 Mechanical SealInstallation FC92-006 RM-057 Refrigerated Air dryer FC92-007 VA-82 Bypass FC92-008 Removal of Check Valve Internals /WD-817 FC92-009 Si Relief Valves Setpoint Change FC92-010 ERF computer Point for RCDT Level FC92-011 Upgrade of Loops 1183 and 1188 FC92-012 Seismic Mounting of DC Bus Breakers l FC92-014 Emergency. DG F.O. Storage Capacity Addition l l FC92-015 161KV System Modification - Phase 2 FC92-016 Seismic Peak Acceleration Recorders FC92-017 Containment Audio Count rate Speaker FC92-018 RM-060 Isolation Valve Replacement FC92-021 Sample Point for RCDT & CNTMT. Sump 1 31

1 c FORT CALHOUN AGING ASSOCIATED MODIFICATIONS I I MOD NUMBER TITLE FC92-022 Turbine Bldg. Crane HE-3 Controls FC92-023 Containment Crane HE-1 Controls Modernization FC92-024 Replacement of HCV-1040 FC92-025 Replacement of CA-555 & Assoc. Piping FC92-027 Nuclear Instrumentation Rod Drop Annunciator. FC92-028 lAV Under voltage Relay Replacement FC92-029 Wide Range Nuclear instrumentation FC92-030 CCW RCP Seal Cooler Header Relief Valve FC92-031 Altemate sources for Inst. Bus #1 & #2 FC92-033 CV Closure & Power / Load Unbalance Trip i FC92-034 Backup Monitoring Sys. For Peak Linear FC92-035 Shutdown Cooling system High Flow Alarm FC92-036 Penetration M-79 Manual isolation Valve FC92-037 Secondary Sampling system Upgrade FC92-038 Pressurizer Loop Seal Drains FC92-041 HCV-247 Keylock Switch FC92-042 PORV BlockValves Motor Replacement FC92-044 Simplification of Eng. Safeguards Sys. FC92-045 Move R. V. Flange Pres. Switch & Indic. FC92-047 Overload Sizing for MCC Feeder Cables FC92-048 MOV Contactor Voltage Concerns i FC92-049 QSPDS Firmware Update - CET/SMM/HJTC P/S FC92-050 CCW HX Draining improvements FC93-001 BAST CH-11 A & CH-118 Level Indication 32 l

e l FORT CALHOUN AGING ASSOCIATED MODIFICATIONS MOD NUMBER TITLE FC93-002 HCV-438A/B/C/D Time Delay FC93-003 AC-1B CCW HX RW Drain Valve FC93-004 Provide ERF Computer Indication for I&C j l FC93-OO6 Re-Routing of 120 VAC Cables FC93-008 Assoc. Config. Changes. For Spent Fuel Pool RK FC93-012 Replace SFP Temp. Elements TE-408 FC93-013 Replace FH-1 control Console FC93-014 Upgrade CCW Piping Supports ACH-231,238 FC93-015 Modification to PORV Loop Seal FC93-017 HCV-383-3 & HCV-383-4 Limit Switches 1 FC93-018 Walkdown findings for SOUG/IPEEE FC93-019 FCV-1368 Control Circuit FC93-020 FW-6 Spare Conductors FC93-021 Control Rod Drive Ground Detection Sys. FC93-022 Replacement Valves for HCV-746A & 746B FC94-001 Temperature Monitoring FC94-002 Replace MCC Breakers on DC Buses FC94-003 RW Pump Discharge Pipe Replacement FC94-005 Supervisory Relays FC94-006 VA-166 Drain Line l FC94-007 Under Sized Power Cables FC94-010 Replace of IA-3094, with a Larger Valve FC94-011 VA-86/96 Air Distribution & Controls FC94-014 Spacer in Steam Generator Hand Holes l 33 ~ l

FORT CALHOUN AGING ASSOCIATED MODIFICATIONS MOD NUMBER TITLE FC94-021 RW isolation Vaives Auto Actuation Circuitry FC95404 instrument inverter Frequency Regulation FC95406 Fuel Sipping System FC95-014 Replacement of HCV-480/481/484/485 FC95-021 Containment Spray Pump Suction Piping ~ FC%-005 , i!CV-1045, YCV-1045 Hand Control Switch 6

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  • What are the Critical Steps?
  • What Error-Ukely Situation Exists?
  • What is the Worst that can Happen?
  • What Baniers or Defenses are Needed?

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