ML20214J261
| ML20214J261 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/13/1986 |
| From: | Birchell R, Knightly J, Stewart D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20214H850 | List:
|
| References | |
| SWEC-SQN-40, SWEC-SQN-40-R, SWEC-SQN-40-R00, NUDOCS 8612010232 | |
| Download: ML20214J261 (19) | |
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TVA ENFLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-40 SPECIAL PROGRAN REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 4
TITLE: INPO Naintenance Performance Data Survey Data Survey - 1985 REASON FOR REVISION: N/A SWEC
SUMMARY
STATENENT: The items in this report were identified by the Institute of Nuclear Power Vperations (INPO) and were included in the Stone &
Webster Engineering Corporation (SWEC) systematic analysis. All items evaluated within this report were verified to be adequately addressed and can be closed following implementation of planned improvements.
PREPA*ATION PREPARED BY:
Ylf EM/L f [' B tYbJY // 9 L, 1IdNIATURE DATE !
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REVIEWS i PEER: i MdL tdaML SIGNATURE I akI86 DATE i
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SIGNETURE DATE CONCUnneuCES CEG-H: M L/ 71/df6.
SRP: c =44, k, N I 'N SIGNATURE DATE SIGNATURE
- DATE
! APPROVED BY:
MUS/2b ECSP MAN (GER ann DATE ah MANAGER OF flUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's siEnsture denotes SRP concurrences are in files.
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OTiiER SITES CEG Element
Title:
INPO Maintenance Performance Data Survey-1965 SWEC Concerns: A02850909021-003
! A02850909021-006 l
l Source Document: INPO Maintenance Performance Data Survey Report Number: SWEC-SQN-40 I
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Evaluator: /088
'R. C. Birchell #Dat'e Reviewed Dy: D W
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J. J. Knightly Date Approved Dy:
A. G. Debbige ge
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Report SWEC-SQN-40
- 1. INTRODUCTION In November 1984, the Institute for Nuclear Power Operations (INPO) provided its -first report of plant performance data to member utilities. However, this report had minimal data uniquely related to maintenance. The developing interest in maintenance caused INPO to include maintenance performance indicators in the 1985 program. In response to this interest, and with the assistance of the NUMARC Maintenance Working Group, a preliminary list of maintenance related parameters was developed for this purpose.
In early 1985, ten parameters from the preliminary list were identified as potential indicators of maintenance performance and were considered to be reasonably retrievable from each station's records. Data for three indicators were available to INPO through existing sources. In May 1985, data for the remaining seven indicators were received through a mail survey of member utilities.
Two items were addressed as issues in the Stone & Webster Engineering Corporation (SWEC) systematic analysis as follows:
A02850909021-003, High Number of Unplanned Scrams While Critical Due to Maintenance 402850909021-006, High Percentaae of Preventative Maintenance Items i Overdue Information on the background, corrective actions taken, verification methodology, verification analysis, completion status, and pertinent references for these issues is included in this report.
II. VERIFICATION OF SWEC ISSUE A. Background
- 1. A02850909021-003, High Number of Unplanned Scrams While Critical Due to Maintenance i
The INPO report (reference 1) identified the industry median as three, while Sequoyah Nuclear Plant (SQN) unit 1 had eight and unit 2 had five.
- 2. A02850909021-006, High Percentage of Preventative Maintenance Items Overdue The INPO report identified the industry median as 8.5 percent while SQN had 23.5 percent.
Page 1 of 5
8 .- Corrective Actions Taken
'1. A02950909021-003, High Number of Unplanned Scrams While Critical Due to Maintenance SQN provided the following information in the SQN Nuclear Performance Plan, Appendix 2, as follows:
In the past, the number of reactor trips per year has been above the industry average for a two-unit plant.
Management action to address this problem and to achieve the goal of less than 3 trips per unit por year (INPO goal adopted by NRC and Nuclear Utility Management and Resources Committee (NUMARC)) has been and is being taken.
Sequoyah had reduced the number of unplanned reactor trips and engineered safety feature (ESF) actuations experienced since initial operation through positive management and staff attention to the root causes of these trips and actuations as discussed herein. There is strong management involvement and interest in work activities and an attitude that any unplanned trip is unacceptable, not only as an unnecessary challenge to safety systems, but also as a reduction to the power generation goals for the facility.
