ML20203F113

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Summary of 980112 Meeting W/Util in Rockville,Md Re Progress Toward Resolution of Issues Specified in CAL 2-97-01,dtd 970304.List of Attendees & Copy of Handouts Presented at Meeting Encl
ML20203F113
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/02/1998
From: Raghavan L
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
CAL-2-97-01, CAL-2-97-1, NUDOCS 9802270208
Download: ML20203F113 (208)
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Text

{{#Wiki_filter:. t.km # Coq t UNITED STATES p* u- ) NUCLEAR REGULATORY COMMISSION-t WASHINGTON D.C. 30M64001 February 2, 1998 LICENSEE: Florida Power Corporation FACILITY: Crystal River Unit 3

SUBJECT:

SUMMARY

OF MEETING ON JANUARY 12,1998 STATUS OF CONFIRMATORY ACI'lON LETTER ISSUES On January 12,1998, representatives of tho Florida Power Corporation, licensee for Crystal River Nuclear Plant, Unit 3, met with staff memt,ers of the U.S. Nuclear Regulatory Commission at its Headquarters in Rockville, Maryland. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the handouts presented at the meeting. The licensee presented an overview of its progress toward resolution of issues specified in the Confl.matory Action Letter (CAL Nc. 2 97 001) dated March 4,1997. Specifically, the licensee <fiscussed its corrective action programs and stated that CAL ltems 2 end 3 have been adequately addressed. The discussions were general working-levelin nature and did not result in specific action items. L. Raghavan, Project Manager Project Directorate ll-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Attendees List
2. Meeting handout cc w/ enclosures: See next page

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. = = g February 2, 1998 -e LICENSEE: Florida Power Corporation FACILITY: Crystal River Unit 3

SUBJECT:

SUMMARY

OF MEETING ON JANUARY 12,1998 STATUS OF CONFIRMATORY ACTION LETTER ISSUES On January 12,1998, representatives of the Florida Power Corporation, licensee for Crystal River Nuclear Plant, Unit 3, met with staff members of the U.S. Nuclear Regulatory Commission at its Headquarters in Rockville, Maryland. Enclosure 1 is a list of attendees. Enclosure 2 1 is a copy of the handouts presented at the meeting. The licensee presented an overview of its progress toward resolution of issues specified in the Confirmatory Action Letter (CAL No. 2 97-001) dated March 4,1997. Specifically, the licensee discussed its corrective action programs and stated that CAL ltems 2 and 3 have been adequately addressed. The discussions were general working-levelin nature and did not result in specific action items. /S/ L. Raghavan, Project Manager Project Directorate ll 3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Attendees List
2. Meetin0 handout cc w/ enclosures: See next page

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a d64 L Document Name: G:\\ CRYSTAL \\9'10112. SUM Office PM:PDil.3 LA:PDil-3 PD:PDil 3 Name LRaghavan b BClayton FHebdon Date 1/j98 $/N98 / .112/98 Copy Yes/No Yes [Ye's o OFFICIAL RECORlfCOPY

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SUBJECT:

SUMMARY

OF MEETING ON JANUARY 12,1998 STATUS OF. CONFIRMATORY ACTION LETTER ISSUES Qistribution ' HARD COPY 20ookst WP PUBLIC Crystal River Reading OGC ACRS -L.Raghavan J. Johnson, Ril 2 E-Mail - S. Collins /F Miraglia (SJC1,FJM) R. Zimmerman (RPZ) B. Boger (BAB2) J. Zwolinski IJAZ, RCN) K. Landis (KDL) F. Hebdon (FJH) B. Clayton (BAC2) J. Joudan, Rll - T. Martin (e-mail to SLM3) M. Tscliittz, EDO (MDT) B. Keeling S. Flanders S. Cahill E. Weiss G. Holahan-B. Sheron L. Reyes, Ril C... Miller L. Spessard T. Hsia - G. Lainas R. Wessman e y 4 ~J

= = ' CRYSTAL RIVER 3 MEETING JANUARY 12.1998 Name Oroanization L.Raghavan NRC-NRR FraJ Hebdon NRC-NRR Eric ~WeisF NRC/ SRI Kerry Landis NRC/Rif Scott Flanders NRC/NRR Betsy Keeling-NRC/OCA i Mike Tschiltz NRC/OEDO Johns Jaudon NRC/Ril Bruce Boger NRC/NRR Gary Holahan NRC/NRR Brian Sheron NRC/NRR Roy Zimmerman NRC/NRR Luis Reyes NRC/ Region ll Charlie Miller NRC/NRR Lee Spessard NRC/NRR Tony Hsia NRC/OCM/NJD Joseph Galo Gallo & Ross J. Holden Florida Power Corp. Ron Bright Florida Power Corp. M. Rencheck Florida Power Corp. R. Grazio Florida Power Corp. John Paul Cowan Florida Power Corp. Roy Anderson Florida Power Corp. Chip Pardee Florida Power Corp. Jim Baumstark Florida Power Corp. Bruce Hickle Florida Power Corp. T.H. Taylor Florida Power Corp. Gus Lainas NRC/NRR R. Wessman NRC/NRR 5

Florida Power Corporation CRYSTAL RIVER UNIT NO 3 GENERATING PLANT cc: Mr. R. Alexander Glenn Mr. Robert E. Grazio, Director Corporate Counsel Nuclear Regulatory Affairs (SA2A) _ Florida Power Corporation Florida Power Corporation MAC-ASA Crystal River Energy Complex P.O. Box 14042 15760 W. Pov>er Line Street St. Petersburg. Florida 33733-4042 Crystal River, Florida 34428-6708 Mr. Charles Pardee, Director Senior Resident inspector Nuclear Plant Operations (NA2C) Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commicslon Crystal River Energy Complex 6745 N. Tallahassee Road 15760 W. Power Line Street Crystal River, Florida 34428 Crystal River, Florida 34428-6708 Mr. James S. Baumstark Mr. Bruce J. Hickle, Director Director, Quality Programs (SA2C) Director, Restart (NA2C) Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Lina Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Regional Administrator, Region ll Mr. Robert B. Borsum U.S. Nuclear Regulatory Commission Framatome Technologies Inc. 61 Forsyth Street. SW., Suite 23T85 1700 Rockville Pike, Suite 525 Atlanta, GA 30303-3415 Rockville, Maryland 20852 Mr. John P. Cowan Mr. Bill Passetti Vice President - Nuclear Production Office of Radiation Control (NA2E) Department of Health and Florida Power Corporation Rehabilitative Services Crystal River Energy Complex 1317 Winewood Blvd. 15760 W. Power Line Street Tallahassee, Florida 32399-0700 Crystal River, Florida 34428-6708 - Attorney General Mr. Roy A. Anderson Department of Legal Affairs Senior Vice President The Capitol Nuclear Operations Tallahassee, Florida 32304 Florida Power Corporation ATTN: Manager, Nuclear Licensing Mr. Joe Myers, Director Crystal River Energy Complex (SA2A) Division of Emergency Preparedness 15760 W. Power Line Street Department of Community Affairs Crystal River, Fbrida 34428-6708 2740 Centerview Drive Tallahassee, Florida 32399-2100 Mr. Kerry Landis U.S. Nuclear Regulatory Commission Chairman 61 Forsyth Street, SW., Suite 23T85 Board of County Commissioners Atlanta, GA 30303-3415 Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245

f C'4 FLORIDA POWER CORPORATION %){3 cavsrit aivra - unir 3 as L FPC INTEGRATED OUTAGE ASSESSMENT e January 12,1998

r yym :u 4 Discussion he i FPC CR-3 4

Background

i l Readiness for Restart Plan j Corrective Action Plan Extent of Condition System Readiness Reviews Licensing and Design Basis l Organizational Roles and Performance Self Assessments Quality Assessments PRC and NGRC Reviews 3rd Party Reviews 2 NRC Inspections

y,,m DiSCHSSiOH i

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l i FPC CR-3 i Orgam.zational Performance Engineering operations i i Maintenance Licensing Training ~ Quality Programs - Assessments Start-Up and Power Ascension Plan ~ Conclusion l I l = l 01/12/98 3

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===. Background=== VP g4 FPC l Management Team - 13 of 17 Key Positions Have Managers New to CH-3 i - Previous Involvement as Key Roles in 5 l Extended Plant Recovery Programs (Davis ) Besse, Pilgrim, Turkey Point, Brunswiick, Salem) r - 3 New Managers Previously l Licensed / Certified as SRO at B&W Units I '01/12/98 l - 10 New Managers Licensed / Certified SRO 4 t a a

i my

===. Background=== l m y%)eP t FPC i CR-3

  • Recovery Plans l

L~ -Incorporate Experience of Management Team l

  • Integrated NSSS Vice President Role

-Utilized Brunswick and Salem ~ Recovery Plans -Encompassed Technical, Licensing, and Organization Improvements 01/12/98 5 l

gV3Jyse..

