ML15244A226
| ML15244A226 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 04/03/1987 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8704130731 | |
| Download: ML15244A226 (38) | |
Text
REGULATOR'*NFORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NBR:8704130731 DOC.DATE: 87/04/03 NOTARIZED: NO DOCKET #
FACIL:50-000 Generic Docket 05000000 50-269 Oconee Nuclear Station, Unit 1, Duke Power Co.
05000269 50-270 Oconee Nuclear Station, Unit 2, Duke Power Co.
05000270 50-287 Oconee Nuclear Station, Unit 3, Duke Power Co.
05000287 50-369 William B. McGuire Nuclear Station, Unit 1, Duke Powe 05000369 50-370 William B. McGuire Nuclear Station, Unit 2. Duke Powe 05000370 50-413 Catawba Nuclear Station, Unit 1, Duke Power Co.
05000413 50-414 Catawba Nuclear Station, Unit 2, Duke Power Co.
05000414 AUTH. NAME AUTHOR AFFILIATION GRACE.J.N.
Region 2, Office of Director RECIP. NAME RECIPIENT AFFILIATION TUCKERH.B.
Duke Power Co.
SUBJECT:
Forwards summary of i70306 Ung meeting re recent events &
enforcement issues that resulted in concerns about effectiveness of engineering support & interface &
communications between design & operations for utils.
DISTRIBUTION CODE: IE45D COPIES RECEIVED:LTR I ENCL SIZE:_ 3 7 TITLE: Summary of Significant Meeting uith Licensee NOTES:AEOD/Ornstein:1cy.
05000269 AEOD/Ornstein:1cy.
05000270 AEOD/Ornstein:icy.
05000287 LPDR 2cys AMDTS to FSAR. ASLB icy.
05000413 LPDR 2cys AMDTS to FSAR. ASLB icy.
05000414 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL pD2-3 LA 1
0 PASTISH 1
1 HOOD,D 1
1 JABBOURK 1
1 INTERNAL: AEOD/DOA 1
1 AEOD/DSP/TPAB 1
1 DEDRO 1
1 NRR/ADT 1
1 NRR/DLPG/GAB 1
1 NRR/DREP/EPB 1
1 NRR ILRB 1
1 OGC/ROED 1
1 R
L 02 1
1 RON2 FILE 01 1
1 EXTERNAL: LPDR 3
3 NRC PDR 1
1 NSIC 1
1 NOTES:
4 4
TOTAL NUMBER OF COPIES REGUIRED: LTTR 23 ENCL 22
APR 0 31987 Duke P er Company ATTN: /Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- DUKE POWER COMPANY - DOCKET NOS. 50-269, 50-270, 50-287, 50-369, 50-370, 50-413, AND 50-414 This letter refers to the meeting conducted at our request in the NRC Region II Office on March 6, 1987.
This was a management meeting to discuss recent events and enforcement issues that resulted in concerns about the effectiveness of engineering support and the interface and communications between design and operations for the Duke nuclear units.
Enclosed is a summary of the meeting topics.
It is our opinion that this meeting was beneficial, and provided for a better understanding of Duke Power Company's (DPC) management controls and self-evaluation of those controls.
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2 Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this matter, we will be pleased to discuss them.
Sincerely, J. Nelson Grace Regional Administrator
Enclosures:
- 1. Meeting Summary w/1 Attachment
- 2. Meeting Agenda
- 3. List of Recent Issues
- 4. Duke Power Company Handout (cc w/encls:
See page 2) 6704130731 870403 PDR ADOCK 05000269 P
APR 0 3 198,7 Duke Power Company 2
.c w/encls:
H. Owen, Executive Vice President, DPC
/. B. Priory, Vice President, Design Engineering
. S. Tuckman, Station Manager, McGuire V4. W. Hampton, Station Manager, Catawba
.cc-w/encls:
'J. M. Taylor, Director, OIE
. N. Jabbour, NRR D. Hood, NRR
/vRC Resident Inspector Document Control Desk State of South Carolina RII RH R
RII RI RII TPee les VBrowlee Reyes i son GJenkins Ernt 3/ '\\/87 3/ 1/87
/al/87 3/74/87 3/41/87
/87
ENCLOSURE 1 MEETING
SUMMARY
Licensee:
Duke Power Company Facilities:
Oconee, McGuire and Catawba Docket Nos.:
50-269, 50-270, 50-287, 50-369, 50-370, 50-413 and 50-414 A management meeting was held in the NRC Region II Office on March 6, 1987, to discuss recent events and enforcement issues that resulted in concerns about the effectiveness of engineering support and the interface and communications between design and operations for the Duke nuclear units.
