ML20206D776

Summary of 881102 Meeting W/Util in Rockville,Md Re Facility Operating Performance.External Performance Assessments, Performance Indicators,Mgt Initiatives & Feedback Effectivness Discussed.Agenda & Viewgraphs Encl

ML20206D776
Person / Time
Site:	Perry
Issue date:	11/08/1988
From:	Colburn T Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8811170271
Download: ML20206D776 (63)

Text

_ -.

4 tiovember 8, 1988 Docket No. 50-440 Distelbut<on-

poczet n es $

OGC 4

"NRC T Local PDRs Edordon PDIII-3 r/f BGrimes JHannon ACRS(10)

TColburn JClifford PBoehnert LICENSEE:

The Cleveland Electric Illuminating Company FACILITY:

Perry Nuclear Power Plant, Unit No.1

SUBJECT:

MEETING

SUMMARY

- NOVEMBER 2,1988 MEETING TO DISCUSS PERRY UNIT 1 PERFORMANCE On November 2,1988 from 9:00 a.m. to 11:00 a.m., representatives from the Cleveland Electric Illuminating Company (licensee) met with NRR senior management to discuss operating performance for Perry Unit 1.

The licensee discussed external performance assessirents, perfonnance indicators, management initiatives and feedback effectiveness, among other topics.

provides a meeting agenda. Enclosure 2 provides a list of attendees and provides a copy of slides used by the licensee during their presentation.

NRR senior management and staff welcomed the licensee's presentatiun and indicated that many of their programs and initiatives appeared responsive to the operational problems experienced at Perry during 1988. The staff expressed some cautious reservations at the ambitiousness of the upcoming 3-month outage schedule, however the licensee representatives assured the staf f that the schedule was well thought out, adequately pre-planned and very realistic.

/s/

Timothy G. Colburn, Sr. Project Manager Project tirectorate III-3 Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc: See next page Office:

LA/PDIII-3 PM/PDIII-3 P sP !!!-3

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Y Executive Summary - Ferry Ferformance Review Movember 2, 19HH o

A number of major o*stside assessments have been conducted since we received our full power license. each with acceptable results. These included the NRC OSTI and Maintenance Team Inspections and the IMPO Operating and Assist reviews.

o Common weaknesses included:

A more aggressive attitude toward root cause analysis and corrective actions on non-i.ER events was needed (leproved programs in place).

Need to reduce large backlog of Freventive and Corrective Maintenance. (Rave accomplished this objective using the 13 week rolling schedule).

e Strengths include:

Strong commitment to personnel training and development.

Ve!! tounded system engineering concept.

Competent plant staff with adequate resources o

Significant initiatives to strengthen weak areas Evaluated operator performance as well as management involvement and oversight.

Developed I.ER and Scram Reduction programs.

Initiated Boot Cause Analysis leprovements.

Completed Maintenance Self Assessment and currently toplementing resulting corrective actions.

Strong Self Assessment Erograms e

Monthly Ferformance Report / Top Management Involvement.

GA performance based Audits and Serveillances.

Trend reports on corrective actions programs.

Quarterly OA Assessment (self SAI.F).

o Managceent commitment to a conservative operations philosophy and aperating excellence.

Conservatise exists in our operating programs and our routine day to day operations.

Vorking to leprove non-routine operating decisions.

1

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NOVEMBER 2,1988, NRC BRIEFING

- OPENING i

- INTRODUCTION

- OUTSIDE ASSESSMENTS

- PERFORMANCEINDICATORS MANAGEMENTINITIATIVES EFFECTIVENESS FEEDBACK: MANAGEMENT SELF ASSESSMENTS 1

SUMMARY

AND CONCLUSIONS l

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CENTERIOR ENERGY CORPORATION Centerior Energy Corp.

Chairman and Chief Executive Officer R. A. Miller q.