Background

m 4,,k[*9 9% 4 FPC CR-3 l l -Performance Indicators Developed j Using Best Practices l Assessments of Performance .= > 40 Self Assessments l l ~ 150 Quality Assurance Audits and 7 l Surveillances ~ 70 Third Party Reviews 01/12/98 i 6

l 1 Q. Third Party Reviews $r,Ii] (> 70 Assessments) . *c.. FPC cR-3 Jim Taylor i INPO Ed Fuller Framatome Stu Ebneter John Stephenson MPR Carl Woodard EQE Dr. Chung Chiu Sargent & Lundy i Dr. Knuth Failure Prevention Dr. Thorton International Brian Grimes Professor Black Systems Research 01/12/98 Carter Rogers International 7

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Background

w%r$[* 9 s - e FPC j CR-3 i l -Major Evolution / Inspection Pre-Reviews Restart issue Package Closure l Pre-SSFI i a. Pre-OSTI > 7400 NRC Inspection Hours q j a, s :. ) 01/12/98 8 t 1

l E6 Readiness For Restart (Elements) i FPC CR-3 l 1) Organizational Readiness j 2) Operational Readiness l 3) System Readiness 4) Regulatory Readiness 5) Communications Readiness i 01/12/98 9

p7pwegwre - -- = i c. I ~ 2 Performance Indicators l I g - I. ORGAN 1/'4i10NAl READtNESS Performame Indicators Goal at Startup Achiese Tardet ~ 4 I - 7~ A. Restart issue Gosure 0 Jamsary l [ B. MCAP II Restart item Gesure O AONGED 3 C. SeN-Identined Premrsors* 60 % or Geeater

  • FPC
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umnID l C'R-3 E'**'*""'"*'*"""'""*" ~ II. SYSTEM READINM s ; A. Corre<1ne Maintename 200 Open Mork ACHIGID Resteests or less l B. Temporary Modsfication* 5 or less Installed ACHIGID I j C. Resteests for I;.n:.L.-g 200 or less Open AO9tBID Assistame D. Restart Modifications O AQ98DID L Systems Remaining to be O AOMG?D Accepted by Or.erations Ill. OPERAYl0NS READINESS ? A. Centrol Board Deficiencies 10 or less ACHen1D B. Operator %ork Arounds 7 er Less AOMBID C. Operating Prmedures 25 Cennnents or less AOMOID i I 2

p. Eme gemy Operating Imerporate issues January Procedures from 8 CAL Design issues AN Appresal Steps Complete E. Abnormaal Prmederes 15 Cosmnents or Less ACHIGID IV. REGt1A10RY READINESS l

A. License Amendments O AONGID j and Twh Spec Subenittals l B. Other NRC Restart Sohnuttals 0 January C. Iotal 19#7 NRC Ceannei.ments* 0* Post-Restart l 88 D. Satunitial Quality Indes of 5 or Greater AOMOLD V. COMutWICAll0NS READINESS A. E%ee Surveys Insprose ResuRs AONDID I B. Community leaders Meet Prior to Startup AQMGID C. State & Federal Officials / Staff Meet Prior to Startup ACHIBID D. Opportunity to Tour Plant Elected Officials and Staff AOllB1D Imited to Tour E. Open Communication Editorial Boards. Inteniews, and ACHIGID with Media Plant Tours Conderted for These I %he Ceser 0R-3 Routinely - Internal Targets I 01/12/98 j 10 i k

'~ 8 Organizational Readiness y%3h* i e FPC

  • Self-Assessment Ability and Corrective Action Program
  • Backlogs Reviewed and Assessed i

8 Restart !ssues identified and ~ Closed 1 Integrated Outage Verification a

  • Operational Mindset Established l

01/12/98 11

Operational Readiness =),kg.* W (Operations) l FPC ' " ~ Execution of Emergency and Abnormal Procedures Qualified Staff Levels ~ Acceptance of Plant Systems - l Walkdowns With System Engineers Understanding of Plant Configuration ~ - Valve Line Ups / Tag Outs / Equipment Out j Of Service / Plant Materiel Condition / j JCOs "3'*8 Training Complete +

,c, System Readiness ,$8e c4 i ~ FPC CR-3 l

  • Design and Licensing Issues Identified

^ lo and Resolved (CAL #2 and #3)

  • Maintenance Assessed (REAs, j

l Precursor Cards, Procedures, Open ~ l Backlogs) ~ ~

  • Outstanding Equipment Issues Have 7

Compensatory Actions .g. System Functional Tests Complete

  • Integrated Verification Complete 01/12/98 i

13 i

s Regulatory Readiness g%,,%2" 1 FPC CR-3 JCOs, Technical Specification, and Licensing Amendments Approved Submittal Quality Improved 4 1997/1998 Commitments Reviewed j i l Employee Concerns Program (ECP) 1 L Functioning i 01/12/98 14 i i

Q yp, -1 Communications Readiness b3VC .n FPC ?" I Employee Survey Results Show Improvement - Synergy -Bisconti Associates l

  • Media Coverage With Positive Focus
  • Community involved

- Civic involvement - Community Meetings og,12/98 15

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P e,rt + Corrective Action Program -g &n.f Lg 4 > _. FPC CR-3 i i

  • 4 Correcti e Action Deficiency $

s Chise Adions $ Closm ut l I f / ~ r aestart - Restart - 10 CFR [ Non-Resta 50.59 - Non- -USQD - Closure Restart Package l - Root Cause Extent of Condition Screening - Apparent Ceus 4 h Criteria l _ p; I i c n i 01/12/98 i l 19 l I _.t

1 q;e;7 w m Corrective Action Program w45u' 7 + FPC CR-3

  • Assessments

-QA c -Third Party c MCAP II Effectiveness T

  • Pre-OSTI j

) -NRC Inspection Report 97-17 01/12/98 20

Corrective Action Program FPC CR-3 1997 Improvements -Established Dedicated Organization -Line Management Ownership -Lower Threshold for Problem ~ L Reporting -Quality of Root Causes -Corrective Action Follow-Up 01/12/98 21

i emey.g. Corrective Action Program i y:57 4 ps FPC ] CR-3 i i -Establishment of Corrective Action j Review Board (CARB) -Use of Performance Indicators i -Senior Management Involvement i I 1 l 01/12/98 22 4

l f p%23&. ' Corrective Action Program m .F ir $.,P i FPC CR-3 Changes in 1997 n. -Graded Precursor Card Approach -Reportability and Operability - Electronic Database for Tracking and Trending -Communications Tools -Training 01/12/98 23

I l Extent of Condition Timeline of Assessment and Verification Activities t-R- 1 ~ uesign s-Rea9 ess v Assessment EME "c Activities t ~ l Team l D-16 Aggrega'e g ]f saw y,,,,3c,,3,, Am m-e ') f LOCA Team Jk I gm Re -wamenaten of DW I g WC % aggregate of Non Project h { l N r EO &fe I m Assesserent y y y y y y y t 7 Sepi,96 Oct. 96 Jan,97 Feb 97 March,97 April,97 May,97 June,97 July,97 Aug.97 Sept 97 Oct. 97 Now,97 Dec,97 b A A >A I Shutdown due Orgamzaten Rettart i to Turtnne Self Lcense Operator Lube Od Assessments Hequahfica*cn Defense in g g y Depth 8 Measures o * =*oPac i i m subconmtree E I for EOPs Safety Analysis Group Reviews a!! 50.59 Evaluations 01/12/98 k oe33gn sey,ew Boards 24 d f i

Extent of Condition

        • r
%%i5 System Readiness Review am i

i l FPC 1 l CR-3 2 Self Assessments l l -Senior Nuclear Executives l -Quality Assurance 3 Third Party Reviews l - Failure Prevention International (FPI) ~ -MPR j -INPO ""is* NRC SSFI i

l m Extent of Condition -+, $i,.L$_ System Readiness Reviews m i FPC CR-3 Prioritized and Grouped Systems l - PSA: Contribution to Core Damage Frequency l -Fission Product Barrier Approach l (10 CFR 50 Appendix A) -Maintenance Rule Risk Significance l ~ -Safety Significance l -Previous System Assessments o,,12/98 26

Extent of Condition "~ ~' n-3,,p%P System Readiness Reviews g SIS System Review Matrix l Level 1 and 2 Systems j - SSFI Methodology j - 30 Topical Areas ~ l

  • Design and Licensing Documents Operations Maintenance and Surveillances Physical Plant Walkdown / Drawings
  • Programs, Process, Procedures

-Includes > 99% of Systems Contributing 01/12/98 4 o Core Damage Frequency f 27

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System Readiness Reviews i l LEVEL 1 LEVEL 2 LEVEL 3 1 .s.; I i l l l ll l 1 l I l'l' l I i .t l 01/12/ i 29

l SYSTEM READINESS REVIEW PROCESS t License Design Procedures Configuration j i t_ i l I Procedures Walkdowns FSAR EDBDs l ops /SPs/EOPs l l l O en ms P ITS ABDs Section XI pc pp, I FS Commitments gcci e t nalys = l l l Notices / CMIS Maintenance Bulletins r Specifications l f l Calculations I&C/ Mech /Elec I 01/12/98 Drawings 30 i

l Extent of Condition j y System Readiness Review l - e Attribute Evaluation i FPC l CR-3 Attribute Checks l 16044 SAT Discrepancy 14520 1524 [ Work Controls Restart Process Issue 01/12/98 1149 375 31

i Extent of Condition 4 onfiguration Document Integration I' i Collection of FPC System '"f "" t' " l CR-3 j integrate i information by , system in central location l Develop j Licensing Basis by system Integrate Plant j System Ownership Licensing Basis Teams Acceptance 11 Documents i i ~ Overall Integrated / '] e cadon \\ 01/12/98 32

