ML20058Q371

Discusses 930921 Meeting in Atlanta,Ga Re Plant self- Assessment.List of Attendees & Presentation Summary Encl

ML20058Q371
Person / Time
Site:	Crystal River
Issue date:	10/13/1993
From:	Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Beard P FLORIDA POWER CORP.
References
NUDOCS 9310260162
Download: ML20058Q371 (44)

Text

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[i OCT I 31993 Docket'No. 50-302 License No' DPR-72.

Florida : Power. Corporation Mr. P. M. Beard. Jr.

. Senior Vice President, Nuclear Operations ATTN: Manager, Nuclear Operations Licensing P. 0. Box 219 - NA-21 Crystal. River, FL 34423 Gentlemen:-

SUBJECT:

MEETING TO DISCUSS. CRYSTAL RIVER 3 SELF-ASSESSMENT

- This letter refers to the meeting conducted at your request at the NRC Region. II offices'in Atlanta on September 21, 1993. The purpose of the meeting was to. allow Florida Power Corporation to make a presentation on Crystal River 3 self-assessment.

U i

.It isEour opinion that this meeting was beneficial and provided a better understanding of the issues and status of current programs.

In~ accordance with Section 2.790 of the. NRC's " Rules of Practice," Part 1, Title 10, Code of_ Federal Regulations,.a copy of this letter and its enclosures will be' placed-in the NRC Public Document Room.

Should you have any questions concerning this letter, please let us know.

i Sincerely, Original signed by Ellis W. Merschoff, Director Division of Reactor Projects

Enclosures:

1 ~.

List of Attendees-2.-

Presentation Summary cc'w/encls Gary L. Boldt-

- Vice President,- Nuclear Production Florida Power Corporation e

P; 0. Box 219-SA-2C-c50133 Crystal River,.FL 34423-0219 cc w/encis cont'd:

(See page 2)

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9310260162 931013-y PDR ADOCK 05000302-i PDR P'

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Florida Power Corporation 2

OCT I 31993 cc w/enclsEcont'd:

B. J.. Hickle, Director Nuclear Plant Operations Florida Power Corporation P. O. Box 219-NA-2C Crystal River, FL 34423-0219 R.'.C.'Widell, Director

-Nuclear Operations Site Support s

Florida Power-Corporation P. O. Box 219-NA '

Crystal River, FL 34423-0219 Gerald A~ Williams Corporate-Counsel MAC -'ASA

'P.-0. Box 14042 St. Petersburg, FL 33733 Attorney General Department of Legal Affairs The Capitol

-Tallahassee,- FL 32304 Bill Passetti.

Department of Health and Rehabilitative Services 1317 Winewood Boulevard Tallahassee, FL 32399-0700

-Administrator.

Department 'of Environmental

. Regulation 2600 Blair Stone Road Tallahassee, FL 32301 Joe Myers, Director Division of Emergency Preparedness

-2740 Centerview Drive Tallahassee, FL. 32399-2100

-Chairman'

Board of County Commissioners 110 H. Apopka Avenue Inverness, FL 36250

Robert B. Borsum B&W Nuclear-Technologies 1700 Rockville Pike, Suite 525 Rockville. "' 20852-1631 bec w/enci (See page 3) i;

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'--i LFlorida Power Corporation 3

OCT 131993 bec~w/encis:

K..Landis, RII H. Silver; NRR.

Document Control Desk b

-NRC Resident Inspector U.S. Nuclear Regulatory Commission

~ 6745.N. Tallahassee Road Crystal River, FL-34428 ib

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ENCLOSURE 1

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LIST OF ATTENDEES

'NRC Attendees:

S. D. Ebneter, Regional Administrator, Region II (RII)

- L. A _ Reyes, Deputy. Regional. Administrator, RII E..W. Merschoff, Director, Division of Reactor Projects (DRP), RII

.J. P, Stohr, Director, Division of Radiation Safety and Safeguards (DRSS), RII F'

J..P. Jaudon, Deputy Director, Division of Reactor Safety (DRS), RII

'C. A.'Julian, Chief,-Engineering Branch, DRS, RII

G. A. Belisle, Chief, Reactor Projects Section 2A (RP2A), DRP, RII K.~D. Landis, Chief, Reactor Projects Section 2B (RP28), DRP, RII h

P. Holmes-Ray,: Senior Resident Inspector, Crystal River H.. N. Berkow, Director, Project Directorate II-2, DRP-I/II, Office of Nuclear Reactor 1 Regulation (NRR)

H. Silver,, Project Manager,_ Project Directorate II-2, DRP-I/II, NRR L. Raghavan, Project Manager, Project Directorate 11-2, DRP-I/II, NRR R. P. Croteau, Project Engineer, Project Directorate II-2, DRP-l/II, NRR Licensee Attendees:

P.11.1 Beard, Jr., Senior Vice President, Nuclear Operations LP.'R.-Tanguay, Director, Nuclear Operations Engineering and Projects R..Cs Widell, Director, Nuclear Operations Site Support W. M. Marshall, Manager, Nuclear Plant Operations g

. R. W. Davis ^, Manager, Nuclear Plant Maintenance L

'J. H. Terry, Manager, Nuclear _ Plant Systems Engineering

15. G. Johnson, Manager, Nuclear Chemistry and Radiation Protection 1

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SELF ASSESSMENT PRESENTATION

SEPTEMBER 21. 1993 q

1 l-Opening. Remarks.....................Percy (Pat) M. Beard, Jr.

Senior:Vice President, Nuclear Operations (813) 866-5682 0perations.......................... William (Bill ) M. Marshall

. Manager, Nuclear Plant Operations i

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'(904).563-2943 - Ex. 3184

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Mai ntenance......................... Ronald (Ron) W. Davi s 2

Manager, Nuclear Plant Maintenance

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(904) 563-4358 Engi neering......................... Paul R. Tanguay Director, Nuclear Operations Engineering and Projects (813)'866-4710 James (Jim) H. Terry Manager, Nuclear Plant Systems Engineering (904) 563-4395 Pl ant Support....................... Sarah G. ' Johnson Manager, Nuclear Chemistry and Radiation Protection (904) 563-4384 Rolf C. Widell Director, Nuclear Operations Site Support-(904) 563-4529 i

Closing Remarks.....................Percy (Pat) M. Beard, Jr.

