Text

Mgt Meeting Rept on 890307 & 0413.Major Areas Discussed: Status of Plant,Training & Safety Programs & Self Assessment Programs
	ML20247B665
Person / Time
Site:	Salem, Hope Creek, 05000000
Issue date:	05/09/1989
From:	Swetland P; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
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	NUDOCS 8905240198
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-4 U. S. NUCLEAR REGULATORY COMMISSION-REGION I' Docket No.: 50-272/50-311/ 50-354 License No. : DPR-70/DPR-75/NPF-57 Licensee: Public Service Electric and Gas Company Facility: Salem Units 1 & 2 Hope Creek Location: NRC Region I, King of Prussia, Pennsylvania and Hancocks Bridge, New Jersey Date: March 7,Jnd April 13, 1939 Approved by: 7 D Paul D. Swetland, Chief 'dage. '

Reactor Projects Section 2B Meeting-Summary: A meeting was held at the request of Public Service Electric and Gas Company on March 7, 1989 to discuss the status of the Salem and Hope Creek Generating Stations, to' update the training and safety programs, and to present their self assessment programs. A subsequent. meeting was held on April 13, 1989 to discuss the progress made on such licensee programs as' the Safety System Functional Reviews and the Human Performance Evaluation System.

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L DETAILS q 1.D Attendees :-

Nuclear Regulatory Ccmmission

S. Collins, Deputy Director Division of Reactor Projects (DRP)

W. Johnston, Deputy Director Division of-Reactor Safety (DRS)

J. Durr, Chief Engineering Branch, DRS

R. Gallo, Chief Operations Branch, DRS P. Swetland, Chief Reactor Projects Section 28, DRP

M. Shanbaky, Chief Facilities Radiation Protection Section, Division of Radiation Safety and Safeguards (DRSS)-

G. Meyer, Senior Resident Inspector Hope Creek Nuclear Generating Station K. Gibson, Sencior Resident Inspector Salem Nuclear Generating Station

L. Briggs Senior Operations Engineer, DRS

R. Nimitz Senior Radiation Specialist, DRSS

C. Sisco Operations Engineer, DRS

C. Miller- Reactor Engineer, DRP Consolidated Edison

S. Miltenberger Vice President'and Chief Nuclear Officer-S. LaBruna Vice President Naclear Operations L. M111er' General Manager, Salem Operations J. Hagan General Manager, Hope Creek Operations B. Preston General Manager, Licensing and Regulation

C. Connor General Manager, Nuclear Services J. Zupko, Jr. General Manager, Quality Assurance

R. Burricelli . General Manager, Engineering and Plant Betterment

- G. Roggio Station Licensing Engineer-Salem

- D. Cooley Onsite Safety Review Engineer, HC

- L. Reiter Manager, Nuclear Engineering Projects

- E. Liden Manager, Offsite Safety Review

- W. Schultz Quality Assurance Program Audits

- A. Taylor Safety Review Engineer /HPES

- G. Englert OSR-Principal Safety Review Engineer

- L. Piotti Station Quality Assurance-Salem

- A. Giordino Manager, Station Quality Assurance

Attended meeting on March 7, 1989 only.

- Attended meeting on April 13, 1989 only.

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2.0 Discussion '

At the meeting in the NRC Region I of fice on March 7,1989, the licensee provided an overview of their organization and program status at Salem and Hope Creek. An outline of the presentation is provided as: Attachment 1.

The trending of various performance indicators over the -last year was presented for both Salem and Hope Creek. The licensee detailed management's involvement in plant operations by discussing the focus, objectives, and goals established and monitored by the organization. The licensee presented self-identified weaknesses and their programs to address the weaknesses such as improvement programs, action plans and self assessment programs.

At the' meeting held in Hancocks Bridge on April 13, 1989, the licensee discussed additional' details of self-assessment status. The licensee presented their accomplishments in the areas of Safety System Functional Assessment and Human Performance Evaluations, explained their present Action Tracking System and provided some milestones for future efforts, An outline of the presentation is provided as Attachment 2.

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NUCLEAR DEPARTMENT BUDGET

SUMMARY

1988 1988 1989 %-

BUDGET ACTUAL BUDGET INCREASE SALEM $111.4 $135.2 $111.4 ---

HOPE CREEK $ 72.4 $ 76.3 $ 78.4 8.3%

BASE $183.8 $211.5 3.3%

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NEW BASE $173.8 $189.8 9.2%

CAPITAL SALEM $ 49.6 $ 61.2 $ 72.2 45.6%

HOPE CREEK $ 37.5 $ 32.3 $ 40.0 6.7%

TOTAL $ 87.1 $ 93.5 $112.2 28.8%

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1 NUCLEAR DEPARTMENT '

VISION I

Among the best in the U.S. and World Class by 1995 '

MISSION The mission of the Nuclear Department is the safe, reliable and efficient operation of the Company's nuclear facilities within corporate, industry, and regulatory standards; to produce competitive cost electricity for our customers.

1989 OBJECTIVES Improve Nuclear Department and Plant Performance A. SALP Rating B. INPO Category Rating C. Performance Indicators improve Employee Morale and Job Satisfaction Improve Financial Performance

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SUW4ARY OF 1993 NUCLEAR DEPARTMENT OBJECTIVES l

I. BECOME MORE COST COMPETITIVE o IMPROVING EQUIVALENT AVAILABILITY.

o CONTROL 0&M COSTS o CONTROL CAPITAL COSTS I o INCREASE UNIT CAPACITIES II. ACHIEVE INCREASED REGULATORY CONFIDENCE AND ACCEPTANCE.

o TAKE MORE PROACTIVE (COMPREHENSIVE, 4 STRATEGIC) ROLE IN ASSESSING AND SHAPING REGULATORY AGENDA.

o MEET REGULATORS' EXPECTATIONS.

o PERFORM EFFECTIVE SELF-ASSESSMENTS (INCLUDING BUT NOT LIMITED TO SSFIs, HPES) l

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III. DEVELOP QUALIFIED, MOTIVATED AND INVOLVED WORKFORCE.

o IMPROVE WORK QUALITY.

o INCREASE WORKFORCE MOTIVATION.

o SEEK EMPLOYEE IDEAS AND CONTRIBUTIONS.

IV. IMPROVE MANAGEMENT PROCESSES.

o MOVE TOWARD MORE INTEGRATIVE (ESPECIALLY CROSS-FUNCTIONAL) MANAGEMENT PROCESSES.

O CLARIFY ACCOUNTABILITY.

o IMPROVE MANAGERS' AWARENESS OF FINANCIAL AND BUSINESS REQUIREMENTS.

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SALEM GENERATING STATION NRC PRESENTATION MARCH 7, 1989 o Review of Programs / Projects to Correct Identified Weaknesses o- Review of 1988 Performance o Conclusions

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IDENTIFIED WEAKNESSES i SOURCES OF INFORMATION l?

o Management Observations o- Self-Assessment Reports - QA, NSR o NRC Inspection Reports o' ;INPO Evaluations

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I IDENTIFIED WEAKNESSES 1

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o Procedural Inadequacies / Problems o Management & Supervisory Oversight o Personnel Errors o Material Condition 1

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. J PROCEDURAL INADEQUACIES / PROBLEMS o Technical Guidance o Human Factors o Lack of Admin Control l

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TECHNICAL PROCEDURE UPGRADE PROJECT OBJECTIVE Address technical deficiencies Rewrite procedures IAW new technical procedures writers guide.