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President and Chief a

Operating OITicer R. J. Farling l

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r Toledo Edison Cor..,any Cleveland Electric President Illuminating Company M. R. Edciman President L. C. Phillips t

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Vice President-Nuclear Operations Vice President Vice President-Nucicar j

D. C. Shelton W. D. Masters I

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Management Philosophy Conservative, Cautious Approach to Plant Operations 4

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- Take Deliberate, Meaningful Actions to Plant Problems i

- Engineering Onsite Since 1978 4

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- Open and Upfront With NRC

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INTRODUCTION T

Organization Plant History / Milestones Management Initiatives E

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PERRY NUCLEAR POWER PLANT ORGANI7,ATION

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Nuclear Group Vice President

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Perry Plant Technicah Assurance Dept. Director Dept. General Manager Dept Director E. Riley S. Kensicki M. Lyster j

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- Jul 1987: SALP 7 Received

- Sep 1987:INPO Annual Plant Evaluation Nov 1987: Commercial Operations Jan 1988: Maintenance Self Assessment Completed Jan 1988: NRC Maintenance Inspection Mar 1988: NRC OSTI Jun 1988:INPO Special Assist Jul 1988: SALP 8 Received e

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r Outside Assessments: Common Weaknesses and Strengths Weaknesses

- Plant Personnel Are on a Learning Curve

- More Aggressive Attitude Toward Root Cause Analysis and Corrective Actions Was Needed

- Scheduling and Coordination Need Improvement to Reduce the Large Backlog of Preventive Maintenance Tasks and Corrective Maintenance Work Orders Strengths

- Strong Commitment to Personnel Training and Development I

System Engineering Function Appears to be Generally Well Founded and Administered

- Plant is Staffed With an Adequate Number of Competent Personnel to Effectively Maintain the Plant and Operate it in a Safe Manner e

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Management Initiatives Evaluated Operator Performance as Well as Management Involvment and Oversight Developed LER and Scram Reduction Programs Initiated Root Cause Evaluation Improvements Completed Maintenance Self Assessment and Currently Implementing Resulting Corrective Actions 6

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OUTSIDE ASSESSMENTS NRC SALP

- INPO Annual Evaluation

- NRC Maintenance Inspection NRC OSTI l

- INPO Special Assist NRC Pilot Requalification I

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- INPO Training Accreditation

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COMPARISON BETWEEN SALP 7 AND SALP 8 Functional Area SALP 7 SALP8 Plant Operations 2

2 Radiological Controls 2

2 Maintenance 2

2 Surveillance 2

2 Startup Testing 2

1 Fire Protection 2

NR Emergency Preparedness 1

1 Security 1

1 Outages NR NR Eng. & Technical Support NR 2

Quality Prog & Admin Controls t

Affecting Quality 2

2 Training and Qual Effectiveness 2

2 Licensing Activities 2

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Fr-p INPO Annual Evaluation (Sept 1987)

Overall Plant Evaluated as Category 3 Strong Management Commitment to Personnel Training and Development

- System Engineers Are Very Involved in Support of Control Room Operations for Their Atsigned Systems Some Problems are not Resolved in a Timely or Complete Manner Corrective Actions in Response to In-House Events are Often not Effective Improvements are Needed in Scheduling and Coordination to Reduce Large Backlog of Preventive and Corrective Maintenance

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- Control of Temporaq Changes to Plant Systems and Equipment Needs Improvement e

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NRC Maintenance Inspection (Jan 1988)

I.ireshold for Generation of Work Orders was Sufficient Priority of Maintenance Tasks Adequately Tracked; However, Documentation not Effectively Implemented

- Management Attention Adequate-However, Lack of Documented Technical Assessments When Rescheduling Repetitive Tasks 1

Maintenance Self Assessment Indicated Positive Steps Toward Improved Maintenance b

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r NRC OSTI (MAR 1988)

- No Significant Problems in Transition From Construction Phase to Operating Phase Perry Has Implemented Sound Programs and Procedures

- Plant is Staffed with Adequate Number of Competent Personnel Plant Staff Exhibited Good, Positive Attitude and, in General, Worked as a Team

- Plant Personnel Still on a Leaining Curve

- More Aggressive Attitude Toward Root Cause Analysis and Corrective Actions was Needed b

F r

p INPO Special Assist (June 1988)

- Root Cause Analysis for LER/ Scram Events is Generally Good

- Analysis of Condition Report Events (non-LER) Not as Good as LER Investigations; Requires More Formal Documentation Action to Improve Root Cause Methodology; (Training, Deskguide) on Right Track