Extent of Condition Configuration Document l ~ ~~ l Integration Project FPC CR-3 FSAR Change Distribution by Chapter l 125 - f DMARs e C 'h*' I 3 100 - E i Precursors 3 j g 75 - 23 a i 35 f 24 l o 50 - 2s as l L-15 8 6 . 8 8 17 10 3 3 E 25 - u'

  • 55 i

o um, as mu4 2 3 m' z 0 25 25 0 1 2 4 5 6 7 8 9 10 11 14 01/12/98 FSAR Chapter i 33 _~

i Extent of Condition ~ Integrated Verification l Conclusion FPC l ca-3 Of the Restart Modifications, Over 20% Directly Enhanced the Ability of the Operator to Physically Operate the System j - EFV-12 EFW Crosstie FWP-7 Standby Diesel Power l - HPI Recirculation to Sump EFP-1 Trip Defeat Switch l - RWP/SWP Pull to Lock Switches Letdown Line Valve Addition l - FST-CDT Crosstie RB Fan ES Logic ) l ~ - MUV-27 Auto Closure 480 ES U/V Lockout - CREVS MOV-103 Replacement j ~ - 2 Modifications Greatly Enhanced the Main Control Room Environment 01/12/98 34 i I

Extent of Condition {Wgy Integrated Verification e Conclusion FPC CR-3 l

  • Balance of modifications brought l

l the systems into compliance with design and licensing basis l

  • The systems now will operate as expected by the operator under all i

conditions j I 01/12/98 l 35 l .i

= j.y?.y +:+:: Licensing and Design Basis m-i .%5i* -.e FPC

  • 2 Self Assessments i

~ -Licensing and Regulatory i l Performance (1/97) \\ -Review of SA / USQDs Associated with TSCRN 210 (6/97) l i 01/12/98 36 l l

n-g, Licensing and Design Basis ye FPC l 3 Third Party Reviews - Review SA/USQD Process (3/97) i l - Followup Assessment to Verify k SA/USQD Implementation (9/97) i - Altran Quality Review of Selected l SA/USQDs (10/97) j NRC Inspection Report 97-08 (7/97) 01/12/98 37 \\ \\

i l m =- Licensing and Design Basis Sr$& . ~ FPC ~ Initiatives -10 CFR 50.59 Improvements 4 Proceduralized (Impact Against 28 Plant Programs)

  • Stand Alone Document
  • Qualification Standards
  • Independent Review Group (SAG)
  • Parallels NRC Guidance

/' /9s . NRC Assessed Five Areas as " Good" l

t n Licensing and Design Basis i w%%p. P j FPC CR-3 -Configuration Document i Integration Project (CDIP) 1 l

  • Integrates Design and I_icensing Informatmn

'x

  • Validated Chapter 14 Accident N

Analysis l

  • Keeps FSAR Integrity

-CoIIation and Review of 12,000 Docketed Items (1976 to Present) o,,12/98 39 .I

1 l ymm l &~ Licensing and Design Basis l S.rI*$ FPC CR-3 l -Resolution of 25 Potential USQs l -Integrated Verification Team ~ ~ 20% of Restart Modification l Improved Operator Ability to Manage ~ l the Plant Assessed Outage Modifications Impact on Chapter 14 Accidents Assessed Outage Modifications on Safety Margins i 01/12/98 40

w,. Licensing and Design Basis

  • %5<i*

FPC i i CR-3 Emergency Operating Procedures l (EOPs) -Upgrade of E0Ps for Technical and Human Factors j g -Resolved Outstanding Technical i Issues l .= j 01/12/98 41

Licensing and Design Basis y%NP ...e FPC CR-3 -Restructured Flow of E0Ps i, l l

  • Increased Ease 1

l

  • Capable of Mitigating Accidents Beyond l

Design Basis 10 CFR 50.59 Safety Evaluations l Performed on Each Procedure l l - Developed Technical Basis j l Deviations Document l 01/12/98 -Veri ied Setpoints for Actions 42

nn Licensing and Design Basis -& lR +T FPC CR-3 i - Reduced Operator -Burden Validated in Simulator and Field I j Reduced by 1 Step Required in Less j Than 20 Minutes Institutionalized 13 Previous Manual Actions l 01/12/98 43 l

mm Organizational Roles and v. 3:,$*! Assessing Performance e l FPC CR-3 I l Self Assessment Results -Creation of CDIP .v -Changes of Work Control Process - MCAP II Program Revised s -Creation of Design Process -Developed Operations Leadership Plan i l -Institutionalized Design Review Board i i 01/12/98 j I 44 1

i Organizational Roles and i e j F-j l SJht Assessing Performance s-i FPC

  • 3rd Party Assessments CR-3

~70 Completed l - 10 CFR 50.59 (Altran) l ~ - Emergency Diesel Generator (MPR, Duke, Carl Woodard) i l - Pre-OSTI (Stu Ebneter) i - Engineering Readiness (Dr. Knuth) - Maintenance Supervisory l 01/12/98 Effectiveness (INPO) 45 i l l

l Organizational Roles and l 3r%.$ Assessing Performance r FPC i CR-3 l - Configuration Management (INPO, l Industry Peers) -JCOs (Industry Peers, Previous VP) l - Appendix R (Nick Fioravante) l - DC FMEA (FPI) i j - CCHE (MPR) - Conduct of Operations (INPO) t - e. j 01/12/98 i 46 l

I l Organizational Roles and l 38.$ Assessing Performance c FPC t ca-3 l

  • Quality Assessments

~150 Completed l l - Areas of Focus i l

  • Identified Programmatic Issues for Resolution Such as Scheduling Surveillances in Grace Period; Training of Contractor Personnel; l

Translation of STS Requirements into ITS

  • Oversight for Restart Activities Such as l

Containment Penetration Closecut; Construction of Scaffolding l

  • /}2/98
  • Reviewed Restart Packages for Closure i

Organizational Roles and Sm S$w Assessing Performance P l j FPC l

  • Plant Review Committee (PRC)

~ -Organization and Role l ~ - Areas of Focus 4 Provided Oversight of Activities Involving Nuclear Safety i Reviewed Technical Specification and License Amendments Reviews all Changes to Emergency and Abnormal Operating Procedures Used to 8 l' [88 Mitigate Accidents i

Organizational Roles and "F i e-i

St8f, Assessing Performance FPC CR-3 i

Nuclear General Review Committee l 1 (NGRC) l -Organization and Role l - Areas of Fccus l

  • Independent Check on Selected System l

x+- Ability to Perform Design and Mitigation Functions

  • Independent Review of I_evel 1 and 2 l

~ System Readiness Reviews /

  • Independent Assessment of Organizational "C*,'**

Ability to Support Restart

l l Organizational Roles and 1, _.- &$f-Assessing Performance FPC I CR-3 Safety Analysis Group (SAG) s -Organization and Role j -Safety Assessment Effectiveness . Ability to Self-improve r i

  • Improved Knowledge and Skills of j

Preparers Improved 10 CFR 50.59 Quality 1 i l 01/12/98 l so i

l l Organizational Roles and y, l $$.$ Assessing Performance e l FPC i CR-3 l Corrective Action Review Board (CARB) -Organization and Role ~ ~ - Areas of Focus 7 Review of All Root Cause Analysis l ~ Reports for Adequacy l

  • Reviews Precursor Trend Analysis l

Involved in Effectiveness Grading of i 01/12/98 Root Cause Reports 51 1

Organizational Roles and ~ mi. l 3~,3K5 Assessing Performance i m FPC l CR-3

  • Restart Panel

- RoleoAssess Activities Related to Restart j l and Make Recommendations to l L~ Senior Nuclear Officer for Restart j y - Areas of Focus i i

  • Validated Results of System Readiness Reviews
  • Established and Overviewed Restart Screening A

Criteria l

  • Provided Oversight of Restart Readiness Plan 0 / 2/98 Checklists 52

E Organizational Roles and Assessing Performance FPC ~ Restart Issues Screening Panel - Role - Areas of Focus l

  • Ensured Consistent Application of I

Restart Screening Criteria j Reviewed Precursor Cards for Restart Criteria Application j

  • Determined What Items Became Restart 01/12/98 lssues 53 l

i ) sm.m Assessments of Performance w%%.# P FPC ~

  • Third Party Reviews 1

-JCOs for GL 91-18, Rev.1 l j - Pre-Operational Safety Team j Inspection (Pre-OSTI) -Design Solution Sets i -Calculations -Technical Programs 01/12/98 54 I

l wee N Assessments of Performance &$e P j i FPC NRC Inspections CR-3 e - Restart Issue Closure -SSFI - Make-Up & Purification and Decay Heat Removal i - 0STI - Plant Readmess - E0Ps - Technical Basis Document, Set Points, Validation, l Performance ~ -10 CFR 50.59 / Safety Assessments -Corrective Action Program /88

h i i E rganizationalImprovements Engineering i O 1 rec CR-3 -Recruited External Managerial Experience l - Promoted Internal Top Performers -Realigned Responsibilities i -Creation of: I Safety Analysis Group Design Ra. view Boards l ,,,,i,,s -Framatome Engineering Vice so President on Site