Supervisors inform their staffs of the plant goals and encourage the individuals performing work to think through each aspect of their jobs to minimize the potential of a reactor trip. Management also insists on a consistent, thorough investigation of root causes and implementation of corrective actions.to prevent recurrence. Actions addressing the causes of reactor trips and ESF actuations have resulted in increased awareness by employees of the need for improved coordination of work activities and attention to detail as well as in revised instructions and design changes to plant protection systems. The existing policies are expected to further minimize the number of unplanned trips and ESF actuations to meet plant goals.
- To further support reactor trip reductions, SQN is
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participating in Westinghouse Owner's Group-Trip Reduction
, Assessment Program (WOG-TRAP). In' support of this program
[ SQN has provided information on trips experienced since initial startup for use in the Westinghouse (W) Plant Trip Data Base. The results of the data base have been reported in WCAP 10948, "U.S. W Inadvertent Plant Trip Experience."
Findings of the report give detailed reasons and percentages of the root causes of the inadvertent reactor trips. Phase II of the data base will examine specific j activities in the affected areas noted in WCAP 10948. SQN has also sent a licensed reactor operator experienced in manual feedwater control of steam generator levels to a
! WOG-TRAP conference to investigate feedwater initiated l transients and short-term remedial actions which have been.
I successfully implemented on W plants. A final report is to be generated to identify specific sources of problems and strategies that operators employ to avoid or deal with these problems.
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- 2. A02850909021-006, High Percentage of Preventative Maintenance
' Items Overdue SQN provided the following information in the SQf; Nuclear Performance Plan,Section II.4, as follows:
To evaluate maintenance performance, a detailed review and reassessment of maintenance performance beginning in March
.1984 was performed by TVA. The review included findings contained in the most recent Systematic Assessment of Licensee Performance (SALP) report, NRC violations, Licensee Event Reports (LERs),.the latest INPO evaluation, internally identified findings, and applicable Davis-Besse issues.
While specific details vary, the maintenance issues addressed in this section share one underlying root cause:
lack of management attention as evidenced by inconsistent management involvement, accountability and control of maintenance. This lack of management attention occurred at all levels and was chiefly because of the increased attention required to put in place a new plant maintenance organization responsible for an expanded scope of work during the previous SALP reporting period. A contributor to this lack of management attention was the fact that several maintenance supervisory positions were temporarily filled because of management training assignments (although experience was gained by lower level supervisors, having temporary supervisors in line positions contributed to the poor management control).
To further assess the maintenance programs at SQN, the Manager of Nuclear Power directed TVA's Nuclear Managers Review Group (NMRG) to conduct a comprehensive assessment of corrective and preventative maintenance practices at SQN. This review may trigger changes in maintenance procedures, organizational realignments, and revisions to position descriptions. Changes in SQN's maintenance program and practices, which TVA determines to be needed, will be made.
Specific questions that NMRG were asked to address included:
Do procedures clearly describe the entire process of
- accomplishing both corrective and preventative maintenance?
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Is the work well planned and job-stepped in a manner that is clearly understood in the field?
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- Is the process from problem recognition to corrective action
, implementation timely and efficient?
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- Does maintenance personnel have a basic under standing of the j plant equipment and systems to ensure they are aware of the j importance or safety impacts of their work?
TVA will provide more details on its program to upgrade nuclear maintenance following the NMRG review and the formulation of a plan l of action based on that review.
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Maintenance management involvement at SQN is being increased by stressing personnel accountability, through better review and improvement of maintenance procedures, by placing more emphasis on trending equipment failures and preventative maintenance, by requiring improved training of craft personnel, and by other management activities to assess the reliability of safety-related equipment before startup. Monitoring and use of established performance indicators will permit maintenance supervision and plant management to better recognize and act to correct negative trends in the future.
I Maintenance Work Control System Improvement Background - In May 1985, plant management began evaluating changes to improve SQN's maintenance request (MR) system. The system was based on TVA's past corporate format and approach for requesting maintenance. Often several MRs were needed to complete a single
- job creating additional paperwork for planners and reducing the i time available for scoping and plannir.g the work activity, j Under the system, nontechnical tasks _such as a request to move bookcases were initiated in the same manner as work needed to 3 correct a complex component or plant system problem. Because of I
- this, the MR system was overloaded and not responsive to work
- requiring detailed planning. To enable management to more readily
{ and efficiently direct attention and resources to priority areas, a
] new work request tag / card was implomented as discussed below.