Senior Vice President.

Nuclear Operations

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ENCLOSURE 2 f_d' ry' ~ '

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PLANT ' OPERATIONS

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CHALLENGE-I IMPROVE TOOLS OPERATORS USE TO DO JOBS.

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- ACTIONS-

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ENHANCE PROCEDURES: EOPs, VPs,; ARs IMPLEMENT COMPUTERIZED LOG TAKING

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E PLANT OPERATIONS i

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RESULTS '

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~ PROCEDURES q,

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- INTEGRATED TEAM RESPONSE 4

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- REDUCED OPERATOR STRESS L

- ENHANCED COMMUNICATIONS

- SSOD OVERSIGHT lMPROVED

-- IMPROVED OPERATOR RESPONSE 1

e-COMPUTERIZED LOG TAKING AND TRENDING 1

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-- EARLY IDENTIFICATION OF NEGATIVE TRENDS l

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- ENHANCED OPERATOR ATTENTION g

- EFFECTIVENESS OF OPERATOR ROUNDS 1

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- INSTANT. RETRIEVAL OF INFORMATION w,

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- DOCUMENTATION QUALITY AND

- CONSISTENCY

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PLANT-OPERATIONS

. CHALLEN'GE m

m REVIEW AND CLARIFY OPERATING STANDARDS 7

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ENHANCE Al-500, CONDUCT OF. OPERATIONS e

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sJ RESULTS.

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TOTALLY REORGANIZED / REWRITTEN i

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- EASIER TO USE/ UNDERSTAND j

- IMPROVED WATCHSTANDING PRACTICES

- SELF CHECKING, QUESTIONING ATTITUDE, STAR-

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' ENHANCED COMMUNICATIONS FOR SHIFT RELIEF b'

LQUALITY AND CONSISTENCY OF SSOD AND s

OPERATOR LOGS

- ENHANCED-TRAINING FOR EXPECTATIONS-I V

OF OPERATIONS PERSONNEL a

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. PLANT OPERATIONS 1

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- CHALLENGE i

1 ENHANCE TRAINING IN. SELECTED AREAS m

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' ACTIONS p

GOOD HUMAN PERFORMANCE PRACTICES o

e SPECIFIC TRAINING TO ADDRESS NOTED DEFICIENCIES L

re REVIEW REPLACEMENT OPERATOR RO/SRO TRAINING PROGRAMS s

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PLANT! OPERATIONS m-p, RESULTS.

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c' GOOD HUMAN PERFORMANCE PRACTICES

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- IMPROVED WATCHSTANDING PROFESSIONALISM

- MORE USE OF QUESTIONING ATTITUDE, SELF-CHECKING AND STAR PROGRAM L

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- IDENTIFICATION / TIMELY RESOLUTION OF PROBLEMS

-- OBSERVATION / FEEDBACK BY MANAGEMENT-FOR WATCHSTANDING PRACTICES-h

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d SPECIFIC TRAINING'TO ADDRESS NOTED-DEFICIENCIES.

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- OSB~ ENTRIES FOR HUMAN-PERFORMANCE -

PROBLEMS-

- TRAINING DEPARTMENT REVIEWS AND SUBSEQUENT TRAINING ON HUMAN PERFORMANCE PROBLEMS REVIEW REPl.ACEMENTOPERATOR' RO/SRO e

, TRAINING PROGRAMS i',

- NO' PROGRAMMATIC PROBLEMS 0,,'

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PLANT: OPERATIONS 1

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l CHALLENGE'

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~ EARLIER IDENTIFICATION OF DETERIORATING PERFORMANCE l

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ACTIONS.

lNCREASE M' NAGEMENT INVOLVEMENT IN A

e OPERATOR ROUNDS

.e ASSESS CREW PERFORMANCE ON FIRST DAY OF'. SIMULATOR REQUALTRAINING e.

LOWER THRESHOLD FOR ACTION ON 5

PERFORMANCE DEFICIENCIES i

e ENHANCE EVALUATION DEPTH AND CONSISTENCY OF HUMAN PERFORMANCE PROBLEMS e

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PLANT OPERATIONS RESULTS o

INCREASED MANAGEMENT INVOLVEMENT IN OPERATOR ROUNDS

- IMPROVED WATCH STANDING PRACTICES AND RESPONSES IN ALL AREAS OF THE PLANT ASSESS CREW PERFORMANCE ON FIRST DAY OF SIMULATOR REQUAL TRAINING

- MORE ACCURATE APPRAISAL OF INDIVIDUAL AND CREW PERFORMANCE e

LOWER THRESHOLD FOR ACTION ON PERFORMANCE DEFICIENCIES

- OVERALL IMPROVED PERFORMANCE OF THE OPERATING SHIFTS e

ENHANCE EVALUATION DEPTH AND CONSISTENCY OF HUMAN PERFORMANCE PROBLEMS

- SEVERAL HPES EVALUATIONS MEET THE HIGH STANDARDS THAT MANAGEMENT EXPECTS. OTHERS DO NOT.

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IMPROVE OPERATOR SUPPORT l

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ACTIONS t

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.OTA EFFECTIVENESS AND AVAILABILITY m

e SHIFT MANAGER FULL SHIFT COVERAGE I

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RESULTS

• L OTA EFFECTIVENESS: AND. AVAILABILITY 4

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- TRANSITIONED.FROM ONE PERSON /24 HOURE i TO THREE 8-HOUR. SHIFTS /24 HOURS-W y

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. INCREASED-.OTA AVAILABILITY TO SSOD AND

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- NEW VP-580, PLANT SAFETY-VERIFICATION PROCEDURE ISSUED-

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-e SHIFT MANAGER (SM) FULL SHIFT COVERAGE-

- ALLOWS SSOD TO' DEVOTE MORE'MANAGEMEF,

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' AND. DIRECTION TOLTHE ' OPERATING SHIFT:

- REDUCTION.IN CONTROL ROOM TRAFFIC AND

. PHONE: CALLS TO THE SSOD REDUCED ADMINISTRATIVE BURDEN TO SSOD2

- MORE TIME FOR'SSOD TO TOUR PLANT SM HAVE DEMONSTRATED TIMELY

' COORDINATION / RESOLUTION OF COMPLEX.