Develop / implement computerized procedure management system

-ACTIONS TAKEN TO DATE Establish scope - Completed Develop specification for project support /

implementation - Completed Secure Contractor Support - Completed MILESTONES / SCHEDULE Start work 3/89 1989 - 25% complete 1990 - 65% complete 1991 - 100% complete

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T/S SURVEILLANCE IMPROVEMENT EFFORT

-OBJECTIVE Establish T/S Coordinator for Station Validate MMIS Data Base Develop DBASE T/S Matrix Establish Main Frame T/S Matrix data base ACTIONS TAKEN TO DATA Validation of MMIS data base - Completed DBASE T/S Matrix - Comple te d Organizational Alignment - Completed l

MILESTONES / SCHEDULE Reduce reliance on manual files - Ongoing Establish'7 day and less surveillance in MMIS - Ongoing Validate EO surveillance - Ongoing Establish other Regulatory requirements on MMIS - Ongoing

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SUPERVISORY OVERSIGHT WORK PRACTICE'STANDARQ o Prior to Job o During the Job o Job Completion PROCEDURE USE GUI_DELIN1

o. De'finitions o Procedures Cannot Be~ Performed o Procedure Not Required o Expanded Work Scope

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WORK STANDARDS & PROCEDURE USE GUIDELINE i

l OBJECTIVE, Improve work practices Improve procedural compliance Improve attention to detail Feedback Systems ACTIONS TAKEN TO DATE Generated action plan for short and long term actions.

Completed Draft Work Practice Standard.

Completed Draft Procedure Use Guideline.

Completed Performance based monitoring feedback program.

Communications have started MILESTONES / SCHEDULE Issue Work Practice Standard 3/89 Issue Procedure Use Guideline 3/E9 Incorporate Standard into continuing education t r a i n i n a.; 7/S9 Conduct training on Nuclear Department Administrative Procedures 1989 Conduct training on Nuclear Department Safety Manual 19F9 Develop worker's manual of work standards 9/89 Provide coaching and counselling. training for supervisors 1989 Include requirement for evaluation of individual's work practices / procedural compliance in personnel performance appraisal. 1989

Managing Organizational Change" Training. 7'i0

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PERSONNEL' ERRORS:

o Failure to Follow Procedures Procedure!Use Guideline R.P. Procedures Training NTC Human. Factors Review

- Procedures Upgrade Project o Inattention to Detail 1

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RADIATION PROTECTION DEPARTMENT IMPROVEMENT PLAN OBJECTIVE Improve procedural compliance, supervisory oversight and attention to detail.

-ACTIONS TAKEN TO DA_TX Increased management participation in root cause analysis Re-established management Night Order Log Re-instituted supervisory check list Special Procedures Training MILESTONES / SCHEDULE Issue improved work practices standard -

3/89 Evaluate procedural adequacy -

4/89 Prepare outage pians - turnover packages, procedures - 4/89 Incorporate department performance monitoring and feedback program -

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MATERIAL CONDITION IMPROVEMENT (MCI) PROGRAM IDENTIFIED WEAKNESSEE Specific plant areas identified as degraded condition OBJECTIVE Root cause fixes (stop leaks)

Improve component reliability Improve worker safety environment ACTIONS TAKEN_TO DATE Assign Project Manager - Completed Assign Area System Engineers - Completed System Engineers propose Area Corrective Projects - Completed MCI Projects finalized - Completed Maintenance issued projects f or support / schedule - C on;p l e t e d Improvements have started -

23 Heater Drain Pump Upgrade Corrective Maintenance Work Orders Circulating Water System Service Water System MILESTONES / SCHEDULE _

Maintenance Resource Support / Schedule -

3/E0 Total Implementation Schedule -

2./89 GM-SO Program / Schedule Approval -

3/89 Generate Work Orders and Design Changes -

3/E9 Maintenance Work Plan - 3/89 thru 3/90 9

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TABLE I_

SALEM REACTOR TRIPS (1/1/86 12/31/88)

UNIT 1 UNIT 2 1986 9 9 1987 '2 4 1983 2 7 TOTAL' 13 20 TABLE II TRIPS SORTED BY PRIMARY ROOT CAUSE (PRC)

PERS EO EXT. E_V E_N_T _ ._ __ D O C_U M E! E A T I O N UNIT 1 5 7 1 1 UNIT 2 9 9 1 O TOTAL 14 16 2 1 L____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ , _ _ _ _ _ . _ . _ _ _

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1986 - 1983 33 SALEM TRIPS v

l o Rx Turbine Trip Setpoint to 50%

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o RPS Trio Logic 72 SALEM TRIPS o FW Deleted Events

13 SALEM TRIPS.

o 4 Major Elect. Equip Failures o 1 Trouble shoot ing o 1 Failed S.R. Detector o 3 Personnel Error o 2 Indeterminate m_ _ _ _ . _ _ . . ._.m___._..____m____ _ __.m_.. ____ ____

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OVERRIDING CORRECTIVE ACTIONS-(FROM 1986)

_ _ _ _ _ . ITEM STATUS TLrbine Bypass System Modifications Complete - Bot h Units Predetermined Load Reduction Strategy for Loss of a Feed Pump In Place - Both Unit:

l Reinstallation of Clamp Circuit (where needed) into SGWLC Controllers Complete - Bot h Units Day-to-Day Attention to Various Systems Provided by System Engineers Ongoing Increase in Y/Rx Trip Setpoint to 50% Unit 1 - 8th Refueling Complete - Unit 2 Change in Reactor Protection System Unit 1 - 8th Refueling Trip Logic upon Loss of a VIB Complete - Unit 2 New Inverters Unit 1 - 8th Refuelins' Unit 2 -

5th Refuelina Control Room Upgrades Segun on Unit 2 Begin Unit 1 - Bth Refuelino License Change to Perform Turbine Valve Tests at Increased Intervals Awaiting NRC Approval Increased Simulator Practice / Improved Simulator Representations Implemented HPES Being Implemented Reliability Based Maintenance Future O

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HOPE CREEK STATION

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APPROXIMATELY 2400 ACTIVITIES ,

VERIFIED CRDM REMOVAL TOOL-FEEDWATER FLOW N0ZZLES APPROXIMATELY 50 DESIGN CHANGES

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TABLE 4 1988 COMPARISON WITH PREVIOUS YEARS Deficiency M M g Pers Error 34 13 13 Equipment' 22 16 10 i

Design 14 10 9 Procedure 9 E 2 Management 0 0 0 External 0 0 0 Other 14 S 2 TOTAL 94 52. - 36 i

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" STRUCTURED APPROACH USED FOR PROBLEM IDENTIFICATION AND RESOLUTION" ZERO REPEAT FINDINGS y

IMPROVED PERFORMANCE OVERALL

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RESTRUCTURING OF NUCLEAR TRAINING-ORGANIZATION STRUCTURE UPGRADE e 15 AddtionalInstructors e 4 Addtional Technical Support ALIGNMENT OF STANDARDS FOR ALL DISCIPLINES o Salem and Hope Creek IMPROVED INSTRUCTOR TRAINING INSTRUCTOR AND TRAINING EFFECTIVENESS ASSESSMENTS IMPROVED OPERATING EXPERIENCE FEEDBACK MODULAR TRAINING l

LICENSED OPERATOR RECOVERY PLAN l

L_.___ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

F LICEhSED OPERATOR PPELINE RESOURCES COMMITMENT

10 Positions - Salem

8 Positkms - Hope Creek IMPROVED CAREER OPPORTUNITIES

Degreed /Non-Degreed Operators NEGOTIATING EQUIPMENT OPERATORS TRAINING OPPORTUNITIES PROVIDING DEGREE OPPORTUNITY

Increased Flexbilty with Added Recources i

Op3 rations

... Menagem2nt Junior D3partment Head SNSS Departmental Supervision s Engr

2. 2 yr r

NSS B.S. E SYSTEM ,

SRO ENGINEER v

B.S.E Certified CRO Sys Engr

'f B.S.