,3,m Engineering &%t, MS l Knowledge and Skills Improvement -10 CFR 50.59 / USQi >3rd Party -Human Error Reductioni >FPI -Root Cause Analysisi >FPI -Event Free Operationi >FPI - Probabilistic Safety Assessmenti > Internal 01/12/98 57

1 j i E Engineering i MS

  • Improvements in Programs i

-Plant Modification Process i -Design Review Board -Increased Safety Margin -Reduced Operator Action i i .L- -Improved Root Cause i a -10 CFR 50.59 Process -Engineering Services ~ 01/12/98 -Reduction in Backlogs ss

l rww, W Engineering i RL%P l y %, i !!S Performance Assessments i l -6 Self Assessments 1 -INPO, EPRI, Utility Best Practices and Benchmarking i -Process Flowcharting 1 -Technical Design Programs l - Plant Specific Issues l -Design Review Boards 01/12/98 59 f

l gen. Engineering D&R.. 4 FPC Third Party Reviews - Diesel Generator Technical Issues (MPR, Duke, Carl Woodard) -Safety Significant Modifications (MPR, Framatome, Sargent & Lundy) - Engineering Quality Index (FP!) l -Engineering Readiness Assessment (INPO) l 01/12/98 l -Configuration Management so 1

enn "giw Operations gj yr e FPC ~ Organizational Improvements -Recruited 23 Personnel, 7 Previously Licensed l -Operations Leadership Plan l l Implemented -Returned Senior Licensed Person to l Crew Leadership Position j l

  • Graduates of INPO Supervisory

"M'*8 Development Course

i i i I f.:g -. Operations ^~ 4

  1. 4SP i

y e FPC CR-3 -Re-established On-Going License Operator Pipeline -Establishment of Work Controls Center 7 Self Assessments i -Tagging / Clearance Process -Senior Management Involvement In ~ Training 01/12/98 -Operations Training 62

(@0

2. ~.

Operations i Mh5 1 FPC l CR-3 -Work Controls -Conduct of Operations 4 -Site-Wide Accreditation Self Assessment i -Established Management j Observation Program 01/12/98 63

j n., Operations w r$g* Et i q FPC i CR-3 i 3 Third Party Assessments j -INPO Peer Assist of Control Room Functions l -INPO Review of SOER 96-1 (Control l Room Command & Control) e -Previous NRC Senior Resident i Inspector Review of Conduct of i Operations i 01/12/98 64

4 I gyyg.y e. - t m-Operations W57 h y m. FPC i i CR-3 Improvements i -Operations Ownership l -Backlog Reduction -Reduced Operator Burden

  • Emergency Operating Procedures
  • Reduced Work Arounds, Control Board Deficiencies
  • Control Room Noise Abatement 01/1 /98 2

es

  • Procedure Comment Reduction

\\

mes.. Operations y--.-)e.* Mir j FPC j CR-3 -Reduction in Operator Errors l -Establishment of Performance Indicators -Commitment of Resources to Support Operations Pipeline 4 i 01/12/98 66

} l l nwn: g, Maintenance e 1 $$In$ j g-i FPC l Organizational Improvements l CR-3 o -Recruited External Managerial Experience - Promoted Internal Top Performers j -Moved Maintenance Supervision to Field 4 -Establishment of Maintenance Support Groups -Planning Function Moved to 01/12/98 Maintenance 67 i

parepym7 o. j m Maintenance YI c FPC CR-3 -Corrective Action Group Created -Training Review Committee and Peer ~ Group Established l U

  • Material Condition Improvements

-Preservation Upgrade Program -Resolution of Long-Standing l Equipment Issues (10 Years Old ~ Reduced to 3 Years) ~ 01/12/98 68 I

y,w. Maintenance y%$e* I FPC t -Generator Rotor Repaired ~ - Facility Improvements -Corrective and Preventive Maintenance Backlog Reduction ~ (. -Reactor Coolant Pump Oil Leaks -Control Room Improvements 01/12/98 69

e Maintenance $<ND E i FPC l CR-3 l 4 Self Assessments -Work Management Controls - Maintenance Training - Switching and Tagging i - Electrical Work Practices 2 Third Party Assessments -INPO Assist Visits Work Control ~ -INPO Maintenance Supervisory Practices l 01/12/98 70 a

q;y2m. l Maintenance w%)s t P FPC CR-3 Other Improvements -Backlog Reduction l 1-l -12 Week Rolling Schedule i ) PSA Techniques l

  • On-Line Maintenance Windows l

- Performance Indicators to Measure Performance 01/12/98 I 71 1 1

i ?lkf (-??: } ',e! 4 a Maintenance 1 pks?n w FPC CR-3 -Establishment of Maintenance 1 Training Cycle -Nuclear Maintenance Manual

  • Standards

~

  • Expectations
s I

l 01/12/98 i 72 i f 1

i 1 \\ E Licensing \\ FPC l CR-3 o - Organizational Improvements - Organization l

  • New Licensing Manager l
  • Performance Issues c;

l 7e i Streamline Responsibilities l ~ -Schedule Adherence Via Timelines l -Quality Improvements 01/12/98 gg i

i j ge g j Licensing i hki$ FPC CR-3 I i '3 Overall Licensing Submittal Strategy \\ l \\ -Submit Concept Early j 1 e - Follow On Technical Meetings ) i y -Informational Supplement \\ -Final Detailed Supplement 1 l l 01/12/98 74

i r74e#$F:.:::. - c licensing N y

l i

FPC CR-3

  • Submittals l

-53 License Amendments -82 Other Restart Submittals l

  • Conformance to Design / Licensing Basis j

i

  • Potential Unreviewed Safety Questions
  • Resolution of NRC Inspection Issues i
  • Commitments 01/t2/98 75

ww N Licensing i MI4] l c I FPC CR-3

  • 265 Closure Packages

-264 Completed - NRC Inspection Items

  • 2 Self Assessments

-Licensing and Regulatory Performance I - Review of the Technical Specification 01/12/98 Change Process f 76 i i

Sig!W l 7 Licensing y% % P me FPC j CR-3

  • 4 Third Party Reviews l

-10 CFR 50.59 (3) -Nuclear Regulatory Affairs Startup j Readiness i

  • Performance Indicators

-Schedule Performance i - Quality l 01/12/98

l 77 l

t 4

5 i

Tranninf, 1

i FPC CR-3 Organizational Improvements -Recruited External Managerial Experience l . 1, -Creation of Training Steering Committee j -Establishment of Program ~ Curriculum Committees l l - Continuing Training Implementation l 01/12/98 i 78 l

J (l;?v.4:?:.gy. - = l Training 1 FPC CR-3

  • 8 Self Assessments l

- Accreditation Self Evaluation Reports j (Operations) - Identification of Long Term Training Needs l l - Preparations for Startup ~' l - On-The-Job Training and Evaluation l (Maintenance) i ~ - Simulator Fidelity (2) l 1 - Emergency Operating Procedure Training 01/12/98 - Overall Training Program Effectiveness 79

Training FPC CR-3 i l 2 Third Party Assessments \\~ -INPO Assist Visit - Operator \\ l \\ Training for E0Ps \\ . \\/ - Maintenance Training (Peer Utility) T \\,. 't i .\\ .\\\\ l >\\ r I 01/12/98 80 i b

i l te m ei n y 7 m ic Training wN **4 e FPC CR-3 . Improvements -Greater Training Involvement by l Line Organizations 1 -Routine Incorporation of Operating Experience into Training Activities -Increased Level of Senior Reactor Operator Certification Classes 01/12/98 81

i Training 4 i i i FPC CR-3 l -Training Effectiveness N

  • 10 CFR 50.59 i
- i Operator Error Rate
  • Annual Requalification Completion
  • Self Checking

-Simulater Leads Plant in Modifications 01/12/98 l 82 l l

l wm ~ Quality Programs l &Lt-y- FPC CR-3 Organizational Improvements l -Recruited New Manager of QA l -Externally Recruited 4 New Staff Members -Established Viable Rotational Assignment Plan Augmented Outage Staff With 5 Contractors o,,,2,os 83 i

i l m-w+ g; Quality Programs ,e i FPC i '"-3 Other Improvements -Change to Performance Audits and Surveillances in Addition to j Compliance -Quick Turnaround With Clear Line Management Understanding of Inspection Results l -Intrusive Into AII Elements of Restart -Single Point of Contact for Site Self l "i* Assessments s

l Quality Programs FPC CR-3 l x

  • Performance Assessments

-MCAP Effectiveness Assessment l Noted as Strength -Third Party Assessment (9/97) Noted l Quality as Having Positive Impact on l Overall Site Improvement ~ -NRC Region II Noted QPD as Effective j y l (IR97-16) and Performance as Good l' /' '88 (IR97-17) 85 L l

Assessments "Y' \\ e i FPC CR-3 > 40 Self Assessments ~ 70 Third Party Reviews ~ 150 QA Audits / Surveillances l l 37 NRC Inspections Jan - Sept ~10,900 Hours ~ 4,300 Hours by NRR ~ 6,600 Hours by Region H i 01/12/98 86 I

