ML20207S464

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Forwards Four Final Element Repts Addressing Employee Concerns Re Operations,Const & Matl Control & List of Rept Numbers,Related Employee Concerns & Previous Submittal Dates
ML20207S464
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 03/16/1987
From: Mcdonald J
TENNESSEE VALLEY AUTHORITY
To: Harold Denton
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20207S465 List:
References
NUDOCS 8703190495
Download: ML20207S464 (10)


Text

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TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant P. O. Box 800 Spring City, Tennessee 37381 March 16, 1987 5

Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Harold Denton, Director of Nuclear Reactor Regulation In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 EMPLOYEE CONCERNS TASK GROUP (ECTG)

Enclosure 1 provides a listing of the report numbers, the related employee concerns, and the previous submittal dates if applicable. To assist you in your review of these reports, Enclosure 2 provides a comparison between the ECTG Writer's Guide reconunended report format and the transmitted reports.

Enclosure 3 transmits the revised final element reports for 4 elements addressing Sequoyah Nuclear Plant employee concerns in the following categories:

Operations - 1 report Construction - 2 reports Material Control - 1 report As indicated by the report cover sheets, these reports have completed final review by the Senior Review Panel and the Employee Concern Task Group management.

Please telephone Martha Martin at (615) 365-3587 (Watts Bar) if you have any questions.

Very truly yours, TENNESSEE VALLEY AUTHORITY

h. 0! &

J. A. Mcdonald Watts Bar Nuclear Plant Site Licensing Manager cc (See page 2.):

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D s 8703190495 870316 PDR ADOCK 05000327 An Equal Opportunity Employer P PDR

"2 U.S. Nuclear Regulatory Commission ec (Rnclosures):

Nr. James N. Taylor, Director Office of Inspection and Rnforcement U.S. Nuclear Regulatory Commission Washington, D. C. 20555 U.S. Nuclear Regulatory Commission Region II Attn: Mr. Gary Zech 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. B. J. Youngblood, Project Director PWR Project Directorate #4 Division of PWR Licensing - A U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Room 440, 5 Story Phillips Bethesda, Maryland 20814 4512T

.Q Enclosure 1

  • ENCLOSURE 1 Page 1 of 1 SEQUOYAH EMPLOYEE ELEMENT REPORT CONCERN NUNBER ISSUE Construction 11206 XK-85-077-IO4 Unauthorized Work /

(Revised Final) Undocumented Work As Related to Construction NOTE: C011206 was submitted final 10/24/86. This report was revised to incorporate NRC comments.

Construction 17105 IN-85-211-002 Pipe / Fittings As Related (Revised Final) IN-86-282-004 To Construction WI-85-053-012 NOTE: C017105 was submitted final 1/29/87. This report was revised to incorporate NRC comments and SQN's generic review of WBN NCR 6420 into corrective action of report.

Operation 30713 KK-85-062-003 Configuration Control (Revised Final) KK-85-071-N05 BFN-IESC-85-03 IN-85-984-001 NOTE: OP30713 was submitted final 1/9/87. This report was revised to incorporate NRC comments.

Naterial Control 40201 IN-85-463-008 Instruments, Material, (Revised Final) IN-85-463-007 Equipment As It Relates To IN-85-964-003 Purchasing and Requisitions NOTE: NC40201 was submitted final 1/9/87. This report was revised to incorporate NRC comments.

4512T

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Enclosure 2

OPERATIONS CATEGORY E clesura 2 il

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ECTG WRITER'S GUIDE OPERATIONS (OP) ELEMENT REPORTS NOTES / COMMENTS l ,-

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6 1.0 Issue I. Title The brief introduction l Characterization Very brief introduction touches on the source of j the concerns. l l

2.0 Sumary I. Title 1. The Conclusions are i Very brief introduction towards the end of the ,

findings.  ! '

III. Finding (Conclusions) 2. The Conclusions  !

services as a sumary l l of the findings. i l I

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3.0 Evaluators Cover Sheet 1. The printed name of the l  ;

original evaluator (s) l  ;

appears on the cover j sheet. I '

2. The peer reviewer and CEG-H approval signa- l g l tures are also on the j ,.

cover sheet, j l l

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4.0 Evaluation II. Specific Eve.luation  ; l; Process Methodology  :

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5.0 Findings III. Findings 1880T

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l Exclesura 2 OPERATIONS (OP) ELMENT REPORTS NOTES /CONMENTS ECTG WRITER'S GUIDE Root Cause IV. Root Cause 1. At the element level 6.0 the Root Cause-is often (Collective Significance)

.not identifible.

  • 2. Collective significance is not addressed at the .'

element report level.

7.0 Attachments / II. Specific Eva'luation 1. A list of the concerns List of Concerns Methodology with text are included within this section.

2. Other reports are sometimes attached, f

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CONSTRUCTION CATEGORY Enclosure 2 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 Methodology 5.0 Findings IV. Summary of Findings k

6.0 Root Cause V. Root Cause (Collective Significance)** ** Overall Root Cause will

- not ba considered at this k report level.

7.0 Attachments / VIII. Attachmants List of Concerns h

Other items included VI. Corrective Actions h (To be provided by in Construction Element Reports line orgainzations)

VII. Generic Applicability i

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190ST v . . . - _ .- _ ... _ _ . _ _ . . _ _ _ , _ _ _ _ _ . , . _ _ _ _ _ _ _ _ _, _

- .. . - . . . . - . ~ . . .. ..

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MATERIALS CONTROL Enclosura 2 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 Methodology k

5.0 Findings IV. Summary of Findings

-L 6.0 Root Cause V. Root Cause g (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 l-

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Enclosure 3

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