4 AND ROUTINE PROBLEMS OVERALL COMMUNICATIONS 'ARE BETTER EARLY INVOLVEMENT OF SYSTEMS ENGINEERS 4

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NUCLEAR PLANT MAINTENANCE CHALLENGE

. Provide for the continuously improving material condition of CR-3 within our budget constraints.

ACTIONS Completion of Maintenance Self-Assessment.

Establish pro-active vs. re-active management.

Establishing the second level of management as-totally accountable and responsible for their shop / department.

Streamlining our housekeeping program (Al-1000).

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' RESULTS COMPLETION OF. MAINTENANCE SELF-ASSESSMENT:

We may have the best Planning Department in the country.

m Non-Outage backlog has been virtually eliminated.

Work Packages are acceptable to the. craft now.

Planner leads all post-job critiques.

Performance Indicators are a reflection of ourjob i

performance.

Repeat' Maintenance: currently <3% vs. 9%

during 8R.

t Maintenance Backlog:

currently equal to industry average,:but is decreasing.

Fluid Leaks have been reduced -

by-

.approximately 40%

during the last 12-months.

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1 ESTABLISH PRO-ACTIVE VS. RE-ACTIVE MANAGEMENT:

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i The I&C Department is developing test equipment that.will eventually be a power

.(Nuclear / Fossil) industry standard.

All major work and work packages were assigned to the craft prior to the outage.

ESTABLISHING THE SECOND LEVEL OF MANAGEMENT AS TOTALLY ACCOUNTABLE AND RESPONSIBLE FOR THEIR SHOP / DEPARTMENT:

Managers are all within their base and outage:

budgets, year-to-date.

Managers attend all meetings applicable to their shop and make the necessary decisions for their

. shop without prior approval.

STREAMLINING OUR HOUSEKEEPING PROGRAM (Al-1000):

With visits to approximately.15 nuclear power stations as our standard, we are one of the most 1

improved in mat'erial condition.

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CHAll FNGE ;

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Development of quality workers who strive to provide

. work of high quality.

ACTIONS

_ Improve the training provided to management and the craft.

'Re-thinking and rewriting the trouble shooting procedure.

Standardization of post-job critique process.

Improve responsiveness of management to worker issues.

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RESULTS r

IMPROVE THE TRAINING PROVIDED TO MANAGEMENT AND THE CRAFT:

15 individuals are being sent through our pre-engineering course to increase their base knowledge of the plant.

Two crews of Mechanics were sent to Colt Diesel-School prior to the 9M Outage.

Work was completed three days ahead of schedule with no re-work.

c Four Electricians-and one Electrical Supervisor sent to advanced MOVATs training for the upcoming refuel.

RE-THINKING AND REWRITING THE TROUBLE SHOOTING PROCEDURE:

Our trouble shooting procedure (MP-531) during startup, allowed us to resolve a problem with FWV-29 (Main B!ock Valve) without having to go from Mode 3 to Mode 5.

This equates to approximately 2% days outage savings.

We have Expert System software on site and we:

are currently modeling five systems.

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d ISTANDARDIZATION. OF POST-JOB. CRITIQU y

' All1 Maintenance accepts post-job critiques as "the way" of doing bu~siness. Various long term w

andishort term problems have been analyzed and' resolved using this method.

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. Waste Gas Analyser ($240K in expenditures m

starting in 1986).

Battery SPs:.

-certain s.teps were changed-from series to parallel allowing for 80-hours

. reduction of critical path time.

Reduction' of salt leak identification-and repair from 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> to 5:10 hours.

LIMPROVE

-RESPONSIVENESS OF MANAGEMENT TO WORKER;lSSUES:

Craft openly identifies problems and savings

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1 potentials.

Mechanicjduring-9M Outage identified to the Shop Manager that-the bolts on FWV-38 (Low.

Load' Control Valve)'

had been mistakenly over-torqued.

Electrician on " Tidy Friday" identified a set of-1

-RCP. motor. Kingsbury thrust bearings as refurbishable and not waste ($50K savings).

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ENGIN EERING/ TECHNICAL SUPPORT

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CHALLENGE 1 Resolve recurring plant problems s

- ACTIONS:

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installed the following major modifications-e F

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, Condenser Retubing Service Water Temp. Control Encapsulate'd CRD Stators 230 KV "BEST" Transformer Permanent Fuel Transfer Canal Scal Plate-r

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CHALLENGE cont'd Resolve recurring plant problems RESULTS h

Plant; problems, associated with these e

modifications, which had the potential to challenge plant reliability and availability m

were important to safety have been or are, or in-the process of being resolved.

Outage scheduling should ~be enhanced since e-Lthe~. installation of and potential for leaks on

.the seal plate'.has been eliminated 6

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. CHALLENGE-Enhance Engineering-support to address the e

industry issue of Erosion / Corrosion ACTIONS Continued the implementation of the e

Erosion / Corrosion inspection program in 9M Outage Participating on the EPRI CHEC Group Expanding the existing program to incorporate the CHEC program methodology RESULTS I

Outage inspections did not reveal any problem

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areas.