- New Maintenance Request System !
Under the new MR system, maintenance items are requested by
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initiation of a work request tag / card. In addition to requesting l maintenance, the tag / card provides a convenient way to identify deficiencies in the field by placing the tag portion on equipment j needing repair. The card portion containing the description of the l work requested is tracked and ~ evaluated like MRs in the past. Work i not involving safety-related equipment and requiring little
- planning may be authorized and performed utilizing information
, provided on the tag / card. This system facilitates screening of j work requests and the priority of safety-related work.
1 The tag / card system has been well received by Operations personnel i and by Maintenance craftsmen and planners. Use of the tag / card l system has also resulted in improved recognition and
- differentiation between safety-related and nonsafety-related work.
A second phase to improve the maintenance work control system is currently under development. This effort includes development of a work request (WR) supplement forrr. to better accommodate the way i Sequoyah plans and performs maintenance. The new WR supplement, which will be computer printed, is designed to facilitate the
- completion of a multiple craft job without the need for several
! WRs, thus reducing paperwork for planners.
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In addition, a revision to the maintenance work control program has also been made that allows MRs for ASME Section XI valve maintenance to be closed more expeditiously.
C. Verification Methodology The SWEC concerns identified for Employee Concerns Task Group (ECTG) verification were stated, as follows:
RIMS # ISSUE RIMS ITEM A02850909021 High number of RIMS-OO3 unplanned scrams while critical due to maintenance.
A02850909021 High percentage of RIMS-006 4
preventative maintenance items ove rdue .
ECTG reviewed the SQN Nuclear Performance Plan for correspondence related to these issues. This review formed the basis for this verification activity.
D. Verification Activity These items are comparisons of TVA maintenance performance data versus the other member utilities. No formal findings were identified and no recommendations were made by INPO. However, SQN has identified corrective actions to be taken and these actions appear to be adequate for these issues.
E. Completion Status Corrective actions have been identified in the SQN Nuclear Performance Plan. Following implementation of the planned improvements, these SWEC concerns can be closed.
III. References INPO Letter to TVA, dated September 6,1985, P. M. Beard, Jr. , to James P. Darling Page 5 of 5
OPERATIONS CATEGORY Enclosure 3 ECTG WRITER'S GUIDE OPERATIONS (OP) ELEMENT REPORTS NOTES /CONNENTS 1.0 Issue I. Title The brief introduction Characterization Very brief introduction touches on the source of the concerns.
2.0 Susunary I. Title 1. The Conclusions are Very brief introduction towards the end of the findings.
III. Finding (Conclusions) 2. The Conclusions services as a susumery of the findings.
3.0 Evaluators Cover Sheet 1. The printed name of the original evaluator (s) appears on the cover sheet.
- 2. The peer reviewer and CEG-H approval signa-tures are also on the cover sheet.
4.0 Evaluation II. Specific Evaluation Process Nethodology 5.0 Findings III. Findings 1880T
MATERIALS CONTROL E;citsura 3 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT 1.0 Issue I. Introduction Characterization II. Summary of Perceived Problem 2.0 Summary IV. Summary of Findings conclusions (Portion) 3.0 Evaluators Cover Sheet Information 4.0 Evaluation III. Evaluation Process Nethodology S.0 Findings IV. Summary of Findings 6.0 Root Cause V. Root Cause (Collective Significance)** ** Overall Root Cause will not be considered at this report level.
7.0 Attachments / VIII. Attachments List of Concerns Other items included VI. Corrective Actions in Element (To be provided by Reports line organizations)
VII. Generic Applicability 190ST e <-- ,., . - . . . . - . . ,. -.
CONSTRUCTION CATEGORY Enl:stra .3 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT 1.0 Issue I. Introduction Characterization II. Summary of Perceived Problem 2.0 Summary IV. Summary of Findings conclusions (Portion) 3.0 Evaluators Cover Sheet Information 4.0 Evaluation III. Evaluation Process Nethodology 5.0 Findings IV. Summary of Findings 6.0 Root Cause V. Root Cause (Collective Significance)** ** Overall Root Cause will not be considered at this report level.