J. Nelson Grace discussed the NRC concerns as noted in Enclosures 2 and 3 to the letter of transmittal and expressed the desire to know how Duke perceived these concerns and what their self-evaluation showed.
H. B. Tucker discussed how Duke is unique in that they design, build and operate their facilities. Also, what may be perceived as a weakness, as their organization does not conform to a standard, may indeed be a strength as the organizations are closer than if they dealt with outside organizations. Duke's method of indoctrination of their personnel to encourage openness in bringing forth problems and improvements was related as was their methodology of monitoring performance.
G. E. Vaughn spoke of operations; M. 0. McIntosh spoke of support; R. B. Priori compared their program to several ANSI standards and noted strengths and weaknesses.
He discussed their implemented corrective actions and their programs to increase support to the stations.
The presentation by Duke representatives focused on the recent issues at the Duke plants and to the Region II concerns as noted in Enclosures 2 and 3 of the transmittal letter. The scope and depth of the detailed discussions were the categorization of events as they related to quality of operations, valve reliability, and quality of design; areas requiring improvement; quality of operations improvement; maintenance improvements; procedure improvements; advanced training facilities; valve improvement program and system performance improvements.
Further breakdown of the Duke presentation is provided in the Duke handout for the meeting, Enclosu'e 4 to the letter of transmittal.
The NRC staff acknowledged the extensive resources and capabilities of Duke, that they have also recognized the problems we identified, and that they are implementing corrective actions and developing program enhancements to minimize the likelihood of occurrences of similar events. The NRC expects its licensees 2
to promptly evaluate and correct problems they identify.
However, the staff emphasized that significant improvements, are needed.
The several subject issues reflect an unacceptable level of compliance to NRC requirements.
More attention must be provided to the interactions between the engineering organization and various groups within Duke's plant staff to ensure design and analyses are correct; that operations has sufficient information to operate the equipment within the design basis; that engineering has sufficient information to adequately provide equipment that will fulfill the design basis under all operational conditions; that operations has sufficient expertise available to address problems concerning operability; and that engineering and plant personnel recognize the full effect of personnel actions or component conditions on related systems and plant operations.
One area of particular concern expressed by J. N. Grace was that it was not always clear to the staff that there was timely, clear cut, and straight forward communication between Duke's organizational groups regarding system or component degradation, operability, and justification for continued operation.
The meeting concluded with all parties stating that communication is
.important and we should strive to improve our communications.
Attachment:
Attendance List
ATTACHMENT ATTENDANCE LIST MANAGEMENT MEETING MARCH 6, 1987 NRC Attendees: J. N. Grace, Regional Administrator M. L. Ernst, Deputy Regional Administrator L. A. Reyes, Director, Division of Reactor Projects A. F. Gibson, Director, Division of Reactor Safety Licensee Attendees: H. B. Tucker, Vice President, Nuclear Production Department R. B. Priory, Vice President, Design Engineering G. E. Vaughn, General Manager, Nuclear Stations, Duke Power Company (DPC)
M. D. McIntosh, General Manager, Nuclear Support N. A. Rutherford, Supervisor Licensing
ENCLOSURE 2 MEETING AGENDA DUKE POWER COMPANY MARCH 6, 1987
- 1. Discussion of Region II concerns, based on several events at each of Duke's Nuclear Power stations, as to the adequacy and effectiveness of management control systems in the areas of plant operations, engineering support and of communications between operations and design to assure that:
operations has sufficient information to operate the equipment within the design basis engineering has sufficient information to adequately provide equipment that will fulfill the design basis under all operational conditions operations has sufficient expertise available to address problems concerning equipment operability Engineering and Plant personnel recognize the full effect of actions or component conditions on related systems and plant operations.