Degree SRO l

? CLASS RO NCO 8 month R.O. > NCO <

CLASS SRO SRO-NCO 16 month >

l l , -

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I E.O.

EO y OTHER CLASS IBEW 8 month y CLA!SIFICAliONS OPERATIONS DEPARTMENT PIPELINE i

~'

ENGINEERING DEVELOPMENT PIPELINE I

REPLENISH ENGINEERING TALENT

24 Positions Approved >

FEEDER PROGRAM FOR SYSTEM ENGINEERING GROUP

Direct Hires (Recent Graduates and Experienced) e Career Development for High Achievers CAPITALIZING ON STATION SYSTEM ENGINEERING l POSITION FORMAL TRAINING AND FIELD APPLICATIONS SOURCE OF DEGREED STA/SRO ON SHIFT FEEDER GROUP FOR ALL NUCLEAR DEPARTMENT ENGINEERING DISCIPLINES

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MANAGEMENT RE-EMPHASIS OF INDUSTRIAL SAFETY FORMATION OF NUCLEAR DEPA SAFETY BOARD 8

FR ISHMENT OF INDUSTRIAL SAFET

Program Self-Assessment

Employee Surveys e INPO Recommended Plant Visits MAJOR ISSUES OF CONCERN

Priority of Safety

Role of Management

Safety Procedures

Safety Training AREAS OF IMPROVEMENT

Seven Action Plans

O l

MANAGEMENT RE-EMPHASIS OF INDUSTRIAL SAFETY FORMATION OF NUCLEAR DEPARTMENT INDUSTRIAL SAFETY BOARD ESTABLISHMENT OF INDUSTRIAL SAFETY TASK FORCE e Program Self-Assessment

Employee Surveys e INPO Recommended Plant Visits MAJOR ISSUES OF CONCERN e Priority of Safety e Role of Management

Safety Procedures e Safety Training AREAS OF IMPROVEMENT e Seven Action Plans

SEVEN PO NT ACTION PLAN MANAGEMENT ACCOUNTABILITY PROGRAM e Revise Program to Better Define Management Safety Responsbittles.

Evaluation / Performance Criteria in Personnel Appraisals.

SAFETY PROBLEM REPORTING e Visibility of Program.

Timely Response to Concems.

Employee involvement in Development / implementation of Change.

l 1

SAFETY A'NARENESS TRAINING e Safety Meetings.

Communication Meetings.

Develop Accident Hazard Alert.

e Poster Program.

Safety Showcase.

ACCIDENT PREVENTION COMMITTEE o Revise Chader of Safety Discussion Group.

I e Upper Management Commitment and !nvolvement.

Proactive vs. Reactive.

l

Increased Authority of Committee Member.

l i

_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ l

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OPTIMIZATION OF SAFETY STAFF

Current Use of Safety Coordnator.

Safety Checkist.

Planning and Scheduling Support.

Making Safety Easy.

SAFETY PROMOTION / INCENTIVES

Incentives to Promote Safety Awarness and Positive Attitudes.

EQUIPMENT AVAILABILITY AND HOUSEKEEPING e Tool Accountability / Coordination.

Revise Housekeeping Responsibility / Accountability.

1

SELF ASSESSMENTS AND PROACTIVE PROGRAMS SELF ASSESSMENT: A CRITICAL REVIEW OF NUCLEAR PROGRAMS AND PROCESSES CONDUCTED WITH THE INTENT OF

CONFIRMNG EFFECTIVENESS OF FULFLLMENT OF SAFETY OEUECTIVES

IDENTIFYING ACTIONS NEEDED TO MPROVE PERFORMANCE

PREVENTING PROBLEMS

COMMUNICATING -

e FOLLOWING UP OUR CORRECTIVE ACTIONS RECOMMENDATIONS l

1

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PRIOR SELF ASSESSMENT ACTIVITIES l

QUARTERLY NUCLEAR OVERSIGHT COMh4TTEE MEETINGS

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e COOPERATIVE MANAGEMENT AUDIT PROGRAM (CMAP) 1 A!.OITS l

QA MASTER AUDR PLAN Ato SCIEDULE

OPERATING EXPERENCE REVIEW PROGRAM e E&PB TECHNICAL ASSESSMENTS e NPO SELF ASSESSt&NT (HOPE CREEK)

FPO ASSIST VISITS

THIRD PARTY ASSESSMENTS

TECH SPEC VERF1 CATIONS

EMERGENCY OPERATNG PROCEDURE VERIFICATIONS (S/HC)

PRODUCT / SERVICE MANAGENENT(P/SM) ASSESSMENT o SALEM / HOPE CREEK ASSESSMENT FOLLOWNG HATCH SHUTDOWN

TOSFEA CONTROL ROD DRIVE REMOTE HAtOLING MACHilE o HC 6 DAY /24 HOUR OPERATIONS DEPARTIENT OBSERVATIONS

HOPE CREEK 500KV MAN TRANSFORMER FALURE e SALEM UMT 2 GENERATOR WATER NTRUSION

i PRIOR SELF ASSESSMENT ACTIVITIES I 1

o PROGRAM AND PROCESS REVIEWS

- DEFICIENCY REPORT PROCESS

- INCIDENT REPORT PROCESS

- TEMPORARY MODIFICATION PROGRAM

- HC PRE-OP TEST PROGRAM

- HC NSTRUNENT SETPOINT CALCULATION PROGRAM

- SALEM SETPOINT STUDY

- POST TRP REVIEWS e SAFETY SYSTEM FUNCTIONAL REVIEWS

- SALEM AUXILIARY FEEDWATER SYSTEM i

- SALEM COMPONENT COOUNG WATER SYSTEM ;

- SALEM HVAC SYSTEM

- HOPE CREEK SERVICE WATER SYSTEM

l l

a ., .

PRODUCTS OF PRIOR SELF ASSESSMENT ACTIVITIES e PERFORMANCE BASED ALOIT/ SURVEILLANCE TRAlf#KB e E&PB ORGANIZATIONAL APO PROCESS RESTRUCTURING 4 i

e UPGRADED E&PB 1RANNG e SYSTEM ENGNEERNG ORGAMZATION APO TRAtEG

, o DESIGN CHANGE PROCESS f@ROVEMENTS I e WORK CONTROL PROCESS B@ ROVE!ENTS e foUSTRIAL SAFETY

AUGhENTED Al.DITS (TECHMCAL SPECIALISTS) e RADWASTE REDUCTION

RADIATION EXPOSURE REDUCTION

CONRGURATION BASELNE DOCUIENT (CBD) PROGRAM e PREVENTIVE MANTENANCE PROGRAM e PROBASLISTIC RISK ASSESSMENT (FRA) PROGRAM e HUMAN PERFORMANCE EVALUATION SYSTEM (HPES)

PROGRAM

NUCLEAR OPERATIONS 'hENTOR" PROGRAM e PROCEDURE RECOtFIGLEATlON PROECT

FSAR COMPUTERIZATION

P/SM REALLOCATIONS

l l CURRENT SELF ASSESSMENT ACTIVITIES

OPERATNG EXPERIENCE PROGRAM e SALEM MAINTENANCE e THRD PARTY ASSESSMENT OF THE 50.59 PROCESS

SSFR - SALEM AIR SYSEMS

BACKSHIFT QA OBSERVATIONS

PERFORMANCE BASED SURVEILLANCE (SALEM)

POST TRP REVIEWS 1

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FUTURE SELF ASSESSMENT ACTIVITIES 1989 STRATEGIC GOAL DEVELOP AND IMPLEMENT A PROGRAM TO INTEGRATE AND EVALUATE THE RESULTS OF INTERNAL AND EXTERNAL ASSESSMENT ACTIVITIES.

