ML20028B583

From kanterella
Jump to navigation Jump to search
Final Rept of Potentially Reportable Deficiency 92 Re Design of Maint Hatch Shield Door Seal Sys.Initially Reported on 821019.Condition Not Reportable Under 10CFR50.55(e) Because Change Initiated to Upgrade Sys to safety-related Design
ML20028B583
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/22/1982
From: Maurin L
LOUISIANA POWER & LIGHT CO.
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, 92, W3I82-0107, W3I82-107, NUDOCS 8212030048
Download: ML20028B583 (2)


Text

~

.f*

.a . f.

u, +

_OUISI AN A f u2 oct onot S1ncer i i '

POWER & LIGHT / P O BOX B000

  • NEW ORLEANS. LOUISIANA 70* At . (504) 366 2345

$NNIYS '

L. V; MAURIN November .22, 1982.' ' vice President ',

Nuclear Operot%s

% W3I82-0107 j Q-3-AJ5.07 t ,

Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission , .

611 Ryan Plaza Drive, Suite 1000 d s,

Arlington, Texas 76012 i

SUBJECT:

Waterford SES Unit No. 3 I Docket No. 50-382 Potentially Reportable Deficiency No. 92 .

" Design of the Maintenance Hatch Shield Door Scal System" Final Report '

REFERENCE:

Telecon from M. A. Livesay (LP&L) to L. Martirs (NRC) on October 19, 1982  ;

s

. \

Dear Mr. Collins:

r On October 19, 1982 a problem with the design of the maintenance hatch shield door seal system was reported to your office as Potentfally Reportable Deficiency #92. This letter is to inform you that after further eraluation, this specific problem is not considered to be repor::abiq purslant to the requirements of 10CFR50.55(e) for the following reas7n:

1 As originally designed and soproved for constructiot, the Maintenance Hatch Shield Door (MHSD) Seal System was a single non-qualified (i.e., non-safety-related) air supply system to maintain the MHSD itflatable seals. Prior to delivery of the non-safety-related equipment, the question of acceptability of the original design was raised in Construction Engineering Information Request IC-244. It was concluded that the apprcred design was not 9dequate and that the system would have to be upgraded to a safety -related design. As a result, a design change was initiated to revise the system to a safety-related design. i The NRC was notified o f the condition because a non-safety-ralated seal system control panel was received on site. This condition has ben determined to be not reportable because the design change was initiated prior ^to receipt of the panel and it was not installed. The non-safety-related systen did not represent the final design. All equipment instc11ations will be based on the new safety-related design.

Very truly yours,

[ 7 8212030048 821122 .

/g g:: .

PDR ADOCK 05000382 ~ ,

S PDR L. 'i. Maurin /

LVM/ MAL:keh -

l

f -( , .

i s , g~,. .

et

  • f, t

, , Mr. John T. Collins W3182-0107

- Page 2 s

5 cc: Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 h?

s

\,, Director Office of Management U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 s

E. Blake t 's s ,

4 W. Stevenson b 5 u , * '.',a g ,, i

  • . s I'

}

t 4

/

6 s ,

,