\\ i l l i?%" W ? Results ! 3r$i" l %9 l FPC CR-3 i ~16 000 Attributes in System Readiness l i' ~ 585 Commitments Completed 1 ~ ~ 46 LERs Issued ~ 25 USQs Resolved > 8,000 Maintenance Work Requests ~8,800 Precursor Cards Initiated j 01/12/98 87 l

mm l Start-Up and Power Ascension j 3,$i] l <r FPC cu . Organization Staffing -Shift Crews Augmented Start-Up Duty Manager i l Test Supervisor l Engineering Supervisor l Maintenance Supervisor 1 I Licensing Supervisor -Specific Training Conducted "";/"*

  • Hold Points 11..

i nm, Start-Up and Power Ascension m = 45 FPC CR-3 Tests i -Post Maintenance 1 -Surveillances and Performance j -Modification Functional i -Infrequent Evolutions j j x_ INPO SOER 91-1 i T.. -1 I, i -i 01/12/98 89 4 .a

i Conclusion FPC CR-3 Experienced Team In Place

  • Backlogs Low and Understood l
  • Design and Licensing Basis 1

l Defined and Accessible l l l

  • Ready to Restart l

l .l 01/12/98 90

1 M_ FLORIDA POWER CORPORATION h ki CRYSTAL RIVER - UNIT 3 m FPC CR-3 FPC RESOLUTION OF SAFEIY AND LICENSING ISSUES (CAL #2 and #3) i l January 12,1998 l 01/12/98 1

1 l l l l Discussion FPC Okground CR-3 Summary of Outage i Statistical Information Tah!e of Submittals l 7 Remaining I_onger Term Actions How Do We Know We Are Done - Summary ~ l l Key Area Assessments Third Party Reviews l NRC Inspections l Extent of Condition Timeline l Technical Solution - Example System Readiness Review 01/12/98 Programs Reviewed i 2 CDIP l l l i

i pys+c l DiSCHSSion w%<%.-P p FPC CR-3 l Integrated Verification Licensing Challenges i Technical / Licensing Timelines Quality Requests for Additional Information (RAls) Organizational Roles i Operations and Engineering Perspective ConcInsion 01/12/98 3 i i

g9s cy;; _ "t

Background

Sr$f l FPC CR-3 Management Team l l l - 13 of 17 Key Positions Have Managers New to CR-3 l - Previous involvement in 5 Extended Plant Recovery Programs (Davis Besse, Pilgrim, Turkey Point, Brunswick, Salem) ~ - 3 New Managers Previously Licensed / Certified as SRO at B&W Units - 10 Managers Licensed / Certified SRO l 01/12/98 I 4 i i

my

Background

i$ P FPC CR-3 Recovery Plans / -Incorporate Experience of Management Team j J s l

  • Integrated NSSS Vice President Role

~ 1 l -Utilized Brunswick and Salem ~ - Encompassed Technical, Licensing, and Organization Improvements l -Performance Indicators Developed l 01/12/98 i l \\ l

i i i gy;wsgsy. = 1997 Statistical Information i W $." 4 g FPC l CR-3 > 30,000 Outage Activities Completed I ~ 180 Modifications ~ > 8,000 Maintenance Work Requests 4 ~ 8,000 Precursor Cards Initiated > 16,000 Attributes Checked in System Readiness Resiews l ~ 800 Issues Integrated into FSAR Revis~mn 24 l ~ 225 Root Causes Required l > 40 Self Assessments l ~ 150 Quality Assurance Assessments l ~ 70 Third Party Assessments Completed 37 NRC Inspections > 7400 Hours Inspection 264 NRC and FPC Restart Issues Closed ~ 135 NRC Submittals 01/12/98 6 3 Employee SurveysC Improved Results i

Gr*;:-:57 :n - ,= Table of Submittals n._ FPC CR-3 Submittals NOT Requiring NRC Response l - #214 - ECCS Mode 4 - #218 - Letdown Line Rupture l ~ - #223 - Boron Precipitation Prevention Plan i l ~ Submittals Requiring NRC Response for I Restart i ~ l - #210 - SBLOCA (Mode 2) l - #220 - DH-45-FI [ Boron Precipitation] (Mode 2) 01/12/98 l 7 ?

l l ?WY'- Table of Submittals 457 y l FPC l Submittals NRC Approved ca-3 - #209 - Post Accident Monitoring - #211 - OTSG l - #212 - Appendix J, Option B - #213 - LTOPS - #215 - Exigent Diesel Surveillance - #216 - EDG Fans - #219 - EDG Protective Trips Not Bypassed ? - Appendix R - Enhanced Sprinklers / Exemption 8/ /88 - Appendix R - RCP Lube Oil Fill Line Exemption 3 E-

Remaining Longer Term

    • * ~

m_.- - l %$P Actions ?W l FPC CR-3 4 FSAR Revision 25 - Third Quarter 1998 l l USI A-46 and Large Bore Piping l Upgrades - 3 Year Plan i Modifications - Next Refueling -HPI Throttling and Crossover Line - EDG Upgrades / DG Driven EFW Pump CCHE Closeout - Next Refueling Closeout of JCOs (GL91-18, Rev.1) ,,,12/98 9

.l i 'l I m a r g t l e o h u h r g a P t i f R H os s s g e e I n v n t o i t i aL od ea h e '1 e Wh b R O oT 3 D r -R o C F P, 8 ~3C-y '; : 9 3 / 20 %yFC ~ PR 1 1 ~ / ~ 1 0 !!!il.

!i l!llj(

l il

! M~ ' Confirmatory Action Letter Items #2 and #3 FPC c a-3 Conduct Extent of Condition Reviews to Assure That Safety-Related Systems are i l in Compliance With the Licensing and Design Bases of the Facility Satisfactorily Resolve Any Additional Safety or Licensing Questions Including ~ Those Identified as a Result of System j and Engineering Reviews in Item #2 l 01/12/98 above 11

l How Do We Know ? erm l 38g Summary l !IS Fundamentals Are Solidly in Place l - Corrective Action Program i 1 - Hoot Cause Evaluations [ L f. - 10 CFR 50.59 and USQ Process l Technical Approaches to Design Issues l Have Varied Little (Consistency) A Continuum of Assessments of Performance n i Additional Unreviewed Safety Questions l 01/12/98 Have Not Been Identified by NRC u

l i i E Key Area Assessments (Corrective Action) l ((P

  • Quality Program Assessments 3

l '1 - 9 Assessments l - Program Weaknesses Are Being Identified l .~ and Documented With Action Taken to Resolve Issues i i

  • NRC Inspections l

- 9 Inspections l - Corrective Action Process Has Appropriate Sensitivity To Identifying Issues and l Management Attention To Resolving Issues l - Quality of Corrective Action 01/12/98 Recommendations Continue to Improve is

i i Key Area Assessments i m-w $ e" (Root Causes) 'J A i t 3 i FPC Quality Program Assessments j ca-3 1 - 4 Assessments s l - Questions by Corrective Action Review Board l (CARB) are Probing and Critical ^ l - Quality of Root Causes Show Steady improvement i NRC Inspections l - 4 Assessments - Quality of Root Cause Investigations Continue to Improve - Level and Detail of CARB Reviews Continue to l $'88 he Thorough y_ m._,, 7-, _.,,.--,

l Key Area Assessments l S.Ig (10 CFR 50.59) FPC CR-3 l Quality Program Assessments j - 3 Assessments l - Quality of SA/USQDs is Acceptable -Individuals Preparing SA/USQDs are Knowledgeable j - Positive Performance Trend j l NRC Inspections l - 5 Inspections - 10 CFR 50.59 Evaluations are Generally l l 01/12/98 Thorough. Detailed, and Comprehensive i 15 i I __j

l R: Key Area Assessments SrM (Generic Letter 91-18, Rev.1) i e 1 FPC CR-3

  • Quality Programs Review

= -JCOs Complete l Third Party Review j l -Proposed JCOs Conservative =

  • NRC Reviews

- NRR: 2 JCOs Requested for Review j l - Region: Remaining Reviews in '88 Progress

l Third Party Reviews l "^^ w-l Sr$[ (> 70 Assessments) FPC CR-3 Jinn Taylor gg Ed Fuller Framatome l Stu Ebneter t l John Stephenson MPR i Carl Woodard EQE i l Dr. Chung Chiu Sargent & Lundy Dr. Knuth Failure Prevention Dr. Thorton International l Brian Grimes l Professor Black Systems Research ~ l 01/12/98 Carter Rogers International l 17 l

WW2 M.~..!"~' Third Party Reviews m ;5 ,N4 FPC CR-3 Large Bore Piping Technical Solutions j - EDG Loading and SELOCA Gowric Letter 96-06 - EFIC Upgrade Jet Impingement - Control Room Noise Abatement i Failusee Modes and i - HPI Recirculation to l Effects Analysis uake-Up Tank j Reg. Guide 1.97 - 480 undervoitage Trips - Intermediate BuiEding Cable Ampacity High Energy l_ine Break Numerous - Emergency Feedwater Cavitating Venturis s Calculations - Borort Precipitation 01/12/98 18

e-NRC Inspections SrMC .e FPC 37 NRC Inspections c) > 7400 Inspection Hours l CR-3 I - 10 CFR 50.59 ~ - Operability & Reportability Determinations - Corrective Action Process - Emergency Operating Procedures l l - Safety System Functional Inspection 1 l - Operational Safety Team Inspection - Fire Protection l i - Management Corrective Action Plan (MCAP) .. ',' r"; W - Security o l 01/12/98 _ gggggpglggggg l 19 j l l O