UTILIZE PERFORMANCE INDICATORS

DIRECT EFFORTS WHERE MOST NEEDED e IDENTIFY VOIDS IN EXISTING ASSESSMENTS FUTURE ASSESSMENT NEEDS WILL BE IDENTIFIED THROUGH FORMAL SELECTION CRITERIA AND PRIORITIZED OVER A FIVE YEAR ROLLING SCHEDULE I

FUTURE SELF ASSESSMENT ACTMTIES e CMAP AUDITS e PERFORMANCE BASED QA AUDITS

PERFORMANCE BASED QA/NSR SURVBLLANCES S SSFRs e PROGRAM AND PROCESS REVIEWS e OPERATING EXPERIENCE REVIEW PROGRAM e E&PB TECHNICAL ASSESSMENTS e INPO SELF ASSESSMENT (SALEM AND HOPE CREEK) e THIRD PARTY ASSESSMENTS

HPES EVALUATIONS e UT'LIZATION AND CONTROL OF PRA e PERFORMANCE BASED SUPPLIER AUDITS

MATERIAL RECEPT INSPECTIONS e SAFETY SYSTEM OUTAGE MODIFICATION l REVIEWS i

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. YYAc- Mf-t[] 2 MEETING AGENDA PSE8GNQA&NSR/NRCRESIDENTS APRIL 13, 1989

1. SELF ASSESSMENT PHILOSOPHY . . . . . . . . . . J. ZUPK0

2. ATS-QA/NSR ACTION REQUESTS . . . . . . . . . . W. SCHULTZ

3. PERFORMANCE BASED INSPECTIONS . . . . . . . . D. PERKINS

' ll . FIVE-YEAR ACTION PLAN

DEVELOP DN INTEGRATED SELF ASSESSMENT . . . E. LIDEN PROGRAM

DEVELOP'A ROOT CAUSE SKILLS PROGRAM . . . . D. COOLEY

5. HUMAN PERFORMANCE EVALUATION SYSTEMS . . . . . A. TAYLOR (HPES)

G. IE BULLETIN 88-10 M0LDED CASE BREAKERS . . . . W. SCHULTZ

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1986 1987 Total AR's Late-5 Late-70%

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Lok-71 Lob-7 On Time-29% On Time-22%

Page 1 of 2

7 www *

. . . l L Action Requests L Timeliness of Responses by Organization 1988 1987 NHO Lota-52% Lota-51%

On Time-48% On Time-49%

NNS -

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Page 2 of 2 j

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. .. SYSTEMATIC ASSESSMENT OF 4

NRC-0516 06 LICENSEE PERFORMANCE report based on the Regional Administrator's consideration of the licensee's response. The final SALP report should be a stand-alone document. ,

e. Overview. The ratings assigned to individual functional areas are I only one aspect of the SALP process. The SALP Board is expected to assess each functional area in such a manner that the SALP Board discussion focuses on understanding the reasons for the observed performance. The attributes and assessment criteria provided in Appendix approach., A should After be relied assessing allonof to thedevelop a uniform functional areas, and consistant the SALP Board is expected to discuss commonalities, if any, among the func-tional areas. This process of reviewing the summary results from the standpoint of identifying common underlying reasons for the licensee's performance is the basis of the overview. The overview is not a summary statement of the numerical ratings of the individ-ual functional areas. Rather, the overview is intended to be a synopsis of the underlying reasons, in the view of NRC managers, for both good and poor licensee performance. With regard to poor licensee performance, the overview developed should be somewhat spec!fic so that the -licensee may be . fully aware of the areas in ~

which increased utility management attention is required.

To emphaslae topics for consideration beyond the specified functional areas, NRR will identify selected topics for inclusion as part of the overview. Topics selected will be addressed t:y all SALP boards for a defined period, and the summary results will be presented as part of the overview.

General guidance regarding the implementation of the SALP is provided in Ap-pendix 8. Specific guidance for the implementation and conduct of the SALp process is . contained in the operating procedures of each responsible office and Region.

0516-06 FUNCTIONAL AREAS Functional areas represent a grouping of similar licensee activities. Each functional area evaluated will be assigned a rating as defined in Sec-tion 0518-08. Although not all. functional areas need be assessed in a given review, an explanation should be given in the SALP report if a functional area appropriate to a licensee is not evaluated. The evaluation criteria and asso-

, clated attributes against which the functional areas are to be evaluated are l provided r in " Appendiar A tto vthis' chapter: Note that1 performance:.Indicatorst i should :not be . ar factorirr judgements 'about- the effectiveness or reting in a particular SALP functional area. It is inappropriate to make reference" to performance indicator program results in arriving at a SALP rating.

l 061 Operatino Phase Reactors ,

s. Plant Operations. ' This functional area consists chiefly of the con-trol and execution of activities directly related to operating a plant.

It is intended' to include activities such as plant startup, power Approved: June 6,1988 O

g..

SYSTEMATIC ASSESSMENT OF .

. 4.lCEN5EE PERFORMANCE NRC-0516 061.b operation, plant shutdown, and system lineups. Thus, it includes j activities such as monitoring and logging plant conditions, normal operations, response to transient and off-normal conditions, manipu-lating the reactor and auxiliary cohtrols, plantwide housekeeping, ,

control room professionalism, and interface with activities that support operations.

b. Radioloalcal Controls. This functional area consists of activities directly related to radiological controls, including occupational radiation safety (e.g., occupational radiation protection, radioactive materials and contamination controls,. radiation field control, radio-logical surveys and monitoring, and as low as is reasonably achiev-able programs), radioactive waste management (i.e., processing and 1 onsite storage of gaseous, liquid, and solid wastes), radiological l effluent control and monitoring (including gaseous and liquid efflu-ents, offsite dose calculations, radiological environmental monitor-ing, and confirmatory measurements), and transportation of radioac-tive materials (e.g., procurement of. packages, preparation for

, _ ' shipment, selection and control of shippers, receipt / acceptance of shipments, periodic maintenance of peckagings, and point-of-origin safeguards activities). ,

c. Maintenance /5urve!Itance. This functional area includes all activi-ties associated with either diagnostic, predictive, preventive or corrective maintenance of plant structures, systems, and components; procurement, control, and storage of components, including qualifi-cation controls; installation of plant modifications; and maintenance of the plant physical condition. It includes conduct of all survell-lance (diagnostic) testing activities as well as all inservice inspection and testing activities. Examples of activities included are instrument calibrations; equipment operability tests; post-maintenance, post-modification, and post-outage testing; containment leak rate tests; water chemistry controls; special tests; inservice inspection and performance tests of pumps and valves; and all other Inservice inspection activities. -

d. Emeroency Preparedness. This functional area includes activities '

related to the establishment and implementation of the emergency plan and implementing procedures, such as onsita and offsite plan development and coordination; support and training of onsite and offsita emergency response organizations; licenses performance during temarcisess and- octusie eventsethetr test emergencg plansk,..

administration, and implementation of the plan- (both during. drills, and actual events); notification; radiological exposure control; recovery; protective actions; and interactions with onsite and offsita emergency response organizations during exercises and actual

- events.

e. Security. This functional area includes all activities that ensure the security of the plant, that is, all aspects of access control, security chec,s, k safeguards, and fitness-for-duty, activities and controls.

