ML20207P656

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Rev 1 to NRC Systematic Assessment of Sequoyah Nuclear Plant Performance
ML20207P656
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 01/05/1987
From: Gass K, Knightly J, Stewart D
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20207P454 List:
References
SWEC-SQN-55, SWEC-SQN-55-R01, SWEC-SQN-55-R1, NUDOCS 8701160376
Download: ML20207P656 (7)
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TVA LNPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-55

< SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant - Element REVISION NUMBER: 1

-s TITLE:/,NRC Systematic Assessment of SQN Performance I

REASON FOR BEVISION:

t To incorporate TAS and SRP comments.

4 SWEC SU11 MARY STATENENT: The items in this report were identified by the Nuclear Regulatiey Commission (NRC) and were included in the Stone & Webster Engineering Corporation (SWEC) systematic anaylsis. All Items evaluated within this report were verified to be adequately addrassed wittilcorrective actions in progress.

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DATE CONCURRENCE (FINAL REPORT ONLY)

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Title:

NRC Systematic Assessment of SQN Performance SWEC Concerns: A02840907003-002 A07850919005-057 A07850919005-082 A02840907003-003 A07850919005-058 A07850919005-113 A02840907003-004 A07850919005-059 A07850919005-114 A07850919005-008 A07850919005-067 A07850919005-115 A07850919005-014 A07850919005-068 A07850919005-116 A07850919005-015 A07850919005-069 A07850919005-117 A07850919005-016 A07850919005-070 A07850919005-118 A07850919005-017 A07850919005-071 A07850919005-119 A07850919005-020 A07850919005-075 A07850919005-120 A07850919005-037 A07850919005-076 A07850919005-121 A07850919005-038 A07850919005-077 A07850919005-122 A07850919005-039 A07850919005-080 A07850919005-123 A07850919005-056 A07850919005-081 A07850919005-130 Source Documents: NRC Systematic Assessment of Licensee ,

Performance (SALP), 1984, 1985 Report Number: SWEC-SQN-55 Evaluator: N Luo st[Y[Y J. J. Knightly / Date Reviewed by: T [. .b4- /.f '/ 9 6 K. R. Gass Date Approved by: Av /.2/g / P(3 A. G. Debba(e Date' 2199T

SWEC-SQN-55

' NRC SALP Reports 1984, 1985 I. INTRODUCTION The Nuclear Regulatory Commission (NRC) Systematic Assessment of Licensee Performance (SALP) program report for 1985 (reference 1) identified 36 items which were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. In addition, SWEC included 3 items from the 1984 SALP report (reference 2) for a total of 39 items in the following functional areas:

A. Maintenance and Nodifications A07850919005-068, Maintenance and modification training weaknesses

-069, Electrical maintenance training weakness

-070, Nechanical maintenance training not adequate

-081. Failure to schedule. thimble tube cleaning

-116, Nechanical maintenance procedures weak

-117, Failure to control maintenance work activities

-118, overall maintenance quality erratic

-119 Management of maintenance inadequate

-121, Weak controls for post modification tests

-122, Fallare to schedule cleaning during outage

-123, Maintenance and modification problems from inadequate design package development B. Fire Protection A02840907003-003, Fire protection deficiencies A07850919005-017, Appendix R descriptions C. Plant Operations A07850919005-008, Overcrowding of control room

-016. Excessive unplanned reactor trips

-067, R0 and SRO exam pass rates low ,

-082, Fuel assembly damaged

-114, Weak controls over surveillances D. Security A07850919005-080, Increased security violations E. Laboratories A07850919005-058, Analytical laboratories quality controls lacking

-059, Organization and cleanliness in labs poor Page 1 of 3

F. Radiological Controls A02840907003-002, Weakness in emergency preparedness A07850919005-056, Personnel dosimetry violations

-071, Improper wearing of dosimetry

-075. Emergency alarms inaudible

-076, Offsite monitoring teams not coordinated

-077. Emergency supplies / equipment not inspected G. Quality Assurance A02840907003-004, Weakness in QA program A02850919005-015, Lack of procedural adherence

-057, Inadequate records

-113, Failure to complete surveillances H. Administrative Controls A07850919005-037, Delays in correcting nonconforming conditions

-038, Failure to take timely corrective action

-0.*9, High turnover in site director job

-115. Cumbersome procedural interdependencies

-120 Weak recolution of technical nonconformances I. Licensing Activities A07850919005-014, Poor reporting of licensee events

-020 Incorrect interpretation of reporting requirements

-130, Noncesponsiveness to NRC generic letters II. VERIFICATION OF SWEC ISSUES A. Background At the time the 1985 NRC SALP report was communiceted to TVA, both units of the Sequoyah Nuclear Plant (SQN) were already in shutdown because of a planned refueling outage and question '

concerning the environmental qualification of electrical equipment.

SALP reported a wide variety of deficiencies in additional areas.

SQN has remained shutdown to address root causes of these nuclear program problems, and to defino and implement adequate corrective actions.