- Unit SupervisorWork Load Appeared Burdensome Shift Supervisor Involvement in Plant Operations Should Increase Policy Regarding Procedure Compliance Needs Reinforcing e

4

+

NRC Pilot Requalification Feb 1988-Perry Selected as Region III Pilot Plant for Licensed Operator Requalification Program

- May 1988-12 Personnel (7 SRO/5 RO) Participated in Requalification Test Program

- June 1988-Region Ill Notified Perry That Requalification Program Passed All Evaluation Criteria

- Pariticipation in Program was Taxing but a Worthwhile Effort e

6

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INPO Training Accreditation I

Aug-Sep 1987-INPO Accreditation Team Onsite to Review Licensed, Non-licensed and Chemistry Training Programs Jan 1988-INPO Accreditation Board Grants Accreditation of Operator and Chemistry Training Programs Feb 1988-Final Set of Training Programs Submitted to INPO for Accreditation i

Mar 1988-National Academy for Nuclear Training Officially Recognized, Accepted and Accredited Perry's Four Programs Reviewed in Aug-Sep 1987.

Jun 1988-INPO Accreditation Team Onsite for Preliminary Review of Remaining Training Programs i

INPO Accreditation of All Other Areas on Schedule for Completion by Nov 1988 6

6

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PERFORMANCE INDICATORS

- Availability and Core Energy Utilization Scrams and LERs Work Orders and Preventive Maintenance Control Room Instruments / Annunciators Out of Service

- Personnel Cumulative Dose

- Effluent Releases / Liquid and Gaseous

- Losses of Safety Systems

- DieselGeneratorReliability Open Condition Reports

- Reactor Coolant Chemistry Out of Specification l'

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Equivalent Availability Factor

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This is on INPO Performance Measure NOTE: Values shown are cumulative 100 95 GOAL 90

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I I Pf'RRY NUCIIAR r0UG P!Afr l raroemCE wr.uRErmS I roR mNm SErrrmER CTIPffROL ROOM INSTPtMDfTATION OUT OF SIT.' ICE: l j Tte number of instrwwnts in the Control Room, including annemelators, that are out of service or not functional l at ennth's end. INSTPtMNTS DESO!PTION IMPACT ON PLANT STATUS /CDPr9ffS

1) M64-R617 Fecorder VO 87-7903 + 4 ten to repair per priority 3A. DCP 88-264

) to replace oe,$ ete recorder. Est. completion 3-9-89.

2) D21-R360 Fecorder Chart drive brok,- WO 88 4485 can be worked. Recorder to be NTP from thit 2 FJgg to reissue parts Nos.

3) D17-R200 Fecorder Chart drive brnbe. Parts on order U0 88-1870. Est.10-1-88l l for parts.

4) E31-R616 Fecorder Chart drive broke. WO 88-3855 to be issued. Parts l restrained.

I I

3) P44-R475 MFP imbe Oil Teep. Control l Incal, manual control required. DCP 85-110 priority 50/89 i

l l l 6) P45 ): E7J Flow Monitor Requires use of alternate means to estimate flow. i i DESCRIPTION IMPACT ON PtAffT STATUS /CDOWENTS g I I i j l 1) P601-17-B1 l Separator Storage Pool s 1 A(B) l Upper Rx Fool Alarm, DCP 86-%1. Development of DCP i j (P60i-20-B2) l NI/tA 86-%1 (4D/89 outage) to add new upper pool level ir.strumentation may be restrained by the need to access { j l the upper containment raceway design per SED Dats Code D06. i )

2) P601-20-F1 ESU From ECC MK A(B) Fiov lov l In winter mode alarm is locked-in. No problem in summer l

i l (P601-17-06) 1: mode. Need forcast for DCP issue. I i 1 1 I 1 I I I I i i I 1 l l 1 I I i i i l

4 l PERRY NUCIJAR POVER Pl#rr PERFORMANCE MEASURDerrs L FOR MortlTI SEITENBa l COPTIROI, ROOM INSTRUMENTATION OlTP OF SEVICE (COPrr.): The number of instruments in the Control Room, including annunciators, that are out of service or not f1.ne t icial at month's end. DESCRIPTION G F CE IMPACP ON FIAPfr STATUS /COMMDirS

3) 2680-2-B2 IP Cndr L-vel Hl/lo Setpoint change approved and implesmented. VO 88-1787 to determine if sensing lines are installed properly. Plant shutdown required to do che inspection. Forecast completion to be the Tiefuel Outage.