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Plant data is being entered into the computer-7' e

i data base such that it can be used by the CHEC program software 4

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ENGIN EERIN G/ TECH NICAL SUPPORT 1 CHALLENGE _

Enhance Engineering support to address the e

industry issue of Commercial Grade Dedication of equipment L

ACTIONS l

Continued with the implementation of the ongoing procurement initiatives 1

Continued-with the EPRI training for e

procurement personnel Expand our on-site capability to perform e

component testing required for comm.ercial-grade equipment dedication and receipt inspection-activities Fuses Circuit breakers HIPOT for insulation k

Hydrostatic Metal Alloy Verification 5

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ENGINEERING / TECH NICAL SUPPORT CHALLENGE cont'd Enhance Engineering support to address the industry issue of Commercial Grade Dedication of equipment RESULTS Continued to enhance the Procurement Engineer's understanding of the procurement process Equipment conservatively tested on-site has resulted in a significant cost savings and more timely receipt of needed equipment 9

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ENGINEERING./ TECH NICAl_ SU' PORT

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I CHALLENGE

.l Enhance support of Configuration Management e

Base Program A_CTIONS Original CM Scope was completed ahead of e-schedule,40 DB documents completed Initiated the preparation of topical design bases documents CMIS data base continues to be maintained e

and modified to address user needs RESULTS Design ' Bases information is readily available e-and enhances Engineering's ability to respond.

to plant support 1

CMIS data base is used extensively by all;

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m numerous requests to enhance it further as a i

means of improving the effectiveness of the individual organizations y

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E N GIN EERING/ TECH N ICAL SUPPORT CHALLENGE Continue to support the Configuration e-Management Electrical Calc. Enhancement 4

- Program ACTIONS-Completed the scope of the original Electrical

-Calc. Program Continued to maintain the electrical calcs to e

reflect plant changes initiated. effort to develop a Fuse Control e

Program and address the ampacity rating calcs.

- for electrical penetrations Supported implementation of mods. to resolve i

e issues identified during s.aic. development Dedicated team supported the EDSFI i'

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CHALLENGE cont'd

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. Continue to support the Configuration Management Ele'ctrical Calc. Enhancement Program 4

RESULTS e.

Several pieces of equipment were replaced to resolve deficiencies e-Computer models of the electrical systems

enhance'our: ability to support the

. maintenance and modification of the plant o'

EDSFI-appears to have gone well as a' result of 1

.our.self assessments and proactive pursuit of.

.the associated: issues j

Received positive remarks from the EDSFI team e

regarding the. quality of the calcs and the-a

- knowledge level of the individuals invoived.

Plants fuses ~are being' walked down as part of; the Fuse Control Program to~ provide the data needed in the supporting data base w

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E N GI N EERIN G./ TECH N ICAI_ SUPPORT c.

1 CHALLENGE Enhance support of plant activities through e

Modification Process improvement ACTIONS Performed comprehensive process e

improvement review implemented post modification, multidiscipline e

-critiques of major modifications

-RESULTS Effort is currently ongoing, final e

recommendations will be presented to management in October Lessons learned from the critiques have e

enhanced our ability to more cost effectively develop and install modifications in accordance with the established Planning and Scheduling milestones 10 I--

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DISCUSSION TOPICS NUCLEAR PLANT TECHNICAL SUPPORT ORGANIZATION SYSTEM ENGINEER ATTITUDE' E

WORK IMPLEMENTATION COMMUNICATION & DOCUMENTATION 9

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THE CHARGE OF THE TECHNICAL SUPPORT DEPARTMENT u

f THE TECHNICAL SUPPORT DEPARTMENT HAS RESPONSIBluTY FOR PROVIDING PROMPT AND DIRECT SUPPORTTO OPERATIONS AND MAINTENANCE FOR EVALUATING AND PROACTIVELY

-SOLVING PLANT: PROBLEMS TO CONSISTENTLY ACHIEVE AN.80% CAPACITY FACTOR WHILE KEEPING THE SAFETY OF THE PUBLIC PARAMOUNT 3

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l NUCLEAR PLANT TECHNICAL SUPPORT M

ORGANIZATION e NUCLEAR Pl.ANTSYSTEMS ENGINEERING

.e PRIMARY SYSTEMS-

.e SECONDARY SYSTEMS:

.*: ELECTRICAL' SYSTEMS e' INSTRUMENTATION & CONTROLS SYSTEMS E

e SHOP ENGINEERS 7

• COMPONENT ENGINEERING e PREDICTIVE MAINTENANCE e MOTOR OPERATED VALVES e Pl. ANT COMPONENT MAINTENANCE fe PREVENTIVE MAINTENANCE-ellSI. GROUP

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• SECTION XI ACTIVITIES e OTSG ACTIVITIES i

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- l7-NUCLEAR PLANT TECHNICAL SUPPORT l

l CHALLENGE IMPLEMENT A

" SYSTEM MANAGER" CONCEPT-THAT EMBRACES THE.

PHILOSOPHY OF SYSTEM OWNERSHIP ~ BY j

1 THE SYSTEM ENGINEER.

THIS ENSURES ADEQUATE DAY TO-DAY INVOLVEMENT OF SYSTEM ACTIVITIES BUT FOCUSES THE-EFFORTS OF THE STAFF TOWARDS LONG RANGE GOALS WHILE ENSU RING.'

ATTENTION TO DETAIL AND COMMITMENT TO QUALITY.

ACTIONS SYSTEM ENGINEERING IS RESPONSIBLE FOR -

SPECIFYING MAINTENANCE (including troubleshooting of problems), INSPECTION TESTING ACTIVITIES AND MODIFICATIONS.

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RESULTS 1.

CAPACITY FACTOR > 85%

POST OUTAGE RELIABill1Y NEAR 100%

2.

A FEW.

RECURRING LONG TERM "i

PROBLEMS SOLVED DURING 9M OUTAGE:

e. NI-1 REPAIR -

e 1E:

BATTERY TESTING SURVEILIANCE OPTIMlZED RESULTING IN SHORTENED DURATION e RCSG-1A LEAK REPAIRS AND PRESSURE TESTING OF BOTH OTSG'S 4

e AHF-51 FANS ~(CRDM SERVICE STRUCTURE -

COOUNG)

FLOW

" REVERSAL" AND-

' MOTOR INSULATION CLASS UPGRADE:

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A FEW OF THE~MANY RECURRING ~ LONG l

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(CONT.):

LTERM "ON-LINE" PROBLEMS SOLVED BEFORE AND AFTER 9M OUTAGE:

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'e WD-23-LT SPIKING 1

e TOXIC GAS MONITOR DRIFT PROBLEM (WITH PROCEDURE. ENHANCEMENT &

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. VALIDATION) e DEMIN.