B. Corrective Actions The transmittal letter for the 1985 SALP report requested diat TVA l submit its plans for correcting SQN problems. In response to this l request, TVA prepared the Sequoyah Nuclear Performance Plan IR1 (reference 4) to describe the corrective actions TVA is taking to l improve SQN's performance. 1 Page 2 of 3

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O Attachment 1 of this report provides the cross references betwetn l each of the SWEC concerns'and SQN's planned improvements as lR1 documented in the Nuclear Performance Plan. l C. Verification Nethodology The Records and Information Management-System (RIMS) numbers, specific statements of issues, and item numbers for the 39 SALP report items included in the SWEC systematic analysis are identified in attachment 2 to this report.

The Employee Concerns Task Group (ECTG) reviewed the SALP report documentatis. and the SQN Nuclear Performance Plan for information concerning the SWEC issues. This review of the pertinent documentation formed the basis for this verification activity.

D. Verification Analysis

, The revised SQN Performance Plan provides an account of the actions I which TVA is taking to correct the SALP-identified problems and to lR1

' improve the nuclear program for SQN. The planned implementation of l improved programs in the areas of maintenance and modifications, fire protection, plant operations, security, plant laboratories,

' radiological controls, quality assurance, administrative controls, and' licensing activities is for the purpose of improving overall plant performance including all areas identified by the SWEC concerns.

E. Completion Status The SWEC concerns are being addressed as part of SQN's overall nuclear performance plan. Following SQN plant startup and effective plant performance, it is expected that the NRC SALP will reflect the SQN improvements. The SWEC concerns can be closed at that time.

III. REFERENCES l '

1. NRC SALP Inspection Report Numbers 50-327/85-22 and 50-328/85-22, i Sequoyah Units 1 and 2, dated September 17, 1985, W. J. Dircks to C. Dean.
2. NRC SALP Inspector Report Numbers 50-327/84-08 and 50-328/84-08, Sequoyah Units 1 and 2, dated June 12, 1984, R. C. Lewis to H. G. Parris.
3. TVA Revised Corporate Nuclear Performance Plan, dated July 22, 1986 (initial issuance March 10, 1986).
4. TVA Revised Sequoyah Nuclear Performance Plan, dated July 17, 1986 (initial issuance November 1, 1985).

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.e Al ACHNENT 1 Analysis of SQN Response to SALP (arranged by functional areas of SWEC concerns)

SWEC CONCERN ISSUE SON PERFORMANCE PLAN SECTION PAGE A. Maintenance & Modifications l

-068 Mair.tenance/Nodification training 4.4 II-63 l

-069 Electrical maintenance training 4.4 II-62 l

-070 Nechanical maintenance training 4.4 II-62 l

-081 Scheduling of outage work 1.2.9 II-20 l

-116 Maintenance procedures 4.2 II-59 l

-117 Maintenance work controls 4.1 II-55 l

-118 Maintenance quality 4.0 II-53 1 4.1.

-119 Naintenance management II-52 l

-121 Post modification testing Appendix 2.5 4 l

-122 Scheduling of outage work 1.2.9 II-20 l

-123 Inadequate design packages for i modification 3.3 II-50 I B. Fire Protection l

-003 Fire Protection deficiencies 8.0 III-37 l

-017 Appendix R deficiencies 8.0 III-37 i C. Plant Operations lR1-t -008 Control room 2.4 II-8 l l -016 Reduced reactor trips Appendix 2.1 1 l

-067 RO and SRO exam pass rates II.2.3.2 II-29 l

-082 Refueling procedures 2.4 II-8 l i -114 Surveillance testing Appendix 2.3 2 1 D. Security 'l

-080 Plant Security Appendix 2.4 3 l

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E. Laboratories 1

-058 Quality controls-Analytical Labs II.2.4 II-34 1

-059 Organization and cleanliness II.1.2.1 II-5 l F. Radiological Controls l I

i -002 Radiological emergency prepardeness Appendix 2.6 4 1

! -056 Radiological controls II.1.2.3 II-7 l L -071 Radiological controls II.1.2.3 II-7 l

, -075 Emergency alarms Appendix 2.6 5 l

) -076 Emergency organization Appendix 2.6 4 l

-077 Emergency faellities and equipment Appendix 2.6 5 l s

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ATTACHMENT 1 (Continued) l J

SWEC CONCERN ISSUE SON PERFORMANCE PLAN l G. Quality Assurance l

-004 Quality control functions II.1.2.6 II-12 l

-015 Procedures II.2.4 II-32 l

-057 Quality documentation Exec. Summary ES-5 l

-113 Performance of surveillances II.1.2.6 II-13 l H. Administrative Controls l

-037 Timely corrective action II.2.5 II-35 l

-038 Timely corrective action II.2.5 II-35 l

-039 Strengthening management II.1.0 II-1 lR1

-115 Procedures enhancement II.2.4 II-32 l

-120 Technical evaluations II.1.2.5 II-9 l I. Licensing Activities l

-014 Licensing support II.1.2.7 II-16 l

-020 Licensing support II.1.2.7 II-16 l

-130 Licensing support II.1.2.7 II-16 l l

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