4) P680 4-A2 Recire A(B) l'rg 011 Level Hi Alarm locked-in when running fast speed recire. pumps.

(P680 4-A11) I l Unable to perform during (8f) outage. l

5) P680-7-Cl2 l CIE Tover Acid Trh1 Incal panel needs reset capability. Design Change approved l

and avalting implementation. Spec 86E, contact J. Staffiera, l I&C retest only. DCP 87-731, Wo 88-2988 (Priority 4C/88 l Status 25, Restraint 11). I I

6) P680-7-FB l CIE Tower Chlorine Trb1 local panel aceds reset capability. Design Change approsed l

and avalting implementation. Spec 86E, cor. tac: J. Staffiera, l I&C retest only. DCP 87-731. VO 88-2998 (Prierity 4C/88 l Status 25, Restraint 11). i I

7) P680-7-E9 l CIE Tower Dechlorine Trble local panel needs reset capability. Design Change approved i

and avaiting implementation. Spec 86E, contact J. Staffiera,i I&C retest only. DCP 87 731. VO 88-2998 (Priority 4C/88 l l Status 25, Restraint 11). l l 1 I

8) P800-2-C3

. Comp Cas DV Purge to Annual Flow High l Design Change in progrest, DCP 87-793. Priority is 4D/IP. l i i l l l Need parts ordered. l l l l l 9) P870-5-D2 Feedvater Turbidity Hi/to l Setpoint review required. I i I i l 10) P870 7-Al l CRD/RCIRC/RUCU Dissolved 02 High l Setpoint cnange revi - in progress. SCF. O vas l l l l initiated 4-8 88. l t i i I

PFRRY NUCLEAR POVER PIJWT l PERFORMANCE MEASUFJJENTS l FOR I!OflIH SEFFEMBER CONTROL ROOM INSTRIMENTATION OUT OF SDtVICE (CONT.): The number of instruments in the Control Room, including annunciato s, that are out of service or not functional i.t month's end. DAF ESOtIPTION IMPACP ON PLANT STATUS /COMPENTS

1) P601-18-C2 Valve Stem Irak-Off Temp. P865 Recorder needs ability to bypass one or more high inputs, currently requires ILF to bypass. DCP 88-155, U0s 88-5210, 5211, 5212 to correct. All UOs are Status 10, Rest. 11.

No PO yet for necessary parts.

2) P601-22-A3 Dryvcll Temp Hi Replace recorder per DCP-88-136. VO 88-6191 Scheduled GWK of 4th Quarter.

l 3) P601-22-F2 CRD Pump A(B) Trip 011 Pressure lov Need to bypass lov oil pressure alarm for standby pump. (P601-22-F3) DCP 87-680; I&C retest only. Uos are 88-5537 (Status 35, and 88-5538 (Status 25), need parts for cable pull.

4) P680-1-A6 Dump to Condr/Rv Press Hi/Lo Alarm lxked-in. DCP 87-301 is OATS Code E01 EDCR at NED l

L for Manager approval. Avait' y action by NED. I I I l 5) P680-5-C7 l N2 Tank Pressure lov l Tank not being used. Vork Order to find system leaks l l in progress. Contact P86 RSE, Salkievicz. I

6) P680-7-C9 l Main (and RFFT A, B) lop Trbl Alarm design incorrect. UOs 88-629, 630, 631 DCP 87-543 (P680 7-C10) l von't work. NED aM IM: are working jointly on resolution.

l (P680-7-C11) l VO 88-631 has been rescheduled by URC. VO 88-631 modified 8 l so as to permit disassembly of switch. i I l 7) P800-2-F4 l Comb Cas Mixing System Comp B Flow lov DCP 87-646 DCP is E03, at NED for detailed cost estimate. l l Avaiting action by NED as of 8-30-88. l l 1