WATER.

SYSTEM PROBLEMS

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INCLUDING:

- DWP-1A WRONG IMPELLER DWV-134. WRONG VALVE C 1

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DWV-128 lMPROPER ACTUATOR-1 SPRING CONFIGURATION

-:DWV-346. BYPASS LINE TO ELIMINATE

-WATER HAMMER -

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- REMOVAL ~ OF IGSCC AREAS i

4.

ACTION Pl.ANS ARE DEVELOPED TO RESOLVE THE FOLLOWING MAJOR-PROBLEMS:

1 e DHP-1A VIBRATION IN " ALERT" RANGE e' MAKEUP. PUMP TESTING RESULTING IN-REVISED ALIGNMENT PROCEDURE e RETUBING OF SC HEAT EXCHANGERS e REPLACEMENT BUNDLE AND SPARE FOR' SF HEAT EXCHANGER-1

• DECISION NOT TO REPLACE ROTATING l

ASSEMBLY ON RCP-1A l

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CHAIIFNGE MANAGE SYSTEM OUTAGES IN AN EFFORT TO-INCREASE THE RELIABILITY AND i

AVAILABILITY OF THE SYSTEM OR COMPONENT DURING HIGHER RISK PERIODS.

1

- ACTIONS-SYSTEM ENGINEERING PERSONNEL ARE i

RESPONSIBLE FOR COMPLETION OF THE SAFE 1Y BENEFIT DETERMINATION.

SYSTEM ENGINEERING PERSONNEL ARE RESPONSIBLE AND ACCOUNTABLE FOR ALL ASPECTS OF THE SYSTEM OUTAGE. - THE SYSTEM MANAGER.HAS FULL DELEGATIVE AUTHORITY.OF. THE DNPO OVER ALL REQUIRED RESOURCES.

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uV-Ill. J RESULTS 1 SUCCESSFUL SYSTEM / COMPONENT

'T.

LOUTAGES HAVE TAKEN PLACE.

THESE

~ '

INCLUDE:

o VBIT-1E.(INVERTOR-1E) n m

• SPENT FUEL: COOLING

~e DEMIN,. WATER-C U R R E N TEL.Y I. N T H:E PLANNING / SCHEDULING.

STAGES ARE SYSTEM OUTAGES FOR :THE FOLLOWING-5' SYSTEMS:

e ECCS A-TRAIN EQUIPMENT e ECCS B-TRAIN EQUIPMENT

-e EGDG-1 A

(EM E RG ENCY DIESEL GENERATOR-1 A)-

e' EG DG-1 B

- (EMERGENCY DIESEL GENERA ~iOR 1B) e SC SYSTEM d

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L CHAtlFNGE COMMUNICATE EFFECTIVELY WITH O DEPARTMENTS, ENSURING ACCURATE i

INFORMATION IS. TRANSMITTED RELATED TO SYSTEM

. PROBLEMS, ROOT CAUSE.

y IDENTIFICATION, ACTION PLANS FOR RESOLUTION AND ~ VISIBLE TRACKING OF SYSTEM ISSUES.

ACTIONS TECHNICAL SUPPORT COMMUNICATES

~ WITH OUTSIDE DEPARTMENTS ON FOUR-FRONTS.

• A-QUARTERLY TECHNICAL SUPPORT STATUS' REPORT:

IS PRODUCED:

PROVIDING-A DETAILED STATUS OF EACH

SYSTEM, TECH SUPPORT PROGRAM.

STATUS,

-A N D DEPARTMENTAL GOAL STATUS.

e RECENTLY IMPLEMENTED IS AN ON-LINE COMPUTER BASED' INFORMATION SYSTEM THAT CAN BE ACCESSED iBY ANY 'FPC' EMPLOYEE.

THIS

-SYSTEM IS

.USED TO COMMUNICATE IDENTIFIED PROBLEM ACTION PLANS.

e FAILURE.

ANALYSIS / ROOT CAUSE ANALYSIS REPORTS ARE USED: TO DOCUMENT FORMAL. ANALYSIS AND TRANSMIT THE INFORMATION TO ALL APPUCABLE DEPARTMENTS.

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" ACTIONS o SYSTEM WALKDOWNS REQUIRE 4

i (CONT).

C;O M M : U. N --l C A T 1. O ' N A N D' DOCUMENTATION WITH MAINTENANCE S U P E RVIS O RS, O P E RATO RS,.-

M EALTH.

PHYSICS P. E R S O N N E L',

A NiD PLANT MANAGEMENT.

RESULTS e THE SYSTEM ENGINEER IS-THE SINGLE POINT OF ACCOUNTABILITY RELATED TO SYSTEM PROBLEMS g.*

e ALL OPEN ITEMS ARE TRACKED TO

COMPLETION e PLANT' MANAGEMENT HAS:

A MECHANISM.TO PROVIDE FEEDBACK i

TO THE SYSTEM MANAGER t

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RADIOLOGICAL CONTROLS

-CHALLENGE Reduce collective radiation exposure by effectively using the ALARA concept.

1 ACTIONS Improved accountability for the ALARA Program.

Line organizations are now directly responsible.

Revised the dose budgeting process.

Health Physics negotiates departmental and L

job specific dose budgets.-

Dose budgets are printed on all RWP's.

Dose budgets are reviewed with work crews prior to job. commencement.

Work crews are encouraged to set task c

specific dose budgets in addition to meeting the RWP dose budget.

Increased the incentives to reduce dose.

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Performance on dose bud y.

individual merit increases. gets is tied to.

TheLAIARALSpecialist sponsored an AIARA Bucks Program during the 9M Outage..

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The ;ALARA Specialist and HP planners

+

q'uestion modification packages and work.

activities' when estimated dose seems excessive or unjustified.

a.

- Incorporated

.use of

- remote monitoring equipment :during the 9M Outage.

RESULTS

m..

. Collective exposure for the 9M Outage was 40%

. below. budget".

x

.8% is attributed to worker awareness and.

initiatives. Example: Flood Plain MAR dose Lbudget was: reduced from 60 rem to 10 rem.,

due to Engineer and. work crew input - and a

came in under budget.