Extent of Condition ySPe t; m s FPC ) CR-3 i Timeline - 1997 SBLOCA Multi-Disciplined Teams System Readiness Review ~ ~ i Configuration Document Integration Project ~ i Integrated Verification j ) l 01/12/98 20

l Timeline of Assessment and Verification Activities Ucensirg Docket Revew i Des.ign i - J S-Readiness 1 P r i \\ Assessment EPN/EDG / l Activities Interjependency l D-16 Aggregate Integrated Verification -3 V LOCA Team A C<xfgurate i f0"" Re-examinaten of Document aggregate of friegratron Project N Soluten Sets desgn issues EOP Safety l l { l Assessment y 3r y 3r y 3r 3r r Sept 96 Oct,96 Jan,97 Feb 97 March,97 Apni,97 May,97 June,97 July,97 Aug,97 Sept 97 Oct,97 Nov 97 Dec,97 l A A >A Shutdown due Organizaten Restart I to Turbine Self bcense Operator p i Lube Od Assessments Requahfecate Defense in Syst*= A m owner *p 1 Depth i Measures oeaateaeac i m Subcommittee for EOPs Safety Analysis Group Reviews all 50.59 Evaluations i 5 i Design Review Boards I G1/12/98 21 i ?

l Q. SBLOCA Solution Sets ^ S%* 4 FPC CR-3 LIMITING SINGLE / FAILURES 1 ? u l ADMIN LOBA j C i l C LOBB SAFETY l ASSESSMENT Lo.s.f "B" Battery I I EOP/AP REVISIONS EFP-2 ITS SUBMITTAL S l FSAR/EDBD REVISIONS 01/12/98 j 22 i

b i i R' LOSS OF EFP-2 i ~~ w,e'Cw j g m s FPC 2 HPl HPI FLOW CR-3 I puMeS ANALYS!Y. l ^ c n S l U l MITIGATION i STRATEGY FRAMATOME TIME C EFP-2-> 2 HPi PUMPS ANALYSIS I EFW FLOW EFP-1 TRIP C r OPERATIONAL LOAD s ~ + DEFEAT - -

  • AND -+ ADMIN LIMITATION MANAGEMENT SWITCH w

m { l EFW ~ FLOW MOD - swsT b MOD (PTL) l DEPLETION i 500 Psig S l (Operator Cooldown) j S i FWP-7 ' -> FWP-7 ---+ DIESEL w MOD SUCCESS PATH CHALLENGES 01/12/98 DEFENSE IN DEPTH v 23 i l f' I

fyFf - _ l' Extent of Condition S&P y9 2 FPC i l CR-3 Reasonable Assurance That CR-3 Will Operate i i Within its Design and Licensing Bases. l t CH-3 Can Mitigate All Design Basis Accidents l Modifications' System Configuration and Focused Readiness Document Review Review Integration of Programs Program Project 01/12/98 24

{ ..- *= I h System Readiness Reviews %'*$O? FPC -Graded Approach Assessment of 105 Systems -Evaluation of Results i -Disposition and Track Restart l [ Requirements \\ -Operations Acceptance of Systems t l -Startup Performance Monitoring 01/12/98 l 25

e t r System Readiness Reviews -y gj{g}ev (Factors Used in Prioritizing Systems) j e i FPC i CR-3 i i

  • Probabilistic Safety Assessment l

i Factor

  • Maintenance Rule Risk Significance l
  • Number of Previous Configuration Changes l

}~

  • Fission Product Barriers (10 CFR 50, Appendix A, Section II) l 01/12/98
  • Previous Assessment Results 26 r

p,= g ! zW)y, W>si a z t ] j= ] g 1. ] 3 i i {.l Ir 31 lI i.l lil h 41] mj -} i _f 1 l 9 i I. f$ h 1 1 t I l 1 j -1: i l 4 f 4 l 6 = ~ l 5f &3 )(

1I e

3 i i N ~1v 3i i _([ i l f' i l l; iI3 h i 1 l i k i 1;, l i l 'I i l = 'Li [. . i! E p. .d i'3 ill l ll I

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. j[ ei 1 l I (l 1. ' l;7 i i h l l ),. i i l f l L l. O?UN e S \\

i i System Readiness Reviews e LEVEL 1 LEVEL 2 bi Reviews Reviews C- ~ j y FPC 1 Emergency Feedwater System 1 AC Electrical Distribution CR-3 2 Emergency Feedwater Initiation & 2 DC Electrical Distribution Control 3 Air Handling Subsystems 3 Reactor Coolant System 4 Nuclear Services Closed Cycle Cooling Water 4 Emergency Diesel Generators & System EDG support systems 5 Raw Water System 1 j 5 Decay Heat System 6 Decay Heat Closed Cycle Cooling Water l 6 Makeup and Purification System System 7 Core Flood System 7 Control Rod Drive System 8 Engineered Safeguards System 8 Main Steam System 9 Waste Disposal System f 10 Radiation Monitoring System 11 Annunciator System j 12 Building Spray System 13 Feedwater System ) 14 Chemical Addition System l 15 Spent Fuel System l 16 Nuclear Instrumentation System 01/12/98 17 Reactor Protection System 28 18 Containment Access j

!>b[t ib ,i; r t ,.;[: -!F[(' t lI .(i! r [: 5 3 r.2:!-[- x x x x x x x x x x x x x x x x x x x x x x x x x z .c :i si - x x x x x x x x x x x x x x x x x x x x x x x x x ~. yi s 2 i!I I5. e4=",o x x x x x x x = s s s = = w = s x = x x x x x x x x x x x x x x x x x x x x y x x x x 2 I. a : i 5 v *; m, g ) i.It [., x x x x x x x = s s s s 4 s s = 3 xY x x x x x x x x x x x x x x x x x X x x x 2 .ea 3 g x x ,,m s 4 2 1aaE ee < x x x x x x x x x x x x x x x x x x x x x x x x x 2 x x x x x x x s s s s s s s s s 2 5 !. 3L :, j3 .s 22 iie. I5, ie2 x x x x x x x s s s s s s s s u s = a s s s x x x x x x x s s s s s i s s s s s s = s s a .a. s!.sts, x x x x x x x s s i s s s s s s s s s s s s = s s s 2 ! ; 2 ! :

  • i,g-

.s s x x x x x x x s s s s s s = = s s s s s 3 i ! i!!:-{ J" L i != i ish e]1 x x x x x x x s s s s s s 4 F ,aI* 1s 3a 1-x x x x x x x x x x x x x x x x x x x x x x x x x u s X s O I R i !i!- x x x x x x x x x x x x x x x x x x x x x x x x x I T s x x x x x x x s s s s = s s = = s A .s.1e i J i R M ~. i =esi!.

i a-x x x x x x

x x x x x x x x x x x x x x x x x x x 4 ) t W J ss 3 su i" :- x x x x x x x x x x x x x x x x x x x x x x x x x i E x x x x x x x x x x x x x x x x x x x x x x x x x l z I s i ei" 5,* l~ V s i, Et.A x x x x x x x s s s s s E i R S i i4 :-,*!.J & c x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x S a=2 =- E N Ij-} x x x x x x x s s s s s s s = s s s s s s s I D x x x x x x x s s s i s s s s s s s s s s s s s A E

.;:?::* I; x x x x x y

x s s s s s s R sia x x x x x x x x s s s s s s s s s s s s s s s a s M E . g: s5; _2s. t* x x x x x x x x x x x x x x x x x x x x x x x x x TS ii :3 :e2 <, - x x x x x x x x x x x x x x x x x x x x x x x x x Y x x x x x x x = s s s s = x s s s S i.i: i3 6 < - .!i.: j 2f}- x x x x x x x = s = s s s = s ) W ) S W ( ) C R gn 3 D ( h k r c 1 g te o 1 ( e o h a C c m t l ) W ) c s ) P lc p o a i ip e c I o I R o A R( S M R e C tot T C y l T ) t ( m d iu n a d k P r s ) A m ) y ( w N c n c D I) e e t e k M ) r o t i F e ) qd T u s l i r s e d t A C o b R y 3 s a ( y S n l t r b D a C m P s r t S a ( ed s v a a ) i a m e i C W r a ) s d e la n A c g ) t s m l w u ft l m e t ) r s o s N r o s D l e l te s s l n s ( e g u t l A ( a b S ) ) S c e s I s y e s d fe g R W M i m i n t o i s n e P n A o ot t e e r u n c s c a o ( y d C l D( F ( c r n e a b t u s R ) d s a d a M o te t e e e a l i H n P n l n o e s I F S o g r r t s u M o i C d m k t n c t ( r e p d A d n y y d a o n t S l le r e o p A a r s s xs r n o h s a c h b le c c e p C e S i t e y e u D n n r d k t t r r r l a o S F e e e u r n g i y le r r r l c c o a n o D w S a a o t tc t t k o a y g g e I e m a E i k e t l u d k t a m t e a r r d n is c c r n r c e e k c l s a n d e c d e a a d a c e c g a u a o e m m n e s n u h e C o e u u e a e u p C D E E E M R A A B C D D R F M A N R R R N S N W 8 9 =m.;; rExg< /29 1 2 / fo j! !l