- 2. Duke Power Company's response to the expressed concerns with regard to:
their judgements as to the possible root cause of these events their planned action to improve the situation
- 3. General Discussion
- 4. Wrap-up
ENCLOSURE 3 The following is a list of recent issues which form the basis for our concern.
- 1. McGuire - Nuclear Service Water System Pump failed surveillance test (degraded).
Both units Service Water Systems attempted to be cross tied.
Subsequent inspection determined system degraded due to fouling.
Engineering and operations response to the safety system importance was not appropriate in that the schedule was much too long based on system importance. Consequences of single failure (pipe rupture) not fully understood by operations.
- 2. Oconee - Safety System Functional Inspection EFW System pump runout and degradation could occur during anticipated events.
Engineering/Operations interface not appropriate in that procedures were not adequate to support engineering's statement of relying on immediate operator action.
- 3. Oconee - Emergency Condenser Cooling Water System Loss of siphonage which is needed for operation of the low pressure service water system.
Inadequate time duration for surveillance test to assure operability under all design conditions and Technical Specifications.
(1 2
Engineering and plant personnel failed to recognize the effect of low lake levels on related systems and plant operations even though Technical Specification allowed operation at lower levels than the problem occurred.
- 4. Catawba - Depressurization Event The PORV controller at the shutdown panel did not operate the same as the controller in the control room, although they were physically identified.
Remote Shutdown Panel design changes were not properly transmitted to operations.
Temporary instrument labeling by operations was not correct.
Subsequent operations of the panel produced exact opposite of intended effect.
Engineering/Operations interface was inadequate concerning the details of the design changes and important changes were not incorporated to update procedures.
- 5. McGuire - Containment Spray System Operations management was not cognizant and in control of plant systems and allowed both trains of containment spray to be out of service (repeat recurrence).
Management controls were not in effect which would recognize the effect of actions or component conditions on related systems and plant operations. This concerned commrunications and familiarity with system interactions.
3
- 6. McGuire & Catawba - Containment Air Return Fans Curbing Curbing for the Containment Air Return Fans was removed but not reinstalled at McGuire.
The curbing was never designed nor installed at Catawba.
The curbing is required to prevent flooding of the fan cavity during a LOCA thereby assuring the fans operability.
Operations at McGuire did not understood the significance of the curbing and did not control its removal/replacement.
Engineering at Catawba did not provide the design to assure equipment operability.
- 7. Catawba - Containment Spray Heat Exchanger Degradation Efficiency tests on this system were performed over a two month period, with Engineering and Operations involvement, that showed the system to be degraded below FSAR requirements.
Operations did not promptly recognize the significance of the low efficiency test data (i.e., systems not operable) nor did either Engineering or Operations expeditiously move to resolve the problem.
- 8. Oconee - Appendix R, Letdown Coolers The "A" letdown cooler isolation valves were provided fire protection; however, the "B" letdown cooler valves were not provided fire protection.
Engineering determined that operations would not use the "B" letdown cooler and thus did not adequately understand the way operations intended to operate this system nor the plant requirements.
Operations, not only uses the "B" letdown cooler, but must if "A" is out of service.
Engineering/Operations interface breakdown.