Plant modifications have enhanced-dose reduction.

A new-refueling canal seal plate was-2

permanently welded into place, expen. ding.

sameLdose expected for normal installation j

. prior to refueling.

RB1 work; platforms' are being installed"in n

areas where repeat scaffolding construction-i-

has been-required.

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Flood Plain MAR became a benefit - majority 1

ofsinstrumentation.was moved from a high v-radiation area. intoia lower dos ~e ' area --

instead of. moving it closer-to the source.-

1 Exposure r e.q u i re d for routine

'in'strumentation ' calibration will be reduced.

x

. Collective radiation exp.osure is expected to be:<

+

7

- the revised 1993'ALARA Dose Goal of 75. rem.

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[,~14 RADIOLOGICALiCONTROLSl

/ r.;

p LCHALLENGE

^

Reduce collective radiation exposure by improving-radiological worker practices.

ACTIONS -

i Developed and began implementing a Radiation Worker Practical Factors Sign-Off Sheet.

Focused on shop specific knowledge deficiencies.

e-HP Technicians developed and presented-radiological topics customized to meet shop <

needs. This. process will be ongoing.

INew emphasis placed choosing on.

1

' pplicable' topics for. Radiological. Safety a

Bulletins published by the Corporate' Health

-Physicist.

Expanded 'use of the ALARA Simulator to correct poor worker contamination control practices.

RESULTS

A more knowledgeable work force.

i Fewer. personnel contamination events.

Fewer ' Nuclear Safety Concerns of a radiological

=

. nature.

i Collective radiation exposure is expected to be <

e the revised'1993 ALARA Dose Goal of 75 rem.

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RADIOLOGICAL 1 CONTROLS jg2 ce CHALLENGE

a Reduce ' collective radiation exposure by lowering plant dose rates.

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' ACTIONS Coordinated-effort between

ChemRad, Site Nuclear j

Services,. Operations, System Engineering, and-Design 1

Engmeermg Fuel performance is improved.

Fuel Reliability L

'e-Index is.relatively steady at a value approx.1/6th -

of the previous operating cycle value.

a ALARA Specialist chairs Source Term Reduction-l Task Force.

Comprehensive program addresses-cobalt reduction, operating _ and shutdown:

chemistry techniques, RCS microfiltration, and j

other techniques;which are the subject of EPRI research:and development.

lRESULTS 9M dose rates were approximately 1/3 lower e-than;the historical dose rates used during.the 1

budgeting; process.

i 132% is-attributed to source term reduction:

)

improved f6el reliability, reduction in post-1 filter pore size and shifting to a tighter 7

' lithium control program.

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NUCl_ EAR CHEMISTRY

u.+

i

~ CHALLENGE.

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Reduce erosion-corrosion in BOP and-reduce SG j

K fouling caused by corrosion product transport.-

l ACTIONS g

Coordinated effort between Chemistry, Engineering, i

EPRI, and BWOG.

Engineering'(MAR' to. install corrosion product

' samplers and pH(t) probe).

^

EPRI-(AMINMOD and high temperature' probe).

e

.BWOG (Modelling of pH effects in SG).

Chemistry (overall coordination, technical lead).

j Amine optimization program.

j

+

RESULTS Lowest fouling rate in history of plant.

Able to operate entire fuel cycle without SG cleanmg. -

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CHALLENGE-

.l Improve communication of plant chemistry data 7

and: achieve resolution of concerns.

3 ACTIONS l

Developed the Daily Chemistry Report 4

~

. Solicited input from Management,.

t Op'erations, and Engineering - selected data based 'on customer interest and operational impact.

Strengthened ties with Operations, Maintenance, System Engineering, and Scheduling.

. increased-reliance on Shift Managers, work control systems, and daily plant meetings.

. RESULTS Reactor Coolant DH concentration is 2

maintained at or near 25 cc/kg.

LiOH concentration is. maintained within an

' operating band df'*0.1 ppm.

Troubleshooting sources of inleakage has lowered feedwater oxygen concentration.

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t Cross-functional effort is underway to identify sources of RCDT contamination.

i

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Salt Leaks are quickly evaluated and prudent actions taken.

Scheduling expedites repair of systems or n

components that affect plant chemistry conditions.

4

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DAILY CHEMISTRY REPORT 9/3/93 Graphs show mon recent 28 rescits.

. +

SECONDARY CHEMISTRY PRL\\1ARY CHEMISTRY Feedwater Oxvgen j.,

RCS Lithium A 2.9 ppb l 6l 2.26 ppm 2.3 {

{

g

['

Me/ \\,

- - - - B 2.7 ppb 4!

. E L

,2,j. % ^ q-rj v

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l"o Limit 5 ppb

-' aw 2

Linut 2.0 - 2.2 1.s i

• '28 93

hrough 9193 8/793 tfrough 9/2/93 Feedwater Sodium j

3 RCS Hydrogen Meter y

A 1.4 ppb 2.5 26.1 cc/kg as

- - - - B 1.4 ppb 2 s_,

Grab Sample (weekly] y 3't 8/30/93 27 cc/kg 20 ^ ^[#

\\f Limit 3 ppb 05 Limit 25 - 40 15 0

10 7/2&93 through 9G93 7/2193 through 9463 Hotwelj O :vgen Dose Equiv. Iodine

,A 1 ppb 3,l 0

0.03078 uCi/cc g,g3 g

- - B 5.5 ppb e 4, _ _,,.

g,g4 3

j n,g3 WM

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2

^J Limit 10 ppb p.

1 O.02 7/2t93 through 90 93 7/133 through 9/2&3 Hotwell Sodium Wd Release Cs 3 en,,

A 2.5 ppb.

