ML20004F965

From kanterella
Jump to navigation Jump to search
Forwards Revision to Applicant Response to NUREG-0737,Item I.C.5 in App H of Fsar,Re Procedures for Feedback of Operating Experience.Description Provided Should Resolve Concerns Re Timeliness of LER Reviews
ML20004F965
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 06/22/1981
From: Colbert W
DETROIT EDISON CO.
To: Kintner L
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.5, TASK-TM EF2-53-862, NUDOCS 8106260355
Download: ML20004F965 (2)


Text

.

MI E Ciis O n E s i!! " "

June 22, 1981 EF2 - 53,862 [

s

/g g

Mr. L. L. Kintner

.; [.

g%

i, Division of Project Management N

I) p[.'

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission

\\/

?

Washington, D. C.

20555

'C.

4.*'

~

i.m ee of

Dear Mr. Kintner:

Reference:

Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket.No. 50-341

Subject:

Procedures for Feed,back of Operating Exper.ence - NUREG-0737, Item I.C.5 The attachment is submitted as a revision of Detroit Edison's response'to item I.C.5.in Appendix H to the FSAR.

This responds to a position by the Licensee Qualification Branch LQB-5.

We believe-that the summary description provided should resolve the concerns regarding the timeliness of LER reviews.

If considered. acceptable we will amend the FSAR accordingly and will-provide detailed procedures describing the feedback process three months prior to fuel load.

Sincerely, Wh.$b W. F. Colbert Technical Director Enrico Fermi 2 go l a

WFC/AEW:j1 Wg Attachment cc:

B. Little 81062603S g g

4<

  • 6 w

b H.1.C.5.3 Detroit Edison Position I~

'The Tedhnical' Engineer (Nuclear..

.tetion) has the responsibility to assure that all Enrico Fermi 2 License Event Reports (LER'S)

- are reviewed by the On Site Review Orgaaization.(ORS 0).

On pro-cedural matters requiring urgent attentioJ ha can convene on

'ORSO meeting on-shE;t notice to obtain a cc mittee resolution

- on the plant operation., plant maintenance, and other plant work activities. 'LER's that are deemed significant by OSRO and lead to design changes,'aust be submitted to the LER coordinator for.

7 further analysis, and affected personnel as well as the Independent Review i

and Audit Group (IRAG) will. be informed of the ORSO action.

The.LER coordinator will review all plant a ER's.

The: significant Enrico Fermi 2 LER's will be. forwarded to the appropriate nuclear enginsering staff for in-depth review, analysis, and recosamendations for changes t_o improve plant operations.. The rtriew will be given priorities based on the urgency indicat ed by the Technical Engineer -

-or ORSO. Before implementation of the recommended action by the-LER coordinator to upgrade nuclear safety by. resolution of the LER, a review by.IRAG and a-final approval by the. Manager

. Nuclear

. Operations must.be obtained. If warranted, expedious review by the IRAG will be accomplished by conducting special reviews for these significant LER's assigned an urgent priotity by the Technical Engineer

.or OSRO.=

It will be the LER coordinators rasponsibility to ensure k

that all: recommended actions are implemented in a prompt and timely

manner.

With regard to LER's generated at other nuclear. stations, it is

. = Detroit Edison's intention to use the INP0/NSAC program "Significant

- Event Evaluation -and Information Network" (SEE-IN) to identify the significant LER's.: Once SEE-IN identifies a significant event, the event will be processed by the LER coordinator in the same manner

~

. as an Enrico Fermi 2 significant LER.

l; The function' of the LER coordinator will be audited periodically to ensure effective implementation of the fee.iback program.

Detailed procedures relative to the processing of LER's will be furn-ished no later than 90 days before fuel loading. The emphasis of j

these procedures will. be to provide a controlled and expeditous process that assures a thorough analysis and review of all significant

'LER's to be implemented, as well as, ensuring that personnel are fully informed and trained.in the recommended actions that will improve-plant safety and operations. The detailed procedures will be responsive to the NRC position as stated in paragraph H.1.C.5.2.

r

=

F 3

(.

l E

g r!:;

.m.-___,4

_