ENCLOSURE 4 DUKE POWER COMPANY
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CATEGORIZATION OF EVENTS
- QUALITY OF OPERATIONS EMERGENCY CONDENSER COOLING WATER SYSTEM (ONS)
NUCLEAR SERVICE WATER SYSTEM (MNS)
VOLUME CONTROL TANK OUTLET VALVES (MNS)
CONTAINMENT SPRAY SYSTEM (MNS)
VITAL BATTERIES (MNS)
AIR RETURN FANS (MNS)
CONTAINMENT SPRAY HEAT EXCHANGER (CNS)
- VALVE RELIABILITY SAFETY SYSTEM FUNCTIONAL INSPECTION (ONS)
NV-7, NI-9 & NI-10 SIZING AND SETTING (MNS)
LIMITORQUE WIRING ROTORK TORQUE SWITCH SETTINGS e
QUALITY OF DESIGN EMERGENCY CONDENSER COOLING WATER SYSTEM (ONS)
SAFE SHUTDOWN FACILITY (ONS)
SAFETY SYSTEM FUNCTIONAL INSPECTION (ONS)
HP-4, LP-1 AND LP-2 APPENDIX R COMPLIANCE (ONS)
NI-9 AND NI-10 SIZING (MNS)
UNIT 2 LOSS OF CONTROL ROOM TEST (CNS)
AIR RETURN FANS (CNS)
AREAS REQUIRING IMPROVEMENT e
GUIDANCE FOR PROMPT TREATMENT OF DEGRADED CONDITIONS
- QUALITY OF PROCEDURES e
QUALITY OF TESTING e
MANAGEMENT AND SUPERVISORS INVOLVEMENT IN DAY-TO-DAY WORK ACTIVITIES
- DETAILED KNOWLEDGE OF SYSTEM DESIGN BASES
- VALVE MAINTENANCE e
QUALITY OF DESIGN REVIEWS
- QUALITY OF DESIGN DOCUMENTATION e
DESIGN -PRODUCTION INTERFACE
QUALITY OF OPERATIONS IMPROVEMENTS
- ProfessionaliSm
- System "Expert" Concept e Operability Directive e
Employee Training and Qualifications System I Technical Specification Practical Application Training
PR 0 FESSI 0 NALISM e Professionalism is a Brood Expection of All Employees - Port of our Company Culture e Emphasis on Professionalism Presented in Employee Orientation Meetings
- Department Guidance Document Developed to Establish the Standard for Control Room Professionalism e Specific Actions/Meetings with the Management Supervisory Team at McGuire
0 0
SYSTEM "EXPERT" CONCEPT
- Individual Responsibility for System(s)
- Extensive Training in System Design Emphosizing the System's Safety Function e Reliability and Efficiency Assurance
@ Oversight of Operations, Testing, and Maintenance Activities
@ Interface with Other Departments and Outside Groups for System Activities
OPERABILITY DIRECTIVE
- Standardized Guidance for Making Operability Determinations e Pre Planned Approach to Handle Cases Requiring Evaluation a RO/SRO Training and Simulator Activities Will Incorporate Guidance
EMPL 0 YEE TRAINING AND Q UALIFICATI 0 NS SY STEM a The Systematic Approach Concept was Adopted in 1983 e Prepares Employees to Perform Tasks With a High Degree of Quality e
Two Major Components: Training and Qualification e Accreditation Status:
Current Scheduled (3/25/87)
Oconee 4
6 McGuire 4
6 Catawba 8
2
TECH NICAL SPECIFICATI 0 N PRACTICAL APPLICATIO0N TRAINING e Specific Training Program Focusing On the Practical Application of Technical Specifications to Plant Situations
@ Request to Production Support Department Has Been Made e Training to Begin at McGuire on May 25, 1987
@ The Value of Similar Training for SRO's at Catawba and Oconee is Under Evaluation
SELF ASSESSMENT EVALUATIONS o
PROCEDURES TRAINING FACILITIES VALVE IMPROVEMENT PROGRAM RESOURCES
_SySTM PERRACEa _PR OVEETS PERFORMANCE MONITORING PROGRAM p
PREDICTIVE MAINTENANCE MONITORING PROGRAM
DUKE/INPO PILOT SELF-ASSESSMENT PROGRAM CATAWBA SELF-ASSESSMENT PARTIALLY COMPLETE PLAN TO CONDUCT SELF-ASSESSMENTS AT OCONEE AND MCGUIRE
C RENTS NPD PROCEDURE DEVELOPMENT GUIDE COMPLETED IMPROVE PROCEDURE QUALITY REDUCE HUMAN PERFORMANCE ERRORS GO BEYOND INDUSTRY STANDARDS INPO ANSI NRC NUREGS EPRI NUMARC WORK SP......