4 Tritium

- - - - - B 2.8 ppb 3

- - - - - All Other 10 0 2

Linut 5 ppb

,,/

Nuclides 3.0[

0 0.1

<~~'s. #' :-

7/2&93 tirough 9/3S3 Jul-92 through Jul-93 Cycle 9 Steam Generator Level Trend A OTSG Percent Icel B-OTSG Percent Level 85 85 83 D - ' ' "^ #

83 81 81 79 i

+& ~ u W 79 77 77 75 75 enum.emmmeu-memeeemem mm e cnome r cnnnmemo-mne ennm ommmr m-ene mv e e me m

---

mmmmannnnn m nemon er cnn nmecno-Nne

---

mmmmunnnen IIPO EFPD Remarks:

Hotwell sodium is currently trending down after a spike following placement of 'D' waterbox back in service.

b' NUCLEAR' CHEMISTRY g;

' CHALLENGE-LManage 'RCS LiOH concentration consistent with

]

changing plant conditions (i.e. boron, transients, e

-shutdown).

cACTIONS j

-Coordinated effort between Chemistry and

- Operations.-

identified existing trends.of pH vs. LiOH.

l

=

Evaluated frequency and methods of delithiation.

i Decreased LiOH operating band to *0.1 ppm.

increased pH consistent to EPRI guidelines at or e

near'6.9 for normal operation.

/.

Utilized delithiation to constantly decrease-pH

.during 9M shutdown.-

RESULTS RCS pH optimized through effective LiOH control r

for normal plant operations.

pH control during 9M shutdown minimized crud bursts'and contributed to lowered dose rates.

Operations Department understands importance of'pH-control.

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iNUCLEARL CHEMISTRY p_:

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-CHALLENGE i

1 x

.Use: DH control (2 25 cc/kg) to minimize RCS 2

.' corrosion.

r ACTIONS-4 4

+

q Developed. team effort to identify root cause of lower.

DH concentrations. Involved Chemistry, Operations, 2

(System?and. Design Engineering.

1

- Analyzed structure and subcomponents through engineering.

analysis.

Identified pressure regulating valve as limiting component.

e' i

Evaluated Make-Up Pump-curves and developed:

LMake-Up Tank pressure / level curve.

l Developed procedural guidance to increase MUT.

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L:-

pressure.

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Implemented modification to achieve 2 25 cc/kg

-@'STP.

RESULTS RCS DH. maintained at or near 25 cc/kg.

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a-NUCLEAR CHEMISTRY

- CHALLENGE-LDetermine _ potential for corrosion of zircoloy fuel.

cladding due to zeolite precipitation.

ACTIONS -

Examined crud film for zeolite forming species.

.t

=

Babcock and Wilcox Fuel Services was I

contracted to' perform fuel surface scrapings and analysis.

Concentration of zeolite:

forming species.in these samples'was:very low. - most notably, a small amount of

- aluminum was detected. Review of the data-indicates no significant zeolites in the fuel scraping' deposits.

Developed Analytical methods Analytical methods for determination of zeolite species using flame and furnace 1

atomic absorption spectroscopy and colormetric UV/ visible spectroscopy were developed -

and tested.

Appropriate.

procedures were written using CR3 format.

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9 Developed scheduling program.

1 Zeolite analysis Lof reactor coolant and all possible make-up sources is performed on a J

quarterly basis.

w-Review and Trend results.

a Laboratory Information Management System n'

1 (LIMS) profiles allow for entry of zeolite data into chemistry data. base.

Data review and

. trend plotting is easily accomplished.

RESULTS -

-i ALcompreh' nsive, aggressive program is fully-e implemented.

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,w NUCl. EAR CHEMISTRY i

CHALLENGE i

au Establish a" diesel fuel monitoring program 1

} adequate.to prevent failure of emergency diesel a

generato~rs due to poor fuel quality.

1 ACTIONS ~

Defined " adequate monitoring".

=

All available laboratory te'sts:were~

researched to determine l applicability.

Interviews were. conducted onia cross section of many operating nuclear plants.-

'in:the. United Sates,to help solidify the.

scope of the project. The dieselfengine manufa'cturer was also consulted, along-

.with lNPO and:thelNRC.

Purchased analytical equipment.

Laboratory instrumentation was purchased-s that: includes a flash point-tester, a vacuum

' device for particulate determination, microbe testing equipment, and ~special sample collection bombs for representative 1

sampling.-

Developed and tested analytical procedures for the laboratory equipment.

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' Established off-site analytical capability.

9

^

"A' contract'was cytablished with an outside

-1 laboratory:to perform 23 analytical tests-per appropriate: ASTM methods for

.petr.oleum products.

Developed scheduling program.

A scheduling program to perform the

. sampling and surveillance testing was developed to. include on-site and off-site analyses; All analyses are performed per

. ASTM methods for petroleum products.

~

. Review and' trend results.

Laboratory information Management System (LIMS) profiles allow for. entry of

~,

diesel fuel data into chemistry data base.

m

. Data review and trend plotting is easily accomplished.

RESULTS

. A comprehensive, aggressive program is fully implemented.

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NUCLEAR CHEMISTRY g

i CHALLENGE i

Reduce effluent activity by targeting specific radionuclides for removal during liquid waste

processing.

n ACTIONS t

Selected target nuclides based on concentration and dose considerations.

4 Several years of effluent data were.

reviewed.

1

-Specific radionuclides.were targeted based I

on this review.

'h Determined the best removal methods by a

evalu~ating cost and effectiveness.

e Several ion exchange and filtration. media were selected for testing. Cost and availability were considered for each media.

Tested and implemented specific methods.

Zeolite resin has been incorporated for i

cesium removal.

A cobalt selective charcoal media is currently being tested.

}

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av Testing _is conducted on-site' using actual

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aste system samples.

w Liquid radwaste chemistry characterization is performed.

)

Provide continuing system analysis to identify j

future enhancements.

i e

l The Laboratory Information Management-System provides nuclide specific removal trends.for each vessel in the radwaste processing system.

LIMS data is reviewed-on a routine and frequent basis.

New media will be tested as it becomes available.

1 i

RESULTS Improved dF for cesium removal.

Longer vessel run times have reduced solid radwaste generation.

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! NUCLEAR CHEMISTRY

'N'...

CHALLENGE Improve Post Accident Sampling System (PASS) function, operation, and. reliability.

