ML20203M895

Forwards Revised Welding Project Generic Employee Concern Evaluation Repts WP-04-SQN Through WP-07-SQN,WP-09-SQN, WP-11-SQN,WP-13-SQN,WP-16-SQN & WP-17-SQN

ML20203M895
Person / Time
Site:	Sequoyah
Issue date:	09/03/1986
From:	Mcdonald J TENNESSEE VALLEY AUTHORITY
To:	Youngblood B Office of Nuclear Reactor Regulation
Shared Package
ML20203M897	List: ML20203M895 ML20203M901 ML20203M904 ML20203M909 ML20203M912 ML20203M916 ML20203M924 ML20203M929 ML20203M931 ML20203M936 ML20203M941 ML20203M944
References
NUDOCS 8609050141
Download: ML20203M895 (3)

Text

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TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant P. O. Box 800 Spring City, Tennessee 37381 September 3, 1986 Director of Nuclear Reactor Regulation Attention: 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

Dear Mr. Youngblood:

In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority '

') 50-328

SUBJECT:

EMPLOYEE CONCERN TASK GROUP Enclosure 1 to this letter transmits for NRC review 10 reports addressing Sequoyah generic employee concerns in the welding category. As you are aware, t.he employee concerns in the welding area are being resolved as a part of the comprehensive review of the entire TVA Welding Program. As such, the format of these reports differs from the ECTG Writer's Guide recommended format. To ass'ist in your review of these reports, Attachment 1 provides a comparison between the Writer's Guide format and the welding reports. It should be noted that these reports are consistent with the Welding Project's evaluation and reporting process. Earlier drafts of these reports have been previously provided to the NRC in the resolution of the welding technical issue. These reports, in their present format, have been reviewed by B. D. Llaw of your staff.

Specifically enclosed for your review are 10 Welding Project generic evaluation reports. Attachment 2 provides a listing of the report number and the related generic employee concerns. The evaluation of the Sequoyah I

site-specific concerns have been documented in the Welding Project's Program Report for Sequoyah (Phase 1 and 2). These site-specific reparts have not yet l been approved by the Senior Review Panel and will be submitted at a later date.

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' Please feel free to contact Martha Martin at FTS 857-3587 (Watts Bar) if you have any questions.

Very truly yours, 4

TENNESSEE VALLEY AUTHORITY j v ,

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(

. A. Mcdonald /k

! Site Licensing Manager l Watts Bar Nuclear Plant '\

8609050141 860903 PDR ADOCK 05000327 P PDR an Equal Opportunity Employer l -

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Nr. Youngblood September 3, 1986 cc: U.S. Nuclear Regulatory Commission Region II Attn: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

• Enclosure provided to site resident Mr. James M. Taylor, Director (w/o enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. B. D. Liaw, Branch Chief (w/o enclosure)

U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Room T-1132 Bethesda, Maryland 20814

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Attcchmelt 1 ^

ECTG WRITER'S GUIDE NSRS/ERT* WELD PROJECT (WP) REPORTS NOTES /CONNENTS 1.0 Issue Background Info Issues Addressed Characterization (Section I) By Concerns (Section II) l 2.0 List Of Concerns Background Info Scope of Evaluation (Section I) (Section I and Att-1) 3.0 Evaluators Coversheet Coversheet 4.0 Evaluation Scope Not Delineated As Part Process (Section II) Of The WP Reports however it is addressed as part of the Weld Projects Program Manual See Attached WP-03 Procedure.

5.0 Findings Findings Validity or (Section III) Substantiation (Section III) 6.0 Root Cause** Conclusion and Validity or *** Note that recommendations are not included in element reports under the current ECTG program.

and Conclusion Recommendations Substantiation ** Overall Root Cause will (Section IV)*** (Section III) not be considered at this report level.

• The Weld Project has endorsed a numbsr of ERT Reports and general issue level reports as adequately addressing the concerns at this level for SQN.

_ . .