Approved: June 6,1988

~ .o .

T' SYSTEMATIC ASSESSMENT OF N R C-0516-062 LICENSEE PERFORMANCE .

f. Enoineerino/ Technical Support. The purpose of this functional area is to address the adequacy of technical and engineering support for all plant activities. It includes all licensee activities associated with the design of plant modifications; engineering and technical support for operations, outages, maintenance, testing, surveillance, . {

and procurement activities; training;- and configuration management.

g. Safety Assessment /Ouality Verification. This functional area includes all licensee review activities associated with the imple-mentation

of licenses safety policies; licensee activities related to amendment, exemption and relief requests; response to generic letters, bulletins and information notices; and resolution of TMI items and other regulatory initiatives. It also includes licensee activities related to the resolution of safety issues,10 CFR 50.59 reviews, 10 CFR 21 a,ssessenents, safety committee and self-assess-ment activities, analyses of industry's operational experience, root cause analyses of plant events, use of feedback from plant quality assurance / quality control (QA/QC) reviews, and participation in self-improvement programs. It includes the effectiveness of. the licensee's quality verification funiction- in identifying and correcting substandard or anomalous performance, in identifying precursors of potential problems, and in monitoring the overall performance of the plant.

h. Other (As Needed). "For example, when plants are in extended shut-downs, it may be more appropriate to address shutdown operations in -

lieu of plant operations. For readiness assessments, SALp boards may need to consider activities that take place over a shorter in-terval, such as startup testing.

062 ' Construction Phase Reactors

a. Soils and Foundations. This functional area includes all . activities pertaining ,to soils and foundations related to the construction of the ultimate heat sink and major structures. Specifically, this covers, as applicable, subgrade investigation and preparation, fill materials and compaction, embankments, foundations and associated laboratory testing,. .and related instrumentation and monitoring .

systems.

b. Containment, Major Structures, and Maior Steel-Supports. This func .

tionst.. area . Includes; all activitiest relatedsto: the- structuratccons erwte andrsteel.used;in'the containment. (including.the,basemat), ma .

jor structures, and major steel equipment supports. It covers all aspects of structural concreta (e.g., reinforcing steel; concrete batching, delivery, placement, in-process testing, and curing; liner plate erection and fabrication; . and containment post-tansioning), ;

structural steel used in safety-related structures (welded and bolted), and major steet equipment supports (for reactor vessel, '

reactor coolant pumps, steam generators, pressurizer, polar crane, tanks, heat exchangers, etc.). I Approved: June 6,1988

i SALEM I

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DIRBCT OBSERVATION OF ACTIVITIES AND/OR REVIEW 0F .

I DOCUMENTATION TO VERITY CONFORMANCE TO SPECIFIES R3QUIRENENTS tEstos.MAper BASED EX,PANSION OF TEE PERFORMANCE ORIENTED CONCEPT TO ACWIEVE QtT&LITY OF PLANT OPERATIONS EWEASIS W TECWICALLY 900ND EVA1A1ATION OF ACTIVITIES NOST IMPORTANT TO SAFETY A)W RELIABILITY ASSIST MANAGEMENT IN DETERMINING PERFORMANCE STATUS OF PLANT ACTIVITIBS 1

l IDBNTLFY BLBMENT DEFICIENCIES REFINEMENT OF CURRENT POLICY MORE INVOLV,EMENT IN TBCHN@ CAL ISSUES OF PLANT AND REACTOR OBBRATIONS WIGH INCREhSBD POCUS ON TBCHNICAL ISSUES VERSUS MDMINISTRATIME IS9USS l

TECHNICALLY CAPABLE QA PERSONNEL PERFORMING PERFORMANCE MONITORING OF PLANT OPERATIONS

, BROADENS SCOPE AND DIRECTION OF QA EVALUATIONS PROVIDES PERFORMANCE INDICATOR DATA BASE FOR TRACKING AND TRENDING I .

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3ANUARYIMS .

d PLANT MATERIAL COMNTION PERPOSJ4ANCE CECTIVE The material constion of the plant should be maintained w appert ade and rgEshk West epersh l

C RffE N A A. Mechanicat :ymmens and equipment are in good working order.

1 S. Pluid system leaks are minimized.

C. Electrical and electronic equipenent is operable and appropriately protected from adverse environmm.at corditiors.

D. Instrumentathn, controls, and associated indicators are operable and calibrated, as reqJired.

E. Good lubrication practices are evident.

l F. Mechanical operators, fasteners, and supports are in place and operable.

1

l G. CP pment, i structures, and systems are properly preserved and insulated.

H. A method is established to iruncate that material deficiencies have been identif*wd and are in the work control system.

l L NTOU Temporary environmental protection (e.g., dust, humidity, frceze, shock) is provided for plant equipment.

J. Kf0L: Satisfactory equipment condition is verified prior to operational acceptance by the plant staff. Special attention is given to equipment that encounters heavy usage during construction.

32

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'. IMPO Guid211230 for Performance Baced Surveillanos and Aodito JANUARY 190 .

' SURYFR I AMPS TESTDeG PROGRA45 PERFORMANCE CEDECT!YE l

Surve111ance inspection and testing activitle: should provide assurance that ogdpment that affects safe and reliable plant operation will perform within regaired Emita.

CRITFJUA A. Administrative systems and controis ensure timely comptetion of regdred r.rvel!!ances.

l E. Surveillance testing programs inchade egdpment that affacts safe and reliable plant operation and satisfy the technical and administrative requirements of A5ME 5ecti XL Rules for in-service hspection.

C. Proced.res used for aavelliance testing are claar, concise, and contain sufficient detall to ensure safe plant operation, consistent test performance, and accurate results.

D. Survelliance testing and test reviews are perf ormed under procedural controh by l knowledgeable personnet.

, I g wwdw action is taken when acceptance criteria are not met.

F. hdependant review of compieted surw1!1ance tests is condacted a ensure that acceptance criteria are met.

C. Acws! egaipment performance and test data trends are evakasted to improve safety and reliability. ,

M. The effectiveness of surveillance testing programs is periodica!!y evaluated, and t results are used to make program improvements.

L The technical bases for surveillance tests and their methods Oncluding reference documented and available.

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1 I o IDENTIFIES TE AGGEPTABLE LEVEL OF QUALIfly BEING ATTAIMD AND YERIFIED ',

o PROVIDES,RESubTS I,N.TERP$S OF $1 ANT PFAliORW)NpE AND EFFECTIVEN(SS.0F AGTIVITIES SURVEILLED TO ENS J RELIABLE PiANT' PERFORMANCE .

e PROBLEMS $; 0F ASTulu., Og P0TENTI AL j o 1 ARE; PEESEnRD; IN 1FR 1

EFFECT ON SAFE' AND> RELIABLE PLANT' PERFORMANCE y o I S S U E A C T I O N >~ R E.Q U E.S.sc T. S ; A S f. R E..Q U,.I R E D

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I turve111ance Activity The SOA teas randoely selected (M1 aporoptiate sebeduled maintenamee work activities. The verloos types et serve 111ance

[ )

j eenditless were as iellows:

e Periodic manitoring e "Is Process" and ' Start to Flaiah*

l e Preventive (pm), corrective K1s), and Securring Teak l

f (RT) malatesance concerns and 8eceaseadatless

1. cla,rificaties needed of the definities "Within skill et w ckamic".