[

ACTIONS Coordinated effort between Chemistry, Project Engineering, and System Engineering.

identified high maintenance hardware e

components.

identified instrumentation problems.

a Evaluated o.ther programmatic deficiencies.

~

Evaluated state-of-the-art instrumentation.

Determined.

performance enhancements.

to e-optimize system for design accident conditions.

Included technician.(operator) input.

=

RESULTS installation to be completed in December 1993.

i e

We expect:

On-line> instrumentation to be used for i

i normal

[

boron, plant chemistry monitoring for pH and dissolved hydrogen without any additional waste generated..

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' improvediefficiency due. to upgraded computer.

software and

"- operator fi.

friendliness".

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' increas.ed system. reliability due to lower:

t.

maintenance requirements and modular -

design.

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- NUCLEAR. CHEMISTRY l

t f,

CHALLENGE F

Solve problems associated with.the installed Liquid'

- Radiation Monitoring System.

ACTIONS t

=

. Collected-historical data and initiated project.

A plant walkdown identified specific items to be addressed, such as cable size, a

electronic module size constraints, detector piping configuration and available-detector mounting area.

m a

Chemistry and l&C shop personnel were interviewed to uncover historical system problems.

Developed < design input requirements.

I Cable' availability, process connections, and cabinet size. requirements were reviewed to ensure that specified 1

- equipment will meet existing plant conditions.

1 Emphasis was'placed on alleviation of monitor contamination and drainage problems.

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D.eveloped specifications and procured-Bf % s

. equipment 4

bg Off-line-samplers;were specified in order. -

Q, to aidiin decontamination of sampler-well.

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1 Control Room electronics will be replaced-with' digital-equipment versus analog;.

internal panel wiring will.be reworked to i

reduce existing congestion.

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Developsd MAR Package.

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System drawings have been generated.

. Engineering instructions have been. written.

cA bill of materials has been-prepared.

m Demolition l drawings have been generated j

for removal.of 'existmg equip' ment..

,s 4

RESULTS System drawings have been generated.

1 l*:

Engineering instructions have been written.

v i

i A bill of materials has been prepared.

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a Demolition drawings have been generated for

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removal of existing equipment.

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Installation to begin: October 1993, with all, 1; ~,',

.+

monitors replaced 1within approximately two x, -

a, years.

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EMERGENCY PREPAREDNESS i

FIRE PROTECTION

' SECURITY.

b t

.e CHAO FNGE c

Maintain high; standards, high levels of performance,.

and aggressively pursue opportunities to impmve.

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4 EMERGENCY PREPAREDNESS ACTION Hurricane / storm preparedness upgraded on site, including:

Rewrote Violent Weather procedure to address " Andrew" lessons learned' and-

. March 1993 flooding.

Coordinated site plans with corporate-wide plans.

Upgraded on-site communications:

1)

Improved antenna mountings.

2)

Distributed cellular phones 3)

Upgraded radio system for Corporate Security

~

4)

Added additional microwave dish 5)

In the process of procuring portable generators for all radio transmitters 6)

In the process of procuring spare antennas for each system to be installed post-storm

'~

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EMERGENCY PREPAREDNESS h

ACTION Continue to strengthen the interface with off-site agencies to assure the quality of off-site emergency preparedness.

RESULTS Improved proficiency in contaminated injury i

protocol at the off-site hospital.

Plan to replace sirens.

Improved community awareness.

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EMERGENCY PREPAREDNESS t

ACTION Improve proficiency with Emergency Action Levels and notification requirements.

Conduct monthly Control Room classification and communications drills.

Conduct periodic tests of Emergency Coordinator-trained personnel involving event classification and protective actiosy recommendations.

Include. EP Staff in simulator training observation and evaluation.

9 RESULTS Direct and immediate feedback among-EP, Training, and Operations produced impmved-proficiency and enhanced overall program.

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FIRE PROTECTION ACTION Apply innovative methods and technology to

+

the Fire Protection Program that will improve the Program and reduce costs.

Portable Detection System Computer-Based Fire Hazards Analysis

~

Computer-Based Breach Report System Reduced. reliance on contractors for "special" surveillances.

Reduced requirement for Fire Brigader response outside Protected Area.

' Roving Patrol reports to Fire Protection.

RESULTS.

~

P Continued exemplary performance:

No fires No violations No ANI Findings No QPD Findings this SAI.P period.

1 s

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SECURITY 1

ACTION Continue emphasis on Security effectiveness by I

e taking action to improve and measure performance.

Weekly tactical response exercises Periodic training with local law enforcement agency Tracking and trending program Weapons upgrade t

Training resporisibility shifted from contractor to Nuclear Operations Training Department Benchmarking against other plants

]

Self assessment-4 i

RESULTS High levels of performance, capability and morale i

e are being maintained

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7 LICENSING m.+

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CHALLENGE u

-Maintain a position of industry leadership on Licensing issues

' ACTION e

implement TSIP late Novernher 1993 Actively participate in development of Maintenance e

Rule guidance influence direction of license renewal efforts e

LAchieve resolution on procurement e

(.

M l

5 TSIP will be implemented on November 22,1993 e

CR-3 was a-Verification and Validation plant-for e

Maintenance Rule Guidelines B&WOG has taken lead role in license renewal e

Resolution of procurement has been achieved.

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PROBt FM" REPORT Fj;y'-

CORRECTIVE ACTION PROGRAM p

CHALLENGE ilmprove the Corrective Action Program e

ACIlON u.

iProblem Report Electronic Tracking - PR STATUS Revised procedure to reduce ambiguity under QP administration

.Technicallreview of.. corrective action plans by QP e

personnel.for adequacy Le LAssigne.d technical reviewer is available and is used by. personnel responsible for CAP Precursor Program m

e1 'AdvertisedLuse Review cards and determine if -a Problem Report o

'should be written If. writer's name is given, then he is informed of e

disposition-

-Root Cause Analysis Capability z

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RESULTS t

Corrective actions are completed in a more timely manner Technical adequacy of prc, posed corrective actions e

have been improved identification of areas needing improvement but not e

meeting the definition of a problem are being identified Formal root cause analysis help is available e

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