ML20010A456

Final Significant Const Deficiency Rept Re Inadequate Electrical Insulation on ex-core Neutron Flux Detectors, Originally Reported on 810306.Removal of Insulation,Rewrap & Subsequent Testing Performed Per C-E Procedure P9270-105W

ML20010A456
Person / Time
Site:	Waterford
Issue date:	07/31/1981
From:	Aswell D LOUISIANA POWER & LIGHT CO.
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, W3K-81-0277, W3K-81-277, NUDOCS 8108110446
Download: ML20010A456 (3)

Text

'

Dm6s0,srce)

!E H Q's F-i le Popp I

LOUISIANA 24a 0-ONoe Swa POWER & LIGHT R O. BOX 6008

• NEW ORLTANS. LOUISIANA 70174. (504) 366-2345 Su?$8vsY$

'S" July 31, 1981 Vca Present-Power Pnxbetson W3K 0277 Q-3-A35.07.22 Q-3-A35.02.01 Mr. K. V. Seyfrit, Director, Region IV U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Final Report of Significant Construction Deficiency No. 22

" Inadequate Ele:trical Insulation on Ex-Core Neutron Flux Detectors"

Reference:

LP&L Letter to USNRC W3K-81-0105 dated March 6, 1981

Dear Mr. Seyfrit:

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final Report of Significant Construction Deficiency No. 22,

" Inadequate Electrical Insulation on Ex-Core Neutron Flux Det ctors."

If you have any questions, please advise.

I y, E

Very truly yours,

\\

NM Q

'?,

N wa D. L. Aswell 2

QJ

"[

q $$

3-l DLA/LLB/grf N8

/~-

? Ee' h'

Attachment Qf)

Vg

/"

cc:

1) Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with 15 copies of report) 36N 3

2) Director

/

f/ I Office of Management Information and Program Control U. S. Nuclear Regulatory Commission l

Washington, D. C. 20555 (with 1 copy of report) 8108110446 810731 PDR ADOCK 05000382; S

PDR l

f

~

l

.O LOUISIANA POWER 6 LIGHT COMPANY WATERFORD SES UNIT No. 3 j.

b Final Report of Significant Construction Deficiency No. 22 i;

Inadequate Electrical Insulation on Ex-Core Neutron Flux Detectors

.f [/-

Re.'ewed by 7

/&

/Date' R.J./F hiser - SYte Manager

'/

fl '

'2tf }/

~

Reviewed by r

J il1F - Pr ject Superintendent

//

/Ifate fM?

M d[

Reviewed by

_ 'nsing fngineer Date J. 7 art "Proj ect Li Reviewed by 30 R. A. HSrtnett - Q. A. Site Supervisor bate _

July 29, 1981

'l 6.--

e

~

-J

+

+=

FINAL REPORT SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 22

+-

" INADEQUATE ELECTRICAL INSULATION ON EX-CORE NEUTRON FLUX DETECTORS" kh INTRODUCTION Th is report is submitted pursuant to 10CFR50.55(e).

It describes deficiencies in the electrical insulation of the Ex-Core Neutron Flux Detectors. This

[j ptoblem is considered reportable under the requirements of 10CFR50.55(e). To i

the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pursuant to 10CFR21.

,a DESCRIPTION Combustion Engineering Incorporated (C.E.) notified the Ebasco Site Manager, through letter No. C-CS-9270-263 dated 12/24/80, that the present insula-tion between the Ex-Core Detector and the holder assembly (Astroquartz) is inadequate to maintain proper electrical insulation over the life of the

?

detector and that the insulation will be replaced by a more durable material (Refrasil).

The removal of the insulation and the rewrap and subsequent testing of the Refrasil insulation was performed in accordance with approved Combustion Engineering procedures.

SAFETY IMPLICATIONS Based on the information submitted, Licensing has determined that this con-dition is a reportable incident because if the insulation had not been re-placed, electrical contact could develcp between the detector and the holder assembly.

This could lead to performance degradation and/or total loss of the detector.

Siace these detectors are used as input to the Reactor Protective System (RPS) to initiate Ergineered Safety Features (ESF) if off-normal conditions are dete-ted, taeir uncompromised operation is required.

Therefore, the presence of inadeqeate insulation could result in a degrada-tion of safety-related systems.

CORRECTIVE ACTION Completion of repairs was accomplished on July 20, 1981, and performed in accordance with Combustion Engineering Procedure P9270-105W.

The repairs were conducted at the Waterford 3 Site and were inspected and documented by Combustion Engineering as required by their QA/QC Program.

3 e

b-f-h

.