8) P904-1-F2 l CVCU Surge Tank B tevel lov l The B surge tank is not currently used for Unit 1, Design l

l l Review in progress. I I I I I i l i i I

PERY NUCEAR POVDt Pl#fr l PEFREW MFASURDfDfrS FOR MONTH SEPTEMBER CDPfrROL ROOM INSTRtMDfTATION OUT OF SERVICE (CGir.): The number of instruments in the Control Room, including annunciators, that are out of service or not functional at month's end. l DESCRIPTION IMPACT ON PIRfr STATUS /CDMMDFTS g I

9) P904-2-C7 CCCU Chiller C Trip ECC Flow lov l The C Chiller is not used for Unit 1.

DCP 87-0709 is V15, I vos 88-5542 (Status 35. Priority 4D IP, 88-5543 l l (Status 35-11), and 90 88-5544 (Status 30) have been created, l l I&C retest only by Maintenance. l I;

10) P906-C3 l RU Disch/Isol, RU to ESV Radiation Alarm design incorrect. DCP 87-713 at NED for detailed I

l Monitoring Flov Hi/Lo cost estimate. OATS Code E03. Avaiting action by NED. I I I I I I \\ l l I 1 I I I I I I I I I l 1 I I I I I i l i i l l I I I I I I l l 1 1 I I I I I i i i l l I I I i l l ) i I i l I i 1 i i t a I i

Collective Unit Radiation Dose NOTE: Values shown. ore cumulative g i Mon-Rem NEG. RANGE l 200" M 190 ACTUAL 170' 160 150 140 130' 120 110 100' 90 60-70 60 50 \\s I O!l!!!lill!!/

Liquid Radioactive Effluent PERCENT \\ 80 d 'N 'N I 70 [ N's M TOTAL BODY j (N F 'lORGAN BODY s 60 d ] ANNUAL LIMIT -l ""- ADMIN. LIMIT .i 50 ? hs ..s s z i 40 xN'c'<s'. s - N ) 30 l '. ~. 'd'd.c'q$'N i

,794 s.s A,

) 20 j 10 _y 0 '~~ $ f$ $ hh$ ,S' l? o o o si 4 u$ 3 ,E 5 n o x o

0 a O se!! !a \\ / s is i /, / iet it i / IE ! \\ f/' \\ } \\ wg % .2 \\ \\ wws 'er W i e i \\ WE/4

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s % Loss of Safety System Function 'oss of Safety System Funcilon 6 l 5 4 c,n -- ~ tio of Events [ '/ 3 (anckxhsw) f1CIC) g. h,,,,7b 2 P b.i ' s Z-- e e e 'e e e + e PF On 8t/ es s 88 01 88 03 Quantors Ines of Safety Sy=tm Categories 1. Airladt Pr41- (4) - In all cases tim ewrits wre within the cristirg Tednical Specification theses (i.e. allowed door quri for I hour to fix inoperable doce). 2. Omtaisuurit Isolatini blve Proble (5) - 3 IIRT falhses, j 1 EIV Solamid probim j - 1 persumel error l 1

3. Stardy I.iqidd Omtrol (SC) (2) - In loth casrs systdus wre restons! vithin times rapimd by Tednical Siecificatim Acti<n Statemmts for SC.

) ) 4. Omtrol Room HWC (2) - Both tims wre eqidgurnt problems with suert systms (chiller). I 5. Diesel Gmerator (TW)/IECS (2) - nts hai c-mtrol air valve pnblem (crreservative call en americ problas dddi onlaimtal in cruplete rulesign of air control portion of WG. - EII:S - Guracrvatively calla! IIICs inopesable dum a run-Tednical Specificatim irr:tnment bncame innperable.

6. Others (1)

s FtrstOverter/ly

1. Both Dielslea I and 2 D/cs inoperable for 6 houvs and 36 elawtes due to control air *alve problem.

2. Containment atelock - enter daar was opened f ar approwleately 5-6 etnotes, while faaer door was declared inoperable.

Second Ouarter/19EF

1. Seth erstas of Standby Liquid Control (514) seke inoperable during serveillmace testina. for apprestaately ? howes. 35 =tnutes.