7.0 Attachments / VIII. Attachments List of Concerns Other items included VI. Corrective Actions in Construction Element (To be provided by Reports line orgainzations)
VII. Generic Applicability 1905T
ENGINEERING CATEGORY Encl: sure 3 i
Page 1 of 2 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT 1.0 Issue 1. Characterization of Issue (s)
< Characterization 2.0 Summary 9. Discussion, Findings and Conclusions 3.0 Evaluators Cover Sheet Information 4.0 Evaluation 8. Evaluation Process Process 5.0 Findings 9. Discussion, Findings, and Conclusions 6.0 Root Cause (Collective Significance) H H Overall Root Cause will not be considered at this report level.
7.0 Attachments / Attachments as required i List of Concerns Other items included 2. Have issue (s) been identified in Engineering Element in another systematic Reports analysis?
- 3. Document nos., tag nos.,
locations or other specific descriptive identifications stated in element.
- 4. Interview files reviewed
- 5. Documents reviewed related to the element 1992T
ENGINEERING C"TEGORY Enclosura 3 Page 2 of 2 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT Other items included in Engineering Element 6. What regulations, licensing Reports commitments, design require-(cont'd) ments, or other apply or control in this area?
- 7. List requests for information, meetings, telephone calls, and other discussione related to element.
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EncitCtre 3 ECTG WRITER'S GUIDE OPERATIONS (OP) ELNENT REPORTS NOTES /COINEENTS 6.0 Root Cause IV. Root Cause 1. At the element level (Collective Significance) the Root Cause is often not identifible.
- 2. Collective significance is not addressed at the element report level.
7.0 Attachments / II. Specific. Evaluation 1. A list of the concerns List of Concerns Nethodology with text are included within this section.
- 2. Other reports are sometimes attached.
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Enclosure 4 Page 1 of 6 SEQUOYAH EMPLOYEE ELEMENT REPORT CONCERN NUMBER ISSUE Construction 10703 IN-85-707-002 Bending (Initial) IN-85-740-002 Equipment / Material IN-85-740-003 IN-85-773-002 IN-85-831-001 Construction 10603 IN-86-183-001 Bolting-Material (Initial) IN-85-021-X04 Compatibility IN-85-824-001 Note: Report 10603 and Concerns IN-86-183-001, IN-85-021-X04, and IN-85-824-001 were added after 9/26/86.
Construction 11301* IN-85-031-001* Design of Plates (Initial) IN-85-109-X04 OE-QMS-8*
IN-85-033-001*
IN-85-103-001*
Note:
- Report 11301 and Concerns IN-85-031-001, IN-85-033-001, IN-85-103-001 and OE-QMS-8 were added after 9/26/86.
Operations 30202 XX-85-122-004 Five Percent Low (Initial) XX-85-122-005 Voltage Problems MAS-86-004 Engineering 21501 00-85-005-009 Seismic Criteria (Final)
Note: An initial report was not necessary. This will be the only submittal for EN 21501.
Engineering 21510 LDa-85 001 Feedwater Heater (Final) Monorail Design Note: An initial report was not necessary. This will be tha only submittal for EN 21510.
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Enclosure 4 Page 2 of 6 SEQUOYAH EMPLOYEE ELEMENT EEPORT CONCERN NUNBER ISSUE Engineering 23202 IN-85-021-006 Carbon Steel vs (Final) XX-85-127-002 Stainless Steel Drain Pipes Note: An initial report was not necessary. This will be the only submittal for EN 23202.
Operations 30303 IN-85-802-001 Accuracy of Safety-(Final) IN-86-079-002 Related Instruments Note: Initial report transmitted 10/21/86 Operations 30702 XX-85-018-001 Handling Safeguards (Final) IN-85-915-003 Information Note: Initial report transmitted 9/23/86 Operations 31001 SQP-85-003-001 Operation Program and (Final) SQP-85-003-002 Procedures Inadequate XX-85-067-001 SQN-86-013-002 SQP-86-010-001 XX-85-022-001 IN-85-933-001 IN-85-933-010 XX-85-007-002 Note: Initial report transmitted 9/15/86.
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Enclosure 4 Page 3 of 6 SEQUOYAH EMPLOYEE ELEMENT REPORT CONCERN NUMBER ISSUE Operations 31002 IN-85-289-001 Operator Qualifications (Final) IN-85-767-006 IN-85-894-001 IN-86-209-013 XX-85-048-002 I
XX-85-093-001 XX-85-093-002 XX-85-093-003 WI-85-060-001 Note: Initial report transmitted 9/23/86.