I

2. breakdown et f undaneetals - this was evidenced by the incidences el the work oremr, procedure, drawing, ed.c. not being et the job loca, tion.

3. c1w ification and guidance from Engineering needed 1.n ref erence to the control /use of Nest classified part.s ie the There maintenance of set classified componente/ equipment.

appears to be confusion and misunderstandings is this area.

4. There were situations where the procedure was inadequate for

the work activityte).

5. There should be a policy to address unmanned /una,ttended energized test equipment; special concern was safety related and critical hook-up situations that could result in an inadvertent trip.

6. There were situations where the procedures were not properly followed. Also there were implications that the work order activity (s) and the designated procedures were not satisfactorily considered prior to implementation.

7. The 2 year review cycle of some procedures were found to be overdue. NOTE: This has been previously addressed by QAR 58-83-Q008-0 (issued 9/20/88),

e

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Yalves N011#31 1 Doct thder W1 tape auf Linder Tm' trip RN hev. E 1 (k1 ad hatas W 800219002 1 Dect Visual 1mspecticas of $n bryag Pug kxn RF1/2.2 hev. 9/0 1 Caoler tor i,.1" Wes, etc. ad lengper Motor Eect Calibratie af tinit 2 f.H.B. 81 IEKI nev. 5 2 871024H9 1 Supply ran Am. Mtdes

, ' 890122023 Dect 2A SEC Orduct igic and Timing Test M3B Rev. U 2 1

C1011HO 1 Mech Valve Harl - Imak Around Dange Mmetised 1 Tighten Bolting 880718061 1 Mech Spent Ebel Pipe nange leaks - Replacment M11UM22A Rev.13/0 2 l of Gaskets Mech Spent Ibel Pipe nange Leaks - Replacment M11U M23A Rev. 13/0 2 880718063 1 of Gaskets 890116114 1 Medi 21 SN hap / Seal Pirn Ird:ing and hap X11E W . 13 2 Vibrating. Repair and Remek if needed. MSL Ref. Ody Rev. 8 Vibratim Readings on 821 SN Pump KLIG hev. 7 2 890116H4 2 Mech 121 Oarying Pump to Geir B:E (bupling. MllE Rev. 13 2 88U05013 2 Mech Dissemble-Clear Inspee-Inb and Reassemb'le Clean and Inspect SN Side of Omying M11E Rev. 13 2 881222039 1 Mech hap, Inb 011 Beat IXchanger

1E.XbERPTFROMPERFORMANCEBASEDSURVEILLANCEREPORT2/1/89.

j Necative Observations e Absence of visible 'la process' en the job eheervaties by supervisory staff for recurring restine type test activity (s).

e Abseece es *ia process' es the job meef tering by Cestracter supervisors.

e h h es appeeeriate serk properat$es orser te iaplemeetatles br costracter maiartesence porasses1:

procedure review, dreving, teels , etc.

e h abseece of i=te er approprietaAreguired work order, proceewre, drawings et job bocations; this was particularly observed with Ceetracter leuimtenemoe persoamm1.

o contracter Maintenance personesil astpeared t>o be missing, a good grasp et Staties programs and requirements; consideraties of as Sound comed tions and tihe abildty to recognise ad tuations concerning ensdsen conteol configuration /soditfdcatices Wmum tibse' occur.

o Personned are as tensdr job activ.isty, i not identifying p2ent .fcionciges ubem obvious

, deficiencies exiet in their immediate work area.

o The designated program for Station personnel qualification records is not being istp,lemented in a timely manner; the r,+oords for personnel are not current. In the interia, the metM being used to check personnel qualifications / cort'ifications is the computer, hardcopy records, etc.

o Possible hazards in work area due to the amount of water in area and personnel work on electrical equipment.

o observed personnel standing on piping, reaching over equipment - proper staging was used after questions l were raised.

l I

EXCERPT FROM PERFORMANCE BASED SURVEILLANCE REPORT 2/1/89, 9

Observations

1. Observations of areas with Positive aspects and results were as follows:

1. M&TE, when used for activities observed, was calibrated as required.

2. Work was always properly authorized and controlled.

3. A safe and orderly work environment was saintained.

4. Industrial Safety practices were observed (hard hats '

and saf ety glasses, ladders and scaf folding used where necessary). l

5. Good Housekeeping practices observed, tools, parts, and ;

trash renoved f rom work area upon job completion.

6. Paperwork was completed and returned to the supervisor in a timely sanner.

7. 1he Mechanical Maintenance supervisor checked on jobs te determine the progress of the activity.

8. Psroonnel presented a positive attitude during the work activity.

l

9. Tb* MM18 data base reflected the actual work activity status.

10. Radiological control requirements were adhered to. j

11. Rigging Equipment (slings, etc.) load test was l eurrent.

12. For those jobs observed involving critical and saf eguard equipment type testing, the following was boted:

a. The I&c and Electrical Maintenance technicians observed were very attentive to the job task (s) and followed the procedures in a step by step manner.

b. There was e.scellent interfacing between them, Control Room and operations personnel prior to implementation and during the job activities.

OttutPT FROM PERFORMANCE BASED Swill ANCE MW Ma M 2it : Lt _ h____14 he _W ad tthat _ ^"*Mt v Actd- '^ ma r+ iired as a neaulit at h M vinii l h M . ,

Commant.s l

' 1. Perpetuation of poor worA practicap and i4onk hahits:

examply are apt by personnel woriking t .

hen a supervisor and/or the spnior personge3 a program by working a job Mithout a procedur ,r toolp or unsafe practicep. the junior gr@p,. qpe gersonri upy acquire the same tr.aAts. An emphasds needs to ge gt cp doi.ng the right thing: (a) following proceduras apd p,rograpp., (13) fore direct attention to" detail, (c) ask questions rtir,st - be acting.

2. The most pervapive p'~

bles identified was *1ack of attention to details

3. Contractor Maintenance personnel need.nore, 'Vnds. on*

stonitoring by the responsible department supervision.

4. The use of " sign off* sheets..should be considered as a method to control.the num'ber o'f procedur*efsheets.! required for document history re' cords.

5. Thei M374 procedure - three, people. utilizing

' designaked! location could_ save* time, a)npo, . wer, abd;also headsets at each se the' unit would.be', under could' t echnical' consequently speci f i ca tdiminish the, i ons ' Limi t{C6r,,ditions for ' Operations t'ing-(LCO).

6. Relays that are attached for testing should,be equipped with banana type plugs f or ease of testing. The procedure now knurls permanent lugs.

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.m- __ _ _ . - - - _ _ . -__ -..=-m _-

EXCERPT FROM PERFORMANCE, BASED SURVEILLANCE REPORT 2/1/R9.

I ADDENDUM This a6dendum contains observed iindings, activities, or itees that need improvement or possible action.

A. Froceeges need ier prevemtive saiatosance metivitles for work perf ormed es the chargias pumps , are im%te.

I Procedure !n11E (mechanical troubleshooting and repair) was used for cleasing, inspecting, and le ricatins the coup 1 imps . he procoeure has no Las.tructsoms to tematify j what the mechanic is t,o inspect for. Me woesk ordar

( specifits to clean and inapect Sor essiciencies and waner.

j There are no acceptance / rejection criteria to enable the mechanic to evaluate any conditions $ dant 1.fied.

