ML20024F313

Responds to NRC 830627 Ltr Re Violations Noted in IE Insp Rept 50-416/83-22.Corrective Actions:Procedure 01-304 Will Be Revised & Addl Training Provided

ML20024F313
Person / Time
Site:	Grand Gulf
Issue date:	08/08/1983
From:	Dale L MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20024F309	List: ML20024F313
References
AECM-83-0427, AECM-83-427, NUDOCS 8309090264
Download: ML20024F313 (2)

Text

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MISSISSIPPI POWER & LIGHT COMPANY

]- Helping Build Mississippi P. O. B O X 164 0, J A C K S O N, MISSISSIPPI 39205 EuMMMdds August 8, 1983 NUCLEAR PRODUCTION DEPARTMENT  ;-

CO .O Office of Inspection & Enforcement

$  ;- :t.

U. S. Nuclear Regulatory Commission ,p r.;7 Region II CD CL 101 Marietta St., N. W., Suite 2900 **

' '( '

Atlanta, Georgia 30303 # Y. ' '

Attention: Mr. J. P. O'Reilly, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File: 0260/15525/15526

1. E. Report 416/83-22 of May 23 - 27, 1983 AECM-83/0427

Reference:

MAEC-83/0195, dated June 27, 1983.

This letter provides our response to NRC Violation 416/83-22-01 transmitted by your letter of June 27, 1983. The due date for this response was extended to August 8, 1983 during a telephone discussion with Mr. Paul Fredrickson of your office.

Yours truly, L. F. Dale Manager of Nuclear Services LFD:ay i Attachment cc: Mr. J. B. Richard (w/a)

Mr. R. B. McGehee (w/o)

Mr. T. B. Conner (w/o)

Mr. G. B. Taylor (w/o)

Mr. Richard C. DeYoung, Director (w/a)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 8309090264 830816 DR ADOCK 05000416 PDR Member Middle South Utilities System k a

v A) 16

• . Attachment to AECM-83/0427 RESPONSE '-( NRC VIOLATION 416/83-22-01 I. ADMISSION OR DENIAL OF TnE ALLEGED VIOLATION Mississippi Power & Light Company (MP&L) admits to the alleged violation.

II. THE REASONS FOR THE VIOLATION IF ADMITTED The_ individuals performing the evaluations did not properly differentiate the meanings 'of the questions in paragraphs (1) and (ii). Consequently, they believed the requirement was adequately met by referencing paragraph (1) when answering paragraph (ii).

III. THE CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED The subject DCP's have' been re-evaluated and an adequate basis for determination that they do not constitute an unreviewed safety question (USQ) has been provided. It should be noted that the original reviewers did not reach erroneous conclusions, but rather, failed to properly document the rationale for their conclusions.

Additional training was provided to members of the Nuclear Plant

Engineering (NPE) staff on format and content of USQ determinations.

IV. CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS NPE Procedure 01-304 will be revised to provide additional instructions

'for the conduct of these reviews. NPE. personnel responsible for conducting these reviews will receive instruction on the revised procedure._

As a. matter of further information, a subcommittee of the MP&L Corporate Safety Review Committee has reviewed approximately 600-700 USQ determinations associated.with various changes.and tests. Those that the subcommittee believed did not contain sufficient documentation to support the conclusion-have been returned in order to have'the justification strengthened. This process is ongoing in accordance with Technical.

Specification _ requirements.

-V. THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED

=The revision to NPE' Procedure 01-304 will be issued and instruction on

. Its content will be complete by September 15, 1983.

_ .