Operations 31104 SQP-86-009-001 llealth Physics Policies, (Final) SQP-86-009-002 Practices, and Management XX-85-084-001 Control XX-85-066-001 XX-85-009-002 WI-85-038-001*
XX-85-015-001 XX-85-026-001 XX-85-063-001 XX-85-028-X02 XX-85-028-X03 XX-85-098-002 I-86-238-SQN JLH-86-003 JMA-85-001 RII-85-A-0064
- Concern WI-85-038-001 was added after 9/26/86 Note: Initial report transmitted 11/4/86.
Material Control 40512 XX-85-120-003 Containment Vessel Plate (Final)
Note: Initial report transmitted 10/3/86.
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- Enclosure 4
/ Page 4 of 6 SEQUOYAH , ', EMPLOYEE <; ,
1 ELENENT REPORT CONCERN 7 -
NUMBER ISSUE .,'i si Quality Assurance 80404 In-86-090-002 f / , Program Implementation '^
IN-86-087-003*- - .
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- Concern IN-86-087-003 is contained in Subcatkgory 80401.
I; Note: Initial report was not necessary. This,will be the only submit'tal' for
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QA 80404. ,
'. , y,J SWEC-01 A02-840917-0051001 AFWS and Diesel I' -
(Final) A02-840917-005-002 Generator Proce'dures" A02-840917-005-003 - .
A02-840917-005 004 A02-840917-005-005 j' ,/, r, A02-840917-005-006 Note: An initial report was not necessary. This will be the only submittal for -
SWEC-01. ,
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SWEC-04 and -10 A02-8410'02 013-002 NRC Assessment" A02-841002.013 009 of Training .
A02-841002-013'-010 4 I A02-841002-013-011 _s-A02-841002-013-012 A02-841123-006-001 '
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Note: An initial report was not necessary. This will be'the only submitta3 for .
SWEC -4 and -10. 'e -
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SWEC-15 A02-850506-006-001- ',,
,, , SQN Nuclear Plant ,
(Final) A02-85050h-006-002 Radiological Emergency i ,
A02-841206-001-001
. Plan ."-
A02-841206-001-002 }"
Note: An initial report was not necessary. This will be the only submittal forc,~.
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SWEC-15. ,
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,1 SEQUOYAH EMPLOYEE ELEMENT REPORT CONCERN
,', NUMBER ISSUE SWEC-16 A02-841214-002-001 Surveillance Instruction
'(Final) A02-841214-002-002 Inadequacy
, A02-841214-002-003 Note: An initial report was not necessary. This will be the only submittal for SWEC-16.
SWEC-17 A02-841214-003-001 Containment Leak Rate (Final Test Failure '
Note: An initial report was not necessary. This will be the only submittal for SWEC-17 SWEC-20 A02-850124-027-001 Inadequate Implementation (Final) A02-850124-027-002 of Fuel Handling Procedures; Untimely Plant Access Procedure.
/-Note: An initial report was not necessary. This will be the only submittal for f SWEC-20.
SWBC-26 A02-850402-002-001 NCR Disposition for (Final) Pressure Transmitter Note: An initial report was not necessary. This will be the only submittal fcr SWEC-26.
I SWEC-37 A02-850806-014-001 Operational Safety (Final) A02-850806-014-002 Verification A02-850806-014-003 A02-850806-014-004 A02-850806-014-005 A02-850806-014-006 o
Note: An initial report was not necessary. This will be the only submittal for SWEC-37.
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SEQUOYAH .
EMPLOYEE ELEMENT REPORT '? L' CONCERN
( *- NUMBER ISSUE 3
x SWEC-38 A02-850809-036-001 Maintenance (Final) A02-850809-036-002 Management A02-850,809-.036-003 i 3
Note: An initial report was<not necessary.. This will be the only submittal for SWEC-38.
SWEC-39 A02-850819-002-001 Sequoyah Emergency (Final) A02-850819-002-002 Management Note: An initial report was not necessary. This will be the only submittal for i SWEC-39.
t SWEC-40 A02-850909-021-003 INPO Naintenance A02-850909-021-006 Performance Data Survey - 1985 Note: An initial report was not necessary. This will be the only submittal for SWEC-40.
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