Third Ouarter/1987

1. Two manual Fire Protection enntainment teolation valves left open during plant opetations troe June 22 to July ).

198?.

2. Three P51V Itses ewceeded allowable leakage limits.

3. Drywell inner door opened for about 2-3 minutes while outer door declared Snoperable.

4. Mole stemellae B inoperable - inhoard M51V had stem separation, outboard M51Y failed LLRT.

Poorth Omartert19EF

1. Three M51Vs exceeded Technical Specifiention closure times.

First Omarter/1988

3. Centainment Isolation valve failed Local Leau pate Test enco ding allowable secondary contanneent bypass leakage.

Serend Omar(er/19AS

1. Both trains of Centrol Room ItVAC Emergency Rectrewlation Mode become taeperable for 2 hours and 50 stautes.

2. WPCS declared looperable due to failed transmitter monitoring for RFCS line break for 19 hours and 20 einstes.

Third Omarter/1988

1. Seth trains of Standby Liquid, Control inoperable due to operator error for 1 hours and 20 minutes.

2. Upper Inner Cantatament Air lock door opened for about 3 minwies to permit teche.cisa to esis. while outer door was inoperable.

3. Upper inner alttock door seals deflate ( for about 30 seconds while outer door was open (inierlock malfunction).

4. M51Y isolattaa signal not yeceiaed for channels B&O with condenser wactrum below trip setroint.

Fourth Ouarter/1988

1. Both trains of Control Room flVAC Emergency Recirculation Mode were inoperable for 51 annates.

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CONDITION REPORT RESOLUTION TRENDING TOTAL OPEN AS OF 9/30/88 = 123 i 2261 l ~ CLO'ID CLCC.ED i ES AITHOVED/C A Iffi 'IltB i 50-- /' E5El ArTwovtD/ovErac CA o E LNAf4 ROVED U 40-5 v3 30-z Q 2 20- / m // gx,..., ik$,fd$ O \\ [ / CALEIOAR MONTH I 2

Reactor Coolant Chemistry Hours Out-of-Specification IM1 TOYAL HOURS NEG. RANGE f 200' E i 110' 100' j 90 l 80 l 70-l x 60 50-NN 30 l l 20 l 10-9lrE,f,f f f l l l i 1 9 1 e a e

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Fr 4 MANAGEMENT INITIATIVES - Maintenance Improvement Program LER Reduction Initiatives Scram Reduction Program Annunciator Improvement Program Root Cause Evaluation Improvements Special Evaluation of Operator Errors - Reactor Coolant Conductivity Reduction Program - First Refueling Special Initiatives e

fr + Maintenance Improvement Program Maintenance Self Assessment Upgrade Quality of Documentation - Trending / Problem Identification - 13 Week Rolling Schedule Functional Equipment Grouping Codes Plant System Status Report Modified Work Order Categories / Priorities Established Forced Outage Ready to Work List Automatic Tag-Out System (under development) - Reliability Information Tracking System (RITS) - Outage Critiques e 6

e r + r LER Reduction Initiatives Instrument Failure Response Manual Surveillance Verification Program Numerous Modifications to the RWCU System Installation of Sliding Links and Jumper Lugs Modifications to the Feedwater and Condensate Systems Various Modifications to RCIC Complete Revision to Channel Check Procedure Root Cause Analysis Training - Increased Management Attention Toward Completion of Outstanding Corrective Actions Initiated regular LER/ Current Events Training of Operator and I&C Technicians g 1 L' 6

m Fr 4 Scram Reduction Program - Task Force Representing Wide Variety of Work Areas O'ojective-To Evaluate Scram Reduction Ideas From Various Industry and Onsite Sources (Including INPO and BWR Owners Group) Items Were Ranked by a System That Reflected Beth Importance and Implementation Timeframe - Of the Original 170 Recommendations,81 (48%) were Already Incorporated at Perry 1 - Eighteen (11%) Were Given a High Importance With Near Term Implementation Ranking - Currently Establishing Role of Task Force With Ongoing Review of Operating Experience Reports b