SYSTEM READINESS REVIEW PROCESS License Design Procedures Configuration r Procedures FSAR EDBDs Walkdowns i j ops /SPs/EOPs ITS ABDs Section XI Open items PCs/REAs/ prs FSAR Ch.14 Commitments Accident Analysis Notices / CMIS Maintenance Bulletins Specifications i Calculations I&C/ Mech /Elec 01/12/98 Drawings 30 i

System Readiness Reviews LEVEL 1 LEVEL 2 LEVEL 3 i 6 l i I i 1 l I f i i 4 i i l i 01/12/9 1 3' 4

i System Readiness Review -s. y%s%7 Attribute Evaluation l gs i FPC 1 l CR-3 Attribute Checks 16044 l i SAT Discrepancy 14520 1524 E Work Controls Restart Process Issue 01/12/98 1149 375 32

W' Extent of Condition pr$i$ (Focused Review of Programs) FPC Integrated Technical Specification CR-3 e - Improved Tech Spec Project (3/94) FSAR & Related Ch.14 Safety Analysis 1 - Safety Analysis 10 CFR 50.59 Reviews ~ l - Integrated Safety Assessment of Outage MARS - Configuration Document Integration Project l l - SRRP Implementation - FSAR Operational Review Design Basis Documentation ~ ~ j - E0P Enhancement Program /g/88 - SRRP Implementation

j Extent of Condition ~

  • * * * ~

m... $1.L$ (Focused Review of Programs) e i FPc

  • Analysis and Calculations CR-3

) l - EFW/EDG Team j Solution Paths Analysis and Safety Assessment = Integrated Safety Assessment of Outage MARS l l

  • Cooling Time Requirements for SBLOCA and Single Failure

- Pipe Support Review Project l [- - FMEA of the DC Electrical System i - Startup Team Validation of Ch.14 Single Failure Accident Sor,sarios - I&C Calculation Upgrades l - Electrical Calculation Upgrades j - NPSH and Tank Calculations j - Instrument Uncertainty Calculation Analysis Program - D/G Load Calculation ~ - Main Steam Line Breaks 01/12/98 34 - Letdown Line Break Analysis

l Configuration Document

==v i n- \\ l &%$ Integration Project e l FPC ] l fR-3 Integration of the Primary Licensing Documents 1 - FSAR - Improved Technical Specification Bases - Design Basis Documents lsed Information From Reviews Identified by the Confirmatory Action Letter - Item #3 l Established a Future Configuration Control .L. Program 01/12/98 35

Configuration Document m Me.t Integration Program j FPC Project Input Information From: - SRR, PCs, prs, Docket Review, j l Independent FSAR Review, j Modifications, Analysis j Consolidate Information Into Specific l Plant System Information Sets Resolve Open Items Update the Plant Documents 'y8 - FSAR, EDBD, ETS Bases, ABD

Configuration Document -Sy)ht Integration Project FPC CR-3 1936 Total Issues Collected i -2966 Document Changes l -1836 FSAR Related Document j Changes i 1131 Total Issues Resolved This Outage -278 Required for FSAR Revision 24 -Translates into 318 FSAR Changes 01/12/98 l 37 4 m

onfiguration Document Integration FPC There Were 75 People involved, ' " ~ l i With 35 Full-Time at Peak ~ l Project Steering Team ~ i - Department Managers From l ~ Operations, Design, Systems, Licensing j System Ownership Teams Three Project Managers With l Extensive Operations Backgrounds oifi2 fos l 38 1

Configuration Document r-4.)m;w Integration Project y e FPC CR-3 j FSAR SRR Docket Review Review 1 i Corrective Modifications Action l p-j Program \\ \\. I \\ Sple / Technicai 1t informatipJl,0 i i g / Resolut, ion \\ .l i i _ _i r 3 l l Document Integration Group } 01/12/98 y y j 39 l l 1 i l, f

E Document Integration Group 4 l FPC eac CR-3 Decay Heat Make Up gg ant Safety Emergency Engineered Support Diesels Safeguards S Building Emergency VenMation Spray Feedwater i s u _mm x-s j Central t Location i [hdk Tech Spec I ~ Procedures Chapter 14 E and EDBD and ABD Bases 01/12/98 r; Databases l ~ ^"' T' ~~~"' - ~. -. _.. _

l onfiguration Document Integration i i I l Collection of FPC system CR-3 '"f "" ti " integrate information by system in central location l i Deve!op r Licensing Basis by system Integrate Plant i System Ownership Licensing Basis Teams Acceptance b _m: R:2M Documents 1 Overall Integrated 'j e canon 01/12/98 41

i m ;v Configuration Document &SI'" Integration Project w7, l FPC CR-3 FSAR Change Distribution by Chapter 125 - DMARs g E 100 - j ELARs j L Precursors j s 1 8 75 - 23 o I 24 l ie-E5 o 50 - ls as 2s b 15 8 8 8 17 10 3 i E 25 - i o m, as 4 2 j s m* o 2s is 2i 2i 2s 4 _o q 0 1 2 4 5 6 7 8 9 10 11 14 i 01/12/98 FSAR Chapter 42 i l

i agg FSAR Update y ~574,- FPC I CR-3 l Updated for Plant Modifications Emergency and Abnormal Procedures Rewrote Small Break LOCA Section i Validated Accident Analysis Chapter Integrated 850 Corrective Action Changes l 01/12/98 43 l l

I y y + 7 g tl I 7 Integrated Verification hpi m FPC CR-3 Final Focusing of the Activities Was j 5' l Performed in the Integrated Verification - A Team of 6 Multi-Disciplined, Experienced Staff ~ l - A Qualitative Lock Focused on the Impact of = Outage Activities on Operator Burden l l EOP Revisions Modifications i h h 1r 1r Key Issues FSAR Chapter 14 i 01/12/98 44

I Integrated Verification w^ l & L *' Conclusion

..c FPC Of the Restart Modifications, Over 20%

ca-3 Directly Enhanced the Ability of the Operator j to Physically Operate the System - EFV-12 EFW Crosstie FWP-7 Standby Diesel Power j i i - HPI Recirculation to Sump EFP-1 Trip Defeat Switch - RWP/SWP Pull to Lock Switches Letdown Line Valve Addition RB Fan ES Logic - FST-CDT Crosstie - MUV-27 Auto Closure 480 ES U/V Lockout - CREVS MUV-103 Replacement - 2 Modifications Greatly Enhanced the Main Control Room Environment 01/12/98 45

2"" Jr Integrated Verification S&P~ Conclusion I-FPC i CR-3 l

  • Balance of Modifications Brought the Systems Into Compliance With

~ Design and Licensing Basis l

  • The Systems Now Will Operate As l

Expected by the Operator Under AII Conditions i 01/12/98 46

i -7, Integrated Verification e-gp ( Conclusion) m FPC CR-3 l "..the overall effects of the modifications and procedure changes j enhances the ability of the operator to prevent and mitigate accidents. There is also an obvious increase in ~ l the knowledge level of the staff, most notably the system engineers, i operators, and design engineers." 01/12/98 47

perwes.

Licensing Challenges w% % e"- i i I FPC CR-3 "Non-Traditional" Approach for i Complex Licensing Submittals l - Crystal River 3 Addressed Several Generio Industry issues Design and Licensing Changes ~ Were Greater Than Typically i Experienced 1 Seconded Organizatiort Support 'H8 l

i i "Non-Traditional" Approach l g*~4+g for Complex Licensing Submittals FPC j CR-3 Approach -Submit Concept With Identified l " Gaps" i > Complex Issues ~ l - Follow-up Technical Briefings ~ -Submit Preliminary Analysis J -Complete the Submittal -Objective: No Surprises i j 01/12/98 l 49

Crystal River 3 Addressed l

cys, g* e,

Several Generic Industry Issues FPC j CR-3 l Lack of Industry Model for 1 -Boron Precipitation i -Mode 4 Small Break Loss Of Coolant Accident i -Generic Letter 96 Containment Penetrations 1 Hot Shorts" Under Information Notice 92-18 l 01/12/98 50

r E,,, Design and Licensing Changes ~~ Were Greater Than Typically Experienced FPC CR-3 Historical Approach to Resolving Issues - Boron PrecipitaHen j - USI A-46 c> Decay Tank Supports - Emergency Diesel Generator I_oading - FSAR Revision 23 i l - HPI Crosstie l - Emergency Operating Procedures (EOPs) Relatively Short Timeframe From j g'88 Identification o Resolution of Issues i l

Seconded Organizational l Sylt Support FPC CR-3 l Multiple External Organization i Interfaces for Issue Resolution l -Coltec, Sargent & Lundy, Framatome, I l and FPC C Emergency Diesel Upgrades l l -B&W Owners Group, Framatome, and i FPC o E0Ps 01/12/98 52

Seconded Organizational e-Support FPC l CR-3 l

  • Engineering and Licensing l

Organizations l - Engineering Q150 FPC,190 Contractors l - Licensing C 20 FPC,34 Contractors Multitude of Organizational l i l Communications to Resolve Issues Organization Changes l 01/12/98 53