I o What other dosiicinacies is be inspoeting for?

o Are there any tolerances tro be measured when inspecting for wear?

l l

o Should the couplimg be cleaned with a solvent to ensure the removal of all ol<$ grease so an adequate inspection can be performed?

The work package did not sipecify the mainten ce retest o

requirements. This act/ivity requirep tihe y formance of a vibration ana' lysis as per procedure M238. This was not accomplished.

o Procedure M11E was also used to clean and inspect the lube oil heat exchanger (servi:+ water side). The same concerns are $dentified:

o What is the mechanic inspecting for?

o What are the acceptance / rejection criteria?

o When the cooler heads are installed. should they be torqued?

j B. Torquing procedures are not being followed for the torquing of piping systes flanges as per the requirements of procedure M23A (torquing guidelines).

o An air impact gun was used to tighten piping system flanges. The torquing procedure was not listed 1.n the t

work package or present at the work location. The procedure specifies whet is to,be torque'd"and does not provide for the use of air impact tools,.

1 l

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' i i

P'ERFORMANCE INDICATORS FOR CONDUCT OF MAINTENANCE,.OP, RADPRO & CHEM

1. WORK IS AUTHORIZED BY W.O.

Work order / work request established for work activity being performed and at work location.

2. CORRECT PROCEDURE USED Appropriate procedure (s) to complete work activity

3. PROCEDURE CORRECTLY IMPLEMENTED sequence Compliance to procedure requireseats.

followed as applicable.

4. MATERIALS IDENTIFIED & TRACEA&LE SMIP in package for safety related material installed and material ihatified.

5. M&TE IDENTIFICATION & CALINLATION Assure MdiTE being used is properly identified and within established calibration cycles.

6. PERSONNEL QUALIFIED Personnel performing the work are qualified to perform the assigned work activity.

7. SAFETY PRACTICES FOLLOWED Personnel in the work activity area are wearing appropriate safety equipment (hard hats, safety i

' glasses, ear protection. etc.) Scaffolding erected when necessary, use of ladders, 1.anyards, safety belts

used as required.

8. RADIOLOGICAL PRACTICES Personnel are aware of radiological conditions are properly dresced according to RWP requirements wear l

applicable dosametry and conduct their work using good Radiological Safety practices.

9. CURRENT REVISION TO ALL DOCUMENTS USED Assure procedure revisions used for the work activity r

l l

are current. Assure that working drawings are not expired as per void stamp date.

10. GOOD HOUSEKEEPING MAINTAINED Verify that work area is neat and orderly during performance of work. Verify that area is left in acceptable condition after completion of work.

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I l QAE CHECKLIST 4 ET W 4 l SUBJECT JB, LP, RJ, HD-01, 2-02 maintenance TN, RS MD-03 N 1 O&-ce-06 6 )D-47 l

@ rati m d i

Red. Pro r

I# ' 88 ' "

Chemistry l

1 As, aJ, as, Tech. Dept. ,,

RE/TS-0011 TD & GS BOP LP #8 T t,J Tech. Spec. JB, LP MD-04, TD-02 TW Housekeeping AS, LP HK-01 Fuel Handling TW, GL FS F.U. LER 88-011 Unit #1 AS TS-oD OD-10 Submitted By & L/' 7p,. IL JCA Approved By Page of'

. REV.

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Tae sp3rgy PeopKT staties: salen STATIOu OA SURVEILLANCE CEECKLIST MD-01 B

aspogyg Ru3loor quality Assurance Page _ es _

Department MAINTENANCE ACTIVITIES Arco / Activity Surveillance:

Checklist and/or details of Surveillance activitys l l

Omit Technical specification i

1. Activity description

2. Location W.O. # _

W.R.9 3.

Drawin,p

4. Technical Mammal

5. Applicable Procedure 5.1 Approved 5.2 Reviewed withis past 2 years 5,3 Test Equipment eocumented 5.4 Prerequisites signed 5.5 System line-up signed

6. On-The-Spot-Change (s ) /JDCW ( s )

l

6.1 Properly documented 6.2 Approval

7. Test Equipment 7.1 As prescribed by procedure l 7.2 Calibration label 7.3 Calibration due

8. Personnel qualification

9. Out of, Specification data documented

10. Conformance with requirements or REP /EREP ,

. 11. Q.A. notification / hold points

12. Post maintenance testing performed _.

13. Operability retest performed

14. MMIS reflects activity status l COMMENTS _

1, 10/85 QAF-76 REV.

NOQA7/08 _ _ _ _ _

l SURVEILLANCE SCREDULE PSE&G SERVICES fit #T 954RTER i 1999

Quality Assurance' IscarTE TGA Departaent CHECKLIST $ CCfestrTs PROGRAP9(ATIC AREA QAE l

coerTRACTost ses CTR-41

sc-41 CONTRACTOR DG *CTR-41

SC-41 l

CONTRACTOR !#1 C15t-61 SC-01 CONTRACTOR JL C'DR-01 SC-01 CONTRACTOR DF C1R-01 *NDE-It04 SC-01 *NDE-1,06

NDE-103 *NDE-106 MW FP-04 TP-02 + COMMON 10 BOTH FIRE PROTECTION SALEM & HOPE CREEK FP-03

+FP-01 INSERVICE INSP. MG 181-209 181-305 1

JL *SD-03 COMMON TO BOTH SECURITY SALEM & HOPE CREEK

SD-04

SD-11 RG

M&TE-03 COMMON TO BOTH f' M&TE CALIBRATION SALEM & HOPE CREEK M&TE-01

RESCHEDULED FROM FOURTH QUARTER 1988 A mn submitted By Approved By,_ N O V u h *

-q Page 1 o f _1__

Rev.

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SELF ASSESSMENTS AND PROACTIVE PROGRAMS l

SELF. ASSESSMENT: A CRITICAL REVEW OF NUCLEAR PROGRAMS Af0 PROCESSES CONDUCTED WITH THE NTENT OF

CONFHMG EFFECTNEESS OF FULFLUENT OF SAFETY OELECTIVES e DEN 1FYNG ACTIONS EEDED TO BPROVE PERFORMANCE

PREVENTNG PROELEMS e COMMUMCATNG e FOLLOWNG LP OlR CORRECTNE ACTIONS RECOWSOATIONS

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PRIOR SELF ASSESSMENT ACTIVITES l

e QUARTERLY MJCLEAR OVERSIGHT COhMTTEE MEETNGS

COOPERATIVE MANAGEMENT ALDT PROGRAM (CMAP)

ALDTS

QA MASTER AUDIT PLAN Ato SCIEDLLE 1

OPERATNG EXPERENCE REMEW PROGRAM 1

e E&PBTECfHCAL ASSESSMNTS

f90 SELE ASSESShENT (HOPE CREEK)

990 ASSIST VISITS e THIRD PARTY ASSESSMNTS

TECH SPEC VERIFICATIONS e EMERGENCY OPERATNG PROCEDlRE VERIFICATIONS (S/HC) ,

o PRODUCT / SERVICE MANAGEMNT(P/SM) ASSESSMENT e SALEM / HOPE CFEEK ASSESSENT FOLLdWNG HATCH SHJTDOWN

TOSFEA CONTROL ROD DRIVE REMOTE HAPOUNG MACHitE

HC 8 DAY /24 HOUR OPERATIONS DEPARThENT OBSERVATIONS

HOPE CREEK 500KV MAN TRANSFORMER FALLRE

SALEM LNT 2 GEMERATOR WATER NTRUSON l

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PRIOR SELF ASSESSMENT ACTMTIES