6000 PROCEDURES UP TO 40 HOURS PER PROCEDURE S~EDULE PRIORITY 1 PROCEDURES BY 1989 ALL PROCEDURES BY 1994
ADVANCED TRAINING FACILITIES MT. HOLLY FACILITY PLANNED TO SUPPORT MCGUIRE AND CATAWBA NEEDS OCONEE FACILITY PLANNED TO SUPPORT THAT LOCATION'S SPECIFIC NEEDS
-AT Fneral Arrangement -
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ADVANCED RAINING FACILTES 38,000 SQUARE FEET FOR OCONEE ATF 49,000 SQUARE FEET FOR MT, HOLLY EEAIuRES MOCK-UP AREA FOR I
RCP I
CRDM I
RX Head MECHANICAL MAINTENANCE AREA FOR 6
Tools I
Pumps I
Valves I
Snubbers I&E MAINTENANCE AREA FOR I
ICS Equipment a
Batteries I
BreaKers I
MCC Equipment I
Motors TEST LOOP AREA FOR PRESSURE TESTING PUMPS AND VALVES CLASSROOMS LIBRARY BUDGETED TO BEGIN CONSTRUCTION 1988 COMPLETE 1989
VALVE IMPROVFMFNT PROGRAM U
PROGRAM MANAGEMENT LEAD INDIVIDUALS -IDENTIFIED RESOURCES AVAILABLE 7 NPD ENGINEERS 10 DESIGN ENGINEERS TASK FORCE ESTABLISHED 1985 RESOLUTION OF TECHNICAL GENERIC ISSUES I
Packing I
Vendor Qualifications I
Cleanliness Standard I
Special Tooling I
Innovations
.4 Spare Parts I
Quality Monitoring a
MOV Testing
e e
QUALITY TEAM CONCEPT I
Monitor Critical Parameters Problem Identification Finishes, Cleanliness Blue Checking ReassemOly, Retorquing Special Problem Resolution DEDICATED CREWS REWORKED VALVES REDUCED FROM APPROXIMATELY 15% TO < 4%
RESOURCES-FO MAINTENANCE IMPLEMENTATION I
NPD 300 MAINTENANCE PERSONNEL PER SITE CMD 300 MAINTENANCE PERSONNEL PER SITE CMD 600 CONSTRUCTION PERSONNEL PER SITE AVAILABLE
SYSIEM PERFORMANCE IMPROVEMFENS
sySTEM PEFORMCE IPOEET PERFORMANCE MONITORING PROGRAM P
PURPOSE IMPROVE STATION RELIABILITY BY MONITORING KEY SYSTEM AND COMPONENT PERFORMANCE o MONITORING TECHNIQU System Porameter Trending Component Performance Trending Vibration Monitoring Valve Losses Performance Wolkdowns Energy Balances a
SCHEDULE PROGRAM INITIATED 1985 FULLY IMPLEMENTED BY 1988
TOPTORM T1a OPP ORMp
OLD BUSINESS NEW CONSTRUCTION MODE e
QUALITY PRODUCT SPECIALIZATION REASONS FOR CHANGE NEW CONSTRUCTION COMPLETE RECOMMENDATION OF NUMEROUS TASK FORCES, COMMITTEES, WORKING GROUPS REGULATORY DIFFICULITIES DESIRE TO BE PROACTIVE INDUSTRY INITIATIVES(SILLIAN REPORT)
- NEW BUSINESS SUPPORT MODE SMALL MODIFICATIONS TO COMPLEX PLANTS INTENSE REGULATORY SCRUTINY QUALITY PRODUCT (DOCUMENTED)
FLEXIBILITY STRENGTHENS EXISTING MODIFICATION PROCESS CENTRALIZED/RETRIEVABLE
DESIGN QA CMD ENHANCEMENT OF DESIGN PSD NPD
PROJECTED/EXPECTED RESULTS
- INTEGRATED COMMUNICATION DED/CMD/NPD
- HARDEN DESIGN INTERFACE
- DOCUMENTATION OF ENGINEERING REASONS/EVALUATIONS
- AUDITABLE DOCUMENTATION
- ANSI N45.2.11 COMPLIANCE
- SELF-INITIATED AUDITS
PROJECTED/EXPECTED RESULTS (CONT)
DESIGN INPUTS DEFINITION/DOCUMENTATION
- SAFETY REVIEWS/EVALUATIONS
- DESIGN FUNCTIONAL TEST REQUIREMENTS
- LEGIBLE PRODUCT
- CONSTRUCTABLE/MAINTAINABLE/OPERABLE PRODUCT