Technical Issue Timelines Q'-s-, -P I FPC l ca-3 l_icense Amendment l Topic Hequests (IARs) l 1, Emergency Diesel Generators 215,216,219 Emergency Operating Procedures l Small Break LOCA 210 i l Boron Precipitation 220,223 l Control Complex Habitability Envelope 222 j USI A-46 / Large Bore Piping Jet Impingement Letdown Line Rupture 218 01/12/9s low Temperature - Over Pressure 213 l 54 I

l l wew Licensing Timelines w%$e 5 P l l FPC i CR-3 l Topiq LARs l Post Accident Monitoring 209 l OTSG Surveillance 211,221 l Appendix J, Option B 212 ~ ECCS Mode 4 214 Reactor Building Fan Logic 217 NSCCC Overheating 224 Appendix R, Fire Protection 01/12/98 55

Small Break LOCA (1.AR 210) i 1 was F i J { J A l 5 l O j f l W j A 1

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m-cce.oi ute r +[ p[ s* gg,, mm.wg a-o t m c Decers [" y R8 EOPS + E1. -T .EoG asc=e .w.e.o j i.- - EF 9 cuesung wress O - EFC range **ee **=r C stm **= w wee <ses tT2s J {'.;' _ O 6% T2 8888* w,m N EDG or W <*2r*b-Tscan ao outage mode.ceens_ - u ~ ~,--*--~a,,%,y,,,,,,g,ygy ygg>J Q EFPs'*3m mecaser*Q ('. p ~~ ~ PW W **8N ***NG. to.s a m ES asce C -EDG w'st tuo m acesQ EDGmopernamacato. O h. - M P0* 9' N IMS W nae a l'J [Sd ]j EDGreessy e Q ys - EDG Des **W.aC A Q L .anunne 01/12/99 56

qvew?% ~ Quality &Det ...c. FPC CR-3 Actions Taken to Address Quality: l l -Hire New Licensing Manager l -New Engineering Managers and Supervisors -Performance Issues Identified l -Revised Standards on Content i j - Additional Senior Management tnvoivement ,,,12/98 57

i p : -- ~r Quality Index m y%5i" .y l gc Objective - Improve the Quality of Licensing l Correspondence to Approach l L- "Zero Defects" Elements 1 j - Organization and Clarity ) - Technical Content - Timeliness l - Need for Supplement i Calculation i - Maximum 8 Points, Minimum -2 Points 01/12/98 - Monthly Index is Average for Submittals 58

Discussion of Quality Index 50 i = 40 ~ \\cceptable 37 37 + 35 3, 29 + 30 = = ] 25 maoutine + 24 + + n + 20 is + + muas + 15 .novs 10 , O LERs 10 A+ ~ ^ ~ l i 5 + j + - l+ + i i 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec C1/12/98 ( 59

NRC Re4uests for Additional &RP, Information (RAls) c FPC

  • Summary - Third Party Review CR-3 i

l h. - RAls Not Unusual for Number and Complexity of Issues i l - Balance Between Timeliness and Completeness Reasonable l - Accessibility to Technical Reviewer i l Improved Understanding I - Documentation Quality is Being j Addressed l 01/12/98 l 60 1

i NRC RAls ^~ S)g Third Party Review FPC CR-3 Reviewed 33 RAls from January l 1997 to December 23,1997 -19 RAls Since November 1 - Addressed 18 Broad Topics -Contained 143 Questions Lessons Learned Fell Into D 11 Categories l 01/12/98 i 61

l NRC Requests for Additional "~ " m l JhRf Information (RAls) m, FPC issue / IAR

  1. RAls
  2. Questions Month (1997)

CR-3 NSCCC Overpressure 1 6 Aug [96] ~~ RCS Piping 1 1 Apr Reporting 1 1 Jun j MUV-64 1 2 Dec USI A-46 / Large Bore Piping 3 29 Jan, Dec (2) l Jet Impingement 2 4 Apr. Oct l OTSG Tube Rupture 1 1 Dec Appendix R 3 5 Mar, May, Jul 209 1 3 Oct 210 7 46 Sep, Oct, Nw (3), Dec (2) l 211 1 6 Jun l 213 2 15 Aug, Oct l 218 3 15 Oct, Nov, Dec i 219 1 4 Oct 220 2 2 Dec (2) l 222 1 1 Dec j 223 1 1 h 01/12/98 224 1 1 Dec 62 Total 33 143 i i

NRC (RAls) e. Sk d Third Party Review e FPC CR-3 Categ0ry Number Additional Detail to Justify Position 33 Respond to Generic issue 27 Information Available 19 Change or Supplement Commitment 13 New Topic Identified 13 Reconcile Design and Licensing Basis 10 a i j Demonstrate Compliance with Requirements 9 l Documentation Weakness

  • 7 l

Provide Plan for Closure 6 Correct Quality of Submittal

  • 3 l

Correct Responsiveness of Commitments in Submittal 3 i Total 143 l 01/12/98 63 i

Organizational Roles in m &8%.t Submittals c FPC CR-3 l

  • Licensing

- Quality Assurance Safety Analysis Group (SAG)

  • Plant Review Committee (PRC) i Nuclear General Review Committee j

(NGRC) l ~

  • Line Management 01/12/98 64 j

n o

Status of 50.54(f) Letter %)? Initiatives cp FPC i Initiatives / Improvements in 50.54(f) Letter j c R-3 Were Addressed - As Stated in 50.54 (f) Letter l - With More Actions Than Stated in 50.54(f) Letter l - With Some Minor Changes to Details Stated in 50.54 (f) Letter l ~ ~ Additional Initiatives Added Since l 50.54 (f) Letter - CDIP - Configuration Management Enhancements - Additional 10 CFR 50.59 Improvements 4 o/y/98 - Corrective Action Program

l Operations and m,., l S)2 Engineering Perspective l FPC i CR-3 People - Training i - Involvement i Plant - Backlogs i - Hardware Processes i - Assessment - Work Controls l 01/12/98 66 L I

we, Conclusion w%N'I e FPC l ca-3 . FPC Determined and NRC Has 3 l Formally Reviewed and Found l Satisfactory: l 1 -Corrective Action Program - -N - Root Cause Program x l E - 10 CFR 50.59 Process .,( - NR_0 Restart Issue Closure - Emergency Operating Procedures 01/1M/69. 6.

we Conclusion c FPC "~ l = Resolved Multiple Obstacles to Technical Issues WITH OveraII Approaches Remaining Intact 1 i- - Reduced Operator Burden -Increased Margin - Improved Defense in Depth - Resolved Long-Term Issues - Enhanced Reliability 01/12/98 68

Conclusion O'?l0 gS Adequately Addressed NRC Questions on Submittals = Validated the Process of " Extent of Condition" and " Resolution of Issues" -Extent of Condition - SSFI 01/12/98 69

3 ggys.p. Conclusion 58$ r FPC CR-3 FPC Considers Confirmatory Action Letter Items 2 AND 3 . Adequately Addressed 01/12/98 70

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I 2 Acenoudedge SER on seaponse spectraffurthee cienrcaten N C M2% i r 526/93 RAsehng ~vnessen(52ES3) Response to FPC _ RAI for teor response g gym G SIC mopense - ope @a f 993) g3g7} I*N l SER 8er fire, NRC 7 g\\ g{ spectrum (12rif M r i NW letters' b Cormne .a

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Control Complex Habitability Envelope (LAR 222) 1994 1995 1996 1997 3999 l l l l l J F M A M J l J A S 0 14 D 95-02 ' 09 95-21, tlRI 97-C5 (Cat:s) -'747 97.t3 (272) Fl7) (2.76) (62) E#I (10!16) Insp. X7 \\"7 x V7 s Reports is' 23' 'b " 94 25 (12/20) - pt24) 16 5 weetng. Nsin teg cel (11 (10'31) 812 1 -"**"P'* 81 ,,7,,,,, Res:.,t p. ei tee t., Meetings /, \\/ X7 Telecons 6 Res,, C '5C"" 20' tER 95 0. ei _ -aR 9s49 ,,,20

==*=; wm ,e,,,,,,, I I TSCAN 209 LER 97 22 _ LER 97 22-01 LAR ??' LER 9410 ~ ~' ""d 077) Sd ~ w,% g,p (12/23) CCwEiCRE vs a -es.*e -a tu r O'"** *** Submittats-L1 L's U7-X7 T7 T7 XZI7 X7 X7 X7 "5 5 A a y JCO LER 96 04 Test resorts f2'28) HMS ~ 12'15 _g,,,,,,,,,,, CCHETREvs R AI en R At en NaC st peevat LE?:5 10 WCA* st atten .Operenet, tese et 3 0 3) Letanen Lee - - CCNE - e4 L AR 222 plan i 22 9 ,22. ,,, R., ) NRC, 57 57 X7 m letters tets ion 2 testaR westeutes ~ ~ Ieat sese - Instati nee ese Ternever to Reces9, start pt97) de w s Optet ons Plant \\/. UP9'aoe gm.,, Mods ~ "**"""' \\ A i 7 X7 ine .t st (617)

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i g.- d Emergency Operating Procedures e [,, 1988-90 1991-96 1997 l 1998 f l f f~M l l j l F O l l J M A l S l D. J J A N 996 850* 's ($1795) {' ' esp (2r1094; - ,,y,, 93-16 (91296) 6 i p20093) 9515 97 4 97 M 9712 rA (11/27.96) (4ft7/97) (711697) "m p NRC \\k/ $\\ b / g\\/ \\/ \\/' + insp. Yeween. Hismert factnrs Tem Numan Factnes ~vewowett2m fuen.mer (11/28) MueW9

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