V '? Annunciator Improvement Program Recognized Benefit of"Dark Board" Concept and Have Established the Following Program Goals: - No More Than 10 Out of Service Annunciators by End of 1988 - No "Dark Board" Annunciators by End of First Refuel Of Approximately 1500 Annunciators,13 Are Currently Out-of-Service and 20 Remain "Dark Board" Issues Established Continuous Tracking and High Level Management Attention et y

r r p Root Cause Evaluation ' Improvements Enhanced Documentation in Work Orders Established an Incident Response Team - Engineers, Maintenance Planners, Supervisors and Event Investigators Trained ih HPES, MORT and K-T Techniques Condition Report Program Enhancements - Upgrading Investigator Desk Guide; Integral Part of Condition Report Program - Lowered Threshold for Condition Reports Initiation - Emphasis on Effectiveness -Improved CR/LER Trending RITS Used to Trend Data From Corrective Maintenance - Improved Status Feedback Mechanisms Training on Initiation Criteria e 6

Fr p Special Evaluation of Operator Errors Initiated by Plant Manager Following June 8 Scram to Review and Provide Feedback on Operator Activities Manager Of Operations now Conducts "Current Events Training" as Part of Routine Operator Requalification Program Regular Meetings Between Shift Supervisors and Ops Depart. Management to Disseminate Performance Expectations Shift Supervisor More Involved in Management Decisions; Regularly Attends Morning Management Meeting - Operations Management Periodically Attends Pre-Shift Turnover Brief Manager of Operations Periodically Observes Performance of Plant Rounds Initiated Reviews / Revisions to Admin. Progs. to Reduce Burden on Unit Supervisor Reemphasized commitment to Procedural Compliance and Personnel Accountability - Operator License Class Will Expand Supply of Supervising Operators in Jan 89 O

G + Reactor Coolant Conductivity Reduction Program Identified Recurring Problem With High Reactor Coolant Conductivity In-depth Research and Analysis Concluded the Source of the Problem to be: - Resin Bleed-Through From the Condensate Filters - Sodium Hydroxide Input From the Condensate Demineralizers; High Condensate Temperatures Cause Leachin;; of Sodium From Cation Resin - NearTerm Actions - To Eliminate Bleed-Through, Finish Change Out of Condensate Filter Septa - Change Out the Condensate Demineralizer Resin - Bypass Demineralizers During Peak Heat Months; Rely on Filters - Change Out RWCU Filter /Demineralizer Septa Longterm Actions - Review Condensate Flow Capabilities While Demineralizers are Bypassed - Consider Replacing RWCU Septa With Finer Mesh Element e 6

Fr p First Refueling Special Initiatives l - I Complete Offload of All Fuel will Result in More Flexibility for Work System Engineers Instrumental in Defining Work Scope l Added Work Items Evaluated to Assure no Impact on Original Outage Scope Attempting to Eliminate Non-outage Work From Outage Schedule I Preparing Contingency Plans )

M* a rr 9 EFFECTIVENESS FEEDBACK: MANAGEMENT SELF ASSESSMENTS - Monthly Performance Report .1 CR/LER Trend Reports - QA Audit and Performance Based Surveillance Programs i ISEG 1 - Quarterly QA Assessment (self SALP) ) )

I i Quarterly Assessment Report 1987/1988 Ratings AREA 4TH QUARTER IST QUARTER 2ND QUARTER 1987 RATING 1988 RATING 1988 RATING j Plant Operations Good Good Satisfactory j Radiological Controls Excellent Excellent Good Chemistry Cood Cood Good Malatemance Good Cooi Cood Technica1 Specification i Survei11ance Good Good Good 1 l Security Excellent Excellent Excellent i Fire Proteetion Satisfactory Satlsfactory Good i Emergency Freparedness Excellent Excellent Excellent Quality Assurance Good Good Good i I l Licenslag Activity Good Good Good l Eng. and Tech. Support Good Good Good ) Cutage Managenent NR Cood Good l Training & Qualification Excellent Excellent Excellent Material Control Good Good Satisfactory d 6 w

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