PROGRAM AND PROCESS REVIEWS

- DEFICIENCY REPORT PROCESS

- INCIDENT REPORT PROCESS

- TEMPORARY MODIFICATION PROGRAM

- HC PRE-OP TEST PROGRAM

- HC NSTRUNENT SETPONT CALCULATION PROGRAM

- SALEM SETPONT STUDY

- POST TRP REVEWS o SAFETY SYSTEM FUNCTIONAL REVEWS

- SALEM AUXUARY FEEDWATER SYSTEM

- SALEM COMPONENT COOLNG WATER SYSTEM

- SALEM HVAC SYSTErA

- HOPE CREEK SERVCE WATER SYSTEM

4 .

r -PRODUCTS OF PRIOR SELF ASSESSNENT ACTMTIES j e PERFORMANCE BASED ALDIT/ SURVEILLANCE TRAf443

E&PB ORGANZATONAL APO PROCESS RESTRUCT1.RNG e LPGRADED E&PB TRAIG4G e SYSTEM ENGNEERNG ORGAMZATION APO TRAte4G e DESIGN CHANGE PROCESS f@ROVEMENTS

WOFE CONTROL PROCESS EPROVSENTS

900STRAL SAFETY e AUGfENTED ALDITS (TEC$NCAL SPECIALISTS)

RADWASTE REDUCTION

RADIATON EXPOSLNE FEDUCTION

CONFIGURATION BASELfE DOCLEENT (CEE) PROGRAM e P!EVENTIVE MAIMNANCE PROGRAM e PRCBAELIS11C RISK ASSESS $4NT (PRA) PROGRAM i

HUMAN PERFORMANCE EVALUA110N SYSTEM (FfES)

PROGRAM

NUCLEAR OPERATIONS '1ENTOlr PROGRAM

PROCEDURE RECONTILRATION PROECT

FSAR COf@UTERIZATION

P/SM REALLOCA110NS l

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CURRENT SELF ASSESSMENT ACTIVITIES

OPERATNG EXPERIENCE PROGRAM e SALEM MANTENANCE e THRD PARTY ASSESSMENT OF THE 50.59 PROCESS .

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SSFR - SALEM AR SYSTEMS e BACKSHFT QA OBSERVATIONS

PERFORMANCE BASED SURVELLANCES (SALEM) e' POST TRP REVEWS 1

e-FUTURE SELF ASS $SSMENT ACTMTIES e CMAP AUDITS e PERFORMANCE BASED QA AUDITS

PERFORMANCE BASED QA/NSR SURVEE. LANCES i e SSFRs ;

e PROGRAM Ale PROCES8 REVEWS e OPERATNG EXPERENCE REVEW PROGRAM e E&PB TECH 5 CAL A88EBSENTS e INPO SELF ASSEBSENT (SAL.EM Ate HOPE CREEK)

TimD PARTY A88E88MNTS e HPES EVALUATIONS

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SAFETY SYSTEM OUTAGE MODIFICATION RIPMWS

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NSR (1) Sfty Rvu Ener 6

[ QA (2) Pro & Adts Eners (2) Statior. Sves/QC 16 12 15 l ill 93 11a Attrition Factor E St per year 33 28 34 Total to be trained in Sosic 144 121 150 and Intermediate hoot Cause k ' ' ' ' ' _ . . . ._____miim r m ssupikuus

Basio Root Cause Training Day 1

1. Situation Appraisal Day 1

2. Change Analysis Day 1 l 3. Problem Analysis Day 2

4. Definition of Root Cause Day 2 "5 . PSE&G Root Cause Categories Day 2

6. Interpersonal Skills Day 3

7. HPES Overview Intermediate Root Cause Training Day 1

1. Event and Causal Factors Chartine Day 2

2. Potential Problem Analysis Day 2

3. Decision Analysis Day 3

4. Int,erviewing Skills Day 3

5. Root Cause Trendine Advanced Root Cause Training for HPES Evaluators Day 1

1. tFES Terms and Types of Human Performance Day 2

2. Overviiru of Evaluation Techniaues Day 3

3. Interview Techniques, Procedures and Design !

Factors ,

Day 4

4. Checklist Form and Class Exercise \

Day 5

5. Exercise Conclusion, Presentations and Critique Advanced Root Cause Tr i mining for Nuclear Department Professionals (Esch topic is a specialized five--day program)

1. MORT i

2. Accident / Incident Investiestion *1ethods

3. SAT (cc=muniestino Rec -- M tions)

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l g-i INTEGRATED SELF ASSESSMENT MANAGEMENT PROGRAM A

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OBJECTIVE DEVELOP, IMPLEMENT AND MAINTAIN AN ONGOING NUCLEAR-DEPARTMENT SELF ASSESSMENT PROGRAM l

TO INTEGRATE AND EVALUATE THE RESULTS OF ASSESSMENT ACTIVITIES CONDUCTED BOTH INTERNALLY AND EXTERNALLY.

l l

___._____.__.._____.____m.

1

/

SELF ASSESSMENT MANAGEMENT PROGRAM ELEMENTS

+ DEFINE " IDEAL" SELF ASSESSMENT PROGRAM

+ COMPARE " IDEAL" TO CURRENT ACTIVITIES IDENTIFY REDUNDANCIES IDENTIFY VOIDS

+ ELIMINATE REDUNDANCIES AND EARMARK AVAILABLE RESOURCES TO FILL VOIDS

+ DEVELOP MANAGEMENT PROGRAM AND PROCESSES IDENTIFY RESPONSIBILITIES DEVELOP A 5-YEAR SELF SELF ASSESSMENT MANAGEMENT PLAN DEVELOP SELECTION AND PRIORITIZATION CRITERIA IDENTIFY PERFORMANCE INDICATORS DETERMINE COORDINATION METHODOLOGIES DEVELOP PROCEDURES AND TRAINING REQUIREMENTS

+ IMPLEMENT MANAGEMENT PROGRAM DEVELOP AND IMPLEMENT TRANSITION PLAN l

ASSIGN RESOURCES AND RESPONSIBILITIES TRAIN RESOURCES IMPLEMENT 5-YEAR PLAN

+ CONTROL MANAGEMENT PROGRAM HONITOR AGAINST PERFORMANCE INDICATORS MODIFY PROGRAM AS REQUIRED MODIFY 5-YEAR PLAN AS REQUIRED SAMP006

, s A

SELF ASSESSMENT PROGRAM SCOPE

" IDEAL" SELF ASSESSMENT PROGRAM SCOPE b

NSR REVIEWS OE INPO SELF E PROGRAM ASSESSMENTS ASSESSMENTS l

4 QA SSFRs AUDITS

, b SURVEILLANCE l

l v.

l

/

9 4

SURVEY INTERNAL ORGANIZATIONS

+ NUCLEAR DEPARTMENT

+- INTERNAL AUDITING

+ ENVIRONMENTAL AFFAIRS

+ RESEARCH & TESTING' LABORATORY i

_ _ _ _ _ . _ . __ i

r4 ja

., P _

x.

SURVEY EXTERNAL ORGANIZATIONS e

+ DOMESTIC UTILITIES '

+ FOREIGN UTILITIES

, + NUCLEAR INDUSTRY & NON-NUCLEAR INDUSTRY

+ NATIONAL' LABORATORIES

+ DOE FACILITIES

+ NRC

+ INPO 1

+ NUCLEAR INSURERS

- _